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| {{Adams
| | #REDIRECT [[TSTF-09-10, TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b, Sections B 3.8.3 - B 3.10.10 (End)]] |
| | number = ML090850627
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| | issue date = 03/18/2009
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| | title = Transmittal of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b, Sections 3.1.1 - 3.7.5
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| | author name = Gambrell R, Messina J, Raidy T, Schrader K
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| | author affiliation = B & W Owners Group, BWR Owners Group, Combustion Engineering Owners Group, PWR Owners Group, Technical Specifications Task Force, Westinghouse Owners Group
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| | addressee name =
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| | addressee affiliation = NRC/Document Control Desk, NRC/NRR
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| | docket = PROJ0753
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| | license number =
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| | contact person =
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| | case reference number = TSTF-09-10, TSTF-425, Rev 3
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| | document report number = BWROG-88, Rev. 0, TSTF-425, Rev 3
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| | package number = ML090850642
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| | document type = Letter type:TSTF, Technical Specifications
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| | page count = 478
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| | project =
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| | stage = Request
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| }}
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| =Text=
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| {{#Wiki_filter:TECHNICAL SPECIFICATIONS TASK FORCE TSTF A JOINT OWNERS GROUP ACTIVITY March 18, 2009 TSTF-09-10 PROJ0753 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
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| ==SUBJECT:==
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| Transmittal of TSTF-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b"
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| ==Dear Sir or Madam:==
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| Enclosed for NRC review is TSTF-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b." TSTF-425 is applicable to all reactor types.
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| TSTF-425 was revised at the request of the NRC to be consistent with the draft model Safety Evaluation published in the December 5, 2008 Notice for Comment.
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| The NRC's review of TSTF-425 was granted a fee waiver in the NRC letter to A. R. Pietrangelo dated January 10, 2003. We request that the NRC review of the revision to TSTF-425 continue to be granted a fee waiver pursuant to the provisions of 10 CFR 170.11. Specifically, the request is to support NRC generic regulatory improvements (risk management technical specifications),
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| in accordance with 10 CFR 170.11(a)(1)(iii).
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| Should you have any questions, please do not hesitate to contact us.
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| Kenneth J. Schrader (PWROG/W) John Messina (BWROG)
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| Thomas W. Raidy (PWROG/CE) Reene' Gambrell (PWROG/B&W)
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| Enclosure cc: Robert Elliott, Technical Specifications Branch, NRC Joseph Williams, Special Projects Branch, NRC 11921 Rockville Pike, Suite 100, Rockville, MD 20852 Phone: 301-984-4400, Fax: 301-984-7600 Administered by EXCEL Services Corporation
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 Technical Specification Task Force Improved Standard Technical Specifications Change Traveler Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b NUREGs Affected: 1430 1431 1432 1433 1434 Classification 1) Technical Change Recommended for CLIIP?: Yes Correction or Improvement: Improvement NRC Fee Status: Exempt Benefit: Reduces Testing Industry
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| ==Contact:==
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| John Messina, (330) 384-5878, jmessina@firstenergycorp.com 1.0 Description The proposed change relocates all periodic Surveillance Frequencies to licensee control. Revisions to the Surveillance Frequencies will be made in accordance with a new program, the Surveillance Frequency Control Program, which is added to the Administrative Controls.
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| 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 2.0 Proposed Change The proposed change relocates all periodic Surveillance Frequencies from the Technical Specifications and places the Frequencies under licensee control in accordance with a new program, the Surveillance Frequency Control Program. All Surveillance Frequencies are relocated except:
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| * Frequencies that reference other approved programs for the specific interval (such as the Inservice Testing Program or the Primary Containment Leakage Rate Testing Program);
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| * Frequencies that are purely event driven (e.g., Each time the control rod is withdrawn to the full out position);
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| * Frequencies that are event-driven but have a time component for performing the surveillance on a one-time basis once the event occurs (e.g., within 24 hours after thermal power reaching 95% RTP);
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| and
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| * Frequencies that are related to specific conditions (e.g., battery degradation, age, and capacity) or conditions for the performance of a surveillance requirement (e.g., drywell to suppression chamber differential pressure decrease).
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| The definition of "Staggered Test Basis" in Section 1.1, "Definitions," is placed in brackets. Plants that adopt TSTF-425 will no longer use this defined term in the Technical Specifications and should remove it from Section 1.1.
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| A new Administrative Controls Program is added as Specification 5.5.15 (NUREG-1433 and -1434) or Specification 5.5.18 (NUREG-1430, -1431, and 1432). The program is called the Surveillance Frequency Control Program and describes the requirements for a program to control changes to the relocated Surveillance Frequencies.
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| The Bases for each Surveillance are revised to state that the Frequency is set in accordance with the Surveillance Frequency Control Program. These Bases changes reflect the changes made to the Technical Specifications and do not substantially contribute to the understanding of the implementation of the proposed Technical Specification requirements. Therefore, we recommend that the Consolidated Line Item Improvement Process (CLIIP) model application for TSTF-425 not reference the submittal of revised Bases pages. Additionally, this will significantly reduce the size of the plant-specific license amendment requests to adopt TSTF-425.
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| Various editorial changes are made to the Bases as needed to facilitate the addition of the Bases changes.
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| Some Surveillance Bases did not contain a discussion of the Frequency. In these cases, Bases describing the current Frequency were added based on the Bases for similar Surveillances. These instances are noted in the markup along with the source of the text.
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| 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3
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| ===3.0 Background===
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| The NRC has been reviewing and granting improvements to the Improved Standard Technical Specifications (ISTS) based, at least in part, on probabilistic risk analysis insights. Typically, the proposed improvements involved a relaxation of one or more Completion Times or Surveillance Frequencies in the TS.
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| In August 1995, the NRC adopted a final policy statement on the use of probabilistic risk assessment (PRA) methods, which included the following regarding the expanded use of PRA (Ref. 1).
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| * The use of PRA technology should be increased in all regulatory matters to the extent supported by the state of the art in PRA methods and data and in a manner that complements the NRC's deterministic approach and supports the NRC's traditional defense-in-depth philosophy.
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| * PRA and associated analyses (e.g., sensitivity studies, uncertainty analyses, and importance measures) should be used in regulatory matters, where practical within the bounds of the state of the art, to reduce unnecessary conservatism associated with current regulatory requirements, regulatory guides, licensee commitments, and staff practices. Where appropriate, PRA should be used to support the proposal of additional regulatory requirements in accordance with 10 CFR 50.109 (Backfit Rule). Appropriate procedures for including PRA in the process for changing regulatory requirements should be developed and followed. It is, of course, understood that the intent of this policy is that existing rules and regulations shall be complied with unless these rules and regulations are revised.
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| * PRA evaluations in support of regulatory decisions should be as realistic as practicable and appropriate supporting data should be publicly available for review.
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| * The Commission's safety goals for nuclear power plants and subsidiary numerical objectives are to be used with appropriate consideration of uncertainties in making regulatory judgments on need for proposing and backfitting new generic requirements on nuclear power plant licensees.
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| In its approval of the policy statement, the Commission articulated its expectation that implementation of the policy statement will improve the regulatory process in three areas: foremost, through safety decisionmaking enhanced by the use of PRA insights; through more efficient use of agency resources; and through a reduction in unnecessary burdens on licensees.
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| This Traveler is being submitted by the industry Technical Specification Task Force (TSTF) in cooperation with the Nuclear Energy Institute (NEI) Risk Informed Technical Specification Task Force (RITSTF) to implement RITSTF Initiative 5b, "Relocate Surveillance Test Intervals to Licensee Control."
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| On September 28, 2006, the NRC approved the lead plant submittal for Initiative 5b for Limerick Generating Station. On that same date, the NRC provided the final Safety Evaluation for the methodology document, NEI 04-10. The NRC's approval of NEI 04-10 stated that is was only applicable to BWRs and that it did not approve relocation of requirements to perform Surveillances on a Staggered Test Basis. Revision 1 of NEI 04-10 addresses these two restrictions and supports the changes proposed in this Traveler.
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| 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 4.0 Technical Analysis The control of changes to the relocated Surveillance Frequencies will be in accordance with the Surveillance Frequency Control Program. That Program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met. In addition,
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| : a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.
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| : b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies,"
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| Revision 1.
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| : c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.
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| The referenced document, NEI 04-10, provides a detailed description of the process to be followed when considering changes to a Surveillance Frequency. NEI 04-10 will be reviewed and approved by the NRC separately from this Traveler. Therefore, the process is not discussed further here.
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| Some Surveillance Frequencies are performed at a given periodicity on a STAGGERED TEST BASIS and are written similar to "18 months on a STAGGERED TEST BASIS." The phrase "on a STAGGERED TEST BASIS" is also relocated to licensee control under the Surveillance Frequency Control Program and the defined term, which would no longer be used in the TS, is removed from Section 1.1. The purpose of specifying certain Surveillances to be performed on a STAGGERED TEST BASIS is to increase the reliability of the tested system by identifying common mode failures more quickly. Relocating the Frequency requirement to perform Surveillances on a STAGGERED TEST BASIS along with the periodicity allows licensees the flexibility to adjust the Frequency based on operational experience and risk assessment results.
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| For example, a Frequency may be extended but include a new requirement to perform the Surveillance on a STAGGERED TEST BASIS to reflect a higher risk associated with common mode failures. Conversely, a Frequency may be changed to eliminate a requirement to perform the Surveillance on a STAGGERED TEST BASIS due to a lower risk or operational experience associated with common mode failure. NEI 04-10 contains information to support the correct risk modeling of Surveillance Frequencies with and without a requirement to perform the Surveillance on a STAGGERED TEST BASIS.
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| The relocation of the specified Surveillance Frequencies to licensee control is consistent with Regulatory Guides 1.174 (Ref. 2) and 1.177 (Ref. 3). Regulatory Guide 1.177 provides guidance for changing Surveillance Frequencies and Completion Times. However, for allowable risk changes associated with Surveillance Frequency extensions, it refers to Regulatory Guide 1.174, which provides quantitative risk acceptance guidelines for changes to core damage frequency (CDF) and large early release frequency (LERF).
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| Regulatory Guide 1.174 provides additional guidelines that have been adapted in the risk-informed methodology for controlling changes to Surveillance Frequencies.
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| Regulatory Guide 1.174 identifies five key safety principles to be met for all risk-informed applications and to be explicitly addressed in risk-informed plant program change applications.
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| : 1. The proposed change meets the current regulations unless it is explicitly related to a requested exemption or rule change.
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| 10 CFR 50.36(c) (Ref. 10) provides that TS will include items in the following categories:
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| (3) Surveillance requirements. Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
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| This change proposes to relocate various Frequencies for the performance of the Surveillance Requirements to a licensee-controlled program using an NRC approved methodology for control of the Surveillance Frequencies. The Surveillance Requirements themselves will remain in TS. This is consistent with other NRC approved TS changes in which the Surveillance Frequencies are not under NRC control, such as Surveillances that are performed in accordance with the Inservice Testing Program or the Primary Containment Leakage Rate Testing Program, where the Frequencies vary based on the past performance of the subject components. Thus, this proposed change meets criterion 1 above.
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| : 2. The proposed change is consistent with the defense-in-depth philosophy.
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| As described in Position 2.2.1.1 of Regulatory Guide 1.174, consistency with the defense-in-depth philosophy is maintained if:
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| * A reasonable balance is preserved among prevention of core damage, prevention of containment failure, and consequence mitigation.
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| * Over-reliance on programmatic activities to compensate for weaknesses in plant design is avoided.
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| * System redundancy, independence, and diversity are preserved commensurate with the expected frequency, consequences of challenges to the system, and uncertainties (e.g., no risk outliers).
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| * Defenses against potential common cause failures are preserved, and the potential for the introduction of new common cause failure mechanisms is assessed.
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| * Independence of barriers is not degraded.
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| * Defenses against human errors are preserved.
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| * The intent of the General Design Criteria in 10 CFR Part 50, Appendix A is maintained.
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| These defense-in-depth objectives apply to all risk-informed applications, and for some of the issues involved (e.g., no over-reliance on programmatic activities and defense against human errors), it is fairly straightforward to apply them to this proposed change. The use of the multiple risk metrics of CDF and LERF and controlling the change resulting from the implementation of this initiative would maintain a balance between prevention of core damage, prevention of containment failure, and consequence mitigation. Redundancy, diversity, and independence of safety systems are considered as part of the risk categorization to ensure that these qualities are not adversely affected. Independence of barriers and defense against common cause failures are also considered in the categorization. The improved understanding of the relative importance of plant components to risk resulting from the development of this program promotes an improved overall understanding of how the SSCs contribute to the plant's defense-in-depth.
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| : 3. The proposed change maintains sufficient safety margins.
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| Conformance with this principle is assured since SSC design, operation, testing methods, and acceptance criteria specified in the Codes and Standards or alternatives approved for use by the NRC, will continue to be met as described in the plant licensing basis (e.g., FSAR, or Technical Specifications Bases). Also, the safety analysis acceptance criteria in the licensing basis (e.g., FSAR, supporting analyses, etc.) are met with the proposed change.
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| 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3
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| : 4. When proposed changes result in an increase in core damage frequency or risk, the increases should be small and consistent with the intent of the Commission's Safety Goal Policy Statement.
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| NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," will require that changes in core damage frequency or risk are small and consistent with the intent of the Commission's Safety Goal Policy.
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| : 5. The impact of the proposed change should be monitored using performance measurement strategies.
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| NEI 04-10 will require that changes in Surveillance Frequencies be monitored using performance management strategies.
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| Therefore, the proposed change is consistent with the guidance in Regulatory Guide 1.174.
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| 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 5.0 Regulatory Analysis 5.1 No Significant Hazards Consideration The TSTF has evaluated whether or not a significant hazards consideration is involved with the proposed generic change by focusing on the three standards set forth in 10 CFR 50.92, Issuance of amendment, as discussed below:
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| : 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
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| Response: No.
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| The proposed change relocates the specified Frequencies for periodic Surveillance Requirements to licensee control under a new Surveillance Frequency Control Program. Surveillance Frequencies are not an initiator to any accident previously evaluated. As a result, the probability of any accident previously evaluated is not significantly increased. The systems and components required by the Technical Specifications for which the Surveillance Frequencies are relocated are still required to be operable, meet the acceptance criteria for the Surveillance Requirements, and be capable of performing any mitigative function assumed in the accident analysis. As a result, the consequences of any accident previously evaluated are not significantly increased.
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| Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
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| : 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
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| Response: No.
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| No new or different accidents result from utilizing the proposed change. The changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. In addition, the changes do not impose any new or different requirements. The changes do not alter assumptions made in the safety analysis. The proposed changes are consistent with the safety analysis assumptions and current plant operating practice.
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| Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
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| : 3. Does the proposed change involve a significant reduction in a margin of safety?
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| Response: No.
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| The proposed change is administrative in nature, does not negate any existing requirement, and does not adversely affect existing plant safety margins or the reliability of the equipment assumed to operate in the safety analysis. As such, there are no changes being made to safety analysis assumptions, safety limits or limiting safety system settings that would adversely affect plant safety as a result of the proposed change.
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| Margins of safety are unaffected by relocation of the surveillance test intervals to a licensee-controlled program.
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| Therefore, the proposed change does not involve a significant reduction in a margin of safety.
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| 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 Based on the above, the TSTF concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified.
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| 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 5.2 Applicable Regulatory Requirements/Criteria Section 182a of the Atomic Energy Act of 1954, as amended (the Act) requires applicants for nuclear power plant operating licenses to include the TS as part of the license. The Commissions regulatory requirements related to the content for the TS are set forth in 10 CFR 50.36. That regulation requires that the TS include items in eight specific categories. The categories are: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; (5) administrative controls; (6) decommissioning; (7) initial notification; and (8) written reports.
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| However, the regulation does not specify the particular requirements to be included in a plants TS.
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| The proposed change is consistent with other Surveillance Frequencies in the ISTS. In several instances, the ISTS do not specify a particular surveillance Frequency but rather state the Frequency as "In accordance with the Inservice Testing Program." The Inservice Testing (IST) Program references Section XI of the ASME Boiler and Pressure Vessel Code for the surveillance intervals. The surveillance intervals are based on the plant's IST Program which implements the ASME Code. Within the IST program, the actual surveillance intervals vary based on the performance of the individual components. In other instances, the TS again do not specify a particular surveillance Frequency but instead require that the surveillance be performed "in accordance with the Primary Containment Leakage Rate Testing Program." The Primary Containment Leakage Rate Testing Program references 10 CFR 50, Appendix J, Option B, which allows performance based testing. The surveillance Frequency varies based on the past performance of the subject components.
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| The proposed TS changes are administrative in nature. Relocation of the Surveillance Frequencies from the TS to a licensee-controlled program does not affect the plant design, hardware, or system operation and will not affect the ability of the plant to perform its design function in mitigating the consequences of a postulated design basis accident. Therefore, the proposed change does not adversely affect nuclear safety or plant operations.
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| In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the approval of the proposed change will not be inimical to the common defense and security or to the health and safety of the public.
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| 6.0 Environmental Consideration A review has determined that the proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.
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| 7.0 References
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| : 1. USNRC, "Use of Probabilistic Risk Assessment Methods in Nuclear Activities: Final Policy Statement,"
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| Federal Register, Vol. 60, p. 42622, August 16, 1995.
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| : 2. Regulatory Guide 1.174, Revision 1, An Approach for using Probabilistic Risk Assessment in Risk-Informed Decisions On Plant-Specific Changes to the Licensing Basis, November 2002.
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| 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3
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| : 3. Regulatory Guide 1.177, An Approach for Plant-Specific Risk-Informed Decisionmaking: Technical Specification, August 1998 Revision History OG Revision 0 Revision Status: Closed Revision Proposed by: BWROG Revision
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| == Description:==
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| Original Issue Owners Group Review Information Date Originated by OG: 21-May-04 Owners Group Comments (No Comments)
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| Owners Group Resolution: Approved Date: 09-Jun-04 TSTF Review Information TSTF Received Date: 26-May-04 Date Distributed for Review 26-May-04 OG Review Completed: BWOG WOG CEOG BWROG TSTF Comments:
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| (No Comments)
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| TSTF Resolution: Approved Date: 09-Jun-04 NRC Review Information NRC Received Date: 31-Aug-04 NRC Comments: Date of NRC Letter: 05-Feb-07 In a letter dated 2/5/2007, the NRC closed the TAC for TSTF-425, Rev. 0, pending receipt of TSTF-425, Rev. 1.
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| Final Resolution: Superceded by Revision Final Resolution Date: 05-Feb-07 TSTF Revision 1 Revision Status: Closed Revision Proposed by: TSTF Revision
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| == Description:==
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| TSTF-425, Revision 1, includes the following changes:
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| : 1) Markups for NUREG-1430, 1431, and 1432, are added.
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| : 2) The Surveillance Frequency Control Program wording is revised to be consistent with that approved for Limerick, the lead plant.
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| : 3) The references to NEI 04-10 are revised to provide the final title of the report and to reference Revision 1.
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| TSTF Review Information 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 TSTF Revision 1 Revision Status: Closed TSTF Received Date: 01-Mar-07 Date Distributed for Review 01-Mar-07 OG Review Completed: BWOG WOG CEOG BWROG TSTF Comments:
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| (No Comments)
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| TSTF Resolution: Approved Date: 11-Apr-07 NRC Review Information NRC Received Date: 16-Apr-07 NRC Comments: Date of NRC Letter: 02-Oct-07 NRC provided an RAI on 10/2/07.
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| Final Resolution: NRC Requests Changes: TSTF Will Revise Final Resolution Date: 02-Oct-07 TSTF Revision 2 Revision Status: Closed Revision Proposed by: NRC Revision
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| == Description:==
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| Revision 2 was developed in response to an NRC Request for Additional Information dated October 2, 2007.
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| The following items were affected:
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| NUREG-1433 SR 3.8.6.6, and NUREG-1434 SR 3.8.6.6 NUREG-1433 SR 3.6.1.1.2 NUREG-1431 and -1432 SR 3.4.14.1 NUREG-1430, -1431, and -1432 SR 3.4.14.1 Bases NUREG-1430 SR 3.6.3.5 NUREG-1431 SR 3.3.1.8 NUREG-1430 SR 3.3.16.2 and 3.3.16.
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| NUREG-1431 SR 3.3.1.4 Bases NUREG-1431 SR 3.3.1.5 Bases NUREG-1431 SR 3.3.2.3 Bases NUREG-1431 SR 3.6.8.4 Bases NUREG-1432 SR 3.6.11.4 Bases NUREG-1434 SR 3.3.6.2.6 Bases TSTF Review Information TSTF Received Date: 31-Dec-07 Date Distributed for Review 31-Dec-07 OG Review Completed: BWOG WOG CEOG BWROG TSTF Comments:
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| (No Comments)
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| TSTF Resolution: Approved Date: 17-Jan-08 NRC Review Information NRC Received Date: 17-Jan-08 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 TSTF Revision 2 Revision Status: Closed NRC Comments:
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| The NRC requested that the TSTF revise TSTF-425 to reflect the wording and conditions in the published model Safety Evaluation.
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| Final Resolution: NRC Requests Changes: TSTF Will Revise Final Resolution Date: 30-Jan-09 TSTF Revision 3 Revision Status: Active Revision Proposed by: NRC Revision
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| == Description:==
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| The NRC requested that the TSTF revise TSTF-425 to reflect the wording and conditions in the Notice for Comment model Safety Evaluation.
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| Specifically, the list of conditions that would exclude the relocation of a Surveillance Frequency to the Surveillance Frequency Control Program was revised to be consistent with the list provided in the model Safety Evaluation. The two existing conditions were restated as three conditions with no change in intent. A fourth condition was added that excluded the relocation of Frequencies related to specific conditions.
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| Consistent with the new fourth condition, Surveillance Requirement 3.8.6.6 in all five ISTS NUREGs was revised so that the normal performance Frequency of 60 months may be relocated to the Surveillance Frequency Control Program, but the accelerated second and third Frequencies are not relocated.
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| TSTF Review Information TSTF Received Date: 17-Mar-09 Date Distributed for Review 17-Mar-09 OG Review Completed: BWOG WOG CEOG BWROG TSTF Comments:
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| (No Comments)
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| TSTF Resolution: Approved Date: 18-Mar-09 NRC Review Information NRC Received Date: 18-Mar-09 Affected Technical Specifications 1.1 Definitions Change
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| == Description:==
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| Bracket the definition of "Staggered Test Basis" SR 3.4.1.1 RCS Pressure, Temperature, and Flow DNB Limits NUREG(s)- 1430 1431 1432 Only SR 3.4.1.1 RCS Pressure, Temperature, and Flow DNB Limits NUREG(s)- 1430 1431 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.4.1.2 RCS Pressure, Temperature, and Flow DNB Limits NUREG(s)- 1430 1431 1432 Only SR 3.4.1.2 Bases RCS Pressure, Temperature, and Flow DNB Limits NUREG(s)- 1430 1431 1432 Only SR 3.4.1.3 RCS Pressure, Temperature, and Flow DNB Limits NUREG(s)- 1430 1431 1432 Only SR 3.4.1.3 Bases RCS Pressure, Temperature, and Flow DNB Limits NUREG(s)- 1430 1431 1432 Only SR 3.4.1.4 RCS Pressure, Temperature, and Flow DNB Limits NUREG(s)- 1430 1431 1432 Only SR 3.4.1.4 Bases RCS Pressure, Temperature, and Flow DNB Limits NUREG(s)- 1430 1431 1432 Only SR 3.4.2.1 RCS Minimum Temperature for Criticality NUREG(s)- 1430 1431 1432 Only SR 3.4.2.1 Bases RCS Minimum Temperature for Criticality NUREG(s)- 1430 1431 1432 Only SR 3.4.3.1 RCS P/T limits NUREG(s)- 1430 1431 1432 Only SR 3.4.3.1 Bases RCS P/T limits NUREG(s)- 1430 1431 1432 Only SR 3.4.4.1 RCS Loops - MODES 1 and 2 NUREG(s)- 1430 1431 1432 Only SR 3.4.4.1 Bases RCS Loops - MODES 1 and 2 NUREG(s)- 1430 1431 1432 Only SR 3.4.5.1 RCS Loops - MODE 3 NUREG(s)- 1430 1431 1432 Only SR 3.4.5.1 Bases RCS Loops - MODE 3 NUREG(s)- 1430 1431 1432 Only SR 3.4.5.2 RCS Loops - MODE 3 NUREG(s)- 1430 1431 1432 Only SR 3.4.5.2 Bases RCS Loops - MODE 3 NUREG(s)- 1430 1431 1432 Only SR 3.4.6.1 RCS Loops - MODE 4 NUREG(s)- 1430 1431 1432 Only SR 3.4.6.1 Bases RCS Loops - MODE 4 NUREG(s)- 1430 1431 1432 Only SR 3.4.6.2 RCS Loops - MODE 4 NUREG(s)- 1430 1431 1432 Only SR 3.4.6.2 Bases RCS Loops - MODE 4 NUREG(s)- 1430 1431 1432 Only SR 3.4.7.1 RCS Loops - MODE 5, Loops Filled NUREG(s)- 1430 1431 1432 Only SR 3.4.7.1 Bases RCS Loops - MODE 5, Loops Filled NUREG(s)- 1430 1431 1432 Only SR 3.4.7.2 RCS Loops - MODE 5, Loops Filled NUREG(s)- 1430 1431 1432 Only SR 3.4.7.2 Bases RCS Loops - MODE 5, Loops Filled NUREG(s)- 1430 1431 1432 Only SR 3.4.7.3 RCS Loops - MODE 5, Loops Filled NUREG(s)- 1430 1431 1432 Only SR 3.4.7.3 Bases RCS Loops - MODE 5, Loops Filled NUREG(s)- 1430 1431 1432 Only SR 3.4.8.1 RCS Loops - MODE 5, Loops Not Filled NUREG(s)- 1430 1431 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.4.8.1 Bases RCS Loops - MODE 5, Loops Not Filled NUREG(s)- 1430 1431 1432 Only SR 3.4.8.2 RCS Loops - MODE 5, Loops Not Filled NUREG(s)- 1430 1431 1432 Only SR 3.4.8.2 Bases RCS Loops - MODE 5, Loops Not Filled NUREG(s)- 1430 1431 1432 Only SR 3.4.9.1 Pressurizer NUREG(s)- 1430 1431 1432 Only SR 3.4.9.1 Bases Pressurizer NUREG(s)- 1430 1431 1432 Only SR 3.4.9.2 Pressurizer NUREG(s)- 1430 1431 1432 Only SR 3.4.9.2 Bases Pressurizer NUREG(s)- 1430 1431 1432 Only SR 3.4.9.3 Pressurizer NUREG(s)- 1430 1431 1432 Only SR 3.4.9.3 Bases Pressurizer NUREG(s)- 1430 1431 1432 Only SR 3.4.11.1 Pressurizer PORV NUREG(s)- 1430 1431 1432 Only SR 3.4.11.1 Bases Pressurizer PORV NUREG(s)- 1430 1431 1432 Only SR 3.4.11.2 Pressurizer PORV NUREG(s)- 1430 1431 1432 Only SR 3.4.11.2 Bases Pressurizer PORV NUREG(s)- 1430 1431 1432 Only SR 3.4.11.3 Pressurizer PORV NUREG(s)- 1430 1431 1432 Only SR 3.4.11.3 Bases Pressurizer PORV NUREG(s)- 1430 1431 1432 Only SR 3.4.12.1 LTOP System NUREG(s)- 1430 1431 1432 Only SR 3.4.12.1 Bases LTOP System NUREG(s)- 1430 1431 1432 Only SR 3.4.12.2 LTOP System NUREG(s)- 1430 1431 1432 Only SR 3.4.12.2 Bases LTOP System NUREG(s)- 1430 1431 1432 Only SR 3.4.12.3 LTOP System NUREG(s)- 1430 1431 1432 Only SR 3.4.12.3 Bases LTOP System NUREG(s)- 1430 1431 1432 Only SR 3.4.12.4 LTOP System NUREG(s)- 1430 1431 1432 Only SR 3.4.12.4 Bases LTOP System NUREG(s)- 1430 1431 1432 Only SR 3.4.12.5 LTOP System NUREG(s)- 1430 1431 1432 Only SR 3.4.12.5 Bases LTOP System NUREG(s)- 1430 1431 1432 Only SR 3.4.12.6 LTOP System NUREG(s)- 1430 1431 1432 Only SR 3.4.12.6 Bases LTOP System NUREG(s)- 1430 1431 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.4.12.7 LTOP System NUREG(s)- 1430 1431 1432 Only SR 3.4.12.7 Bases LTOP System NUREG(s)- 1430 1431 1432 Only SR 3.4.13.1 RCS Operational LEAKAGE NUREG(s)- 1430 1431 1432 Only SR 3.4.13.1 Bases RCS Operational LEAKAGE NUREG(s)- 1430 1431 1432 Only SR 3.4.13.2 RCS Operational LEAKAGE NUREG(s)- 1430 1431 1432 Only SR 3.4.13.2 Bases RCS Operational LEAKAGE NUREG(s)- 1430 1431 1432 Only SR 3.4.14.1 RCS PIV Leakage NUREG(s)- 1430 1431 1432 Only SR 3.4.14.1 Bases RCS PIV Leakage NUREG(s)- 1430 1431 1432 Only SR 3.4.14.2 RCS PIV Leakage NUREG(s)- 1430 1431 1432 Only SR 3.4.14.2 Bases RCS PIV Leakage NUREG(s)- 1430 1431 1432 Only SR 3.4.14.3 RCS PIV Leakage NUREG(s)- 1430 1431 1432 Only SR 3.4.14.3 Bases RCS PIV Leakage NUREG(s)- 1430 1431 1432 Only SR 3.4.15.1 RCS Leakage Detection Instrumentation NUREG(s)- 1430 1431 1432 Only SR 3.4.15.1 Bases RCS Leakage Detection Instrumentation NUREG(s)- 1430 1431 1432 Only SR 3.4.15.2 RCS Leakage Detection Instrumentation NUREG(s)- 1430 1431 1432 Only SR 3.4.15.2 Bases RCS Leakage Detection Instrumentation NUREG(s)- 1430 1431 1432 Only SR 3.4.15.3 RCS Leakage Detection Instrumentation NUREG(s)- 1430 1431 1432 Only SR 3.4.15.3 Bases RCS Leakage Detection Instrumentation NUREG(s)- 1430 1431 1432 Only SR 3.4.15.4 RCS Leakage Detection Instrumentation NUREG(s)- 1430 1431 1432 Only SR 3.4.15.4 Bases RCS Leakage Detection Instrumentation NUREG(s)- 1430 1431 1432 Only SR 3.4.16.1 RCS Specific Activity NUREG(s)- 1430 1431 1432 Only SR 3.4.16.1 Bases RCS Specific Activity NUREG(s)- 1430 1431 1432 Only SR 3.4.16.2 RCS Specific Activity NUREG(s)- 1430 1431 1432 Only SR 3.4.16.2 Bases RCS Specific Activity NUREG(s)- 1430 1431 1432 Only SR 3.4.16.3 RCS Specific Activity NUREG(s)- 1430 1431 1432 Only SR 3.4.16.3 Bases RCS Specific Activity NUREG(s)- 1430 1431 1432 Only SR 3.7.2.2 MSIVs NUREG(s)- 1430 1431 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.7.2.2 Bases MSIVs NUREG(s)- 1430 1431 1432 Only SR 3.8.1.1 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.1 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.2 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.2 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.3 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.3 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.4 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.4 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.5 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.5 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.6 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.6 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.7 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.7 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.8 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.8 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.9 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.9 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.10 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.10 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.11 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.11 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.12 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.12 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.13 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.13 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.8.1.14 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.14 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.15 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.15 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.16 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.16 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.17 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.17 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.18 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.18 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.19 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.19 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.20 AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.1.20 Bases AC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.3.1 Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1430 1431 1432 Only SR 3.8.3.1 Bases Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1430 1431 1432 Only SR 3.8.3.2 Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1430 1431 1432 Only SR 3.8.3.2 Bases Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1430 1431 1432 Only SR 3.8.3.4 Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1430 1431 1432 Only SR 3.8.3.4 Bases Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1430 1431 1432 Only SR 3.8.3.5 Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1430 1431 1432 Only SR 3.8.3.5 Bases Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1430 1431 1432 Only SR 3.8.4.1 DC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.4.1 Bases DC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.4.2 DC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.4.2 Bases DC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.4.3 DC Sources - Operating NUREG(s)- 1430 1431 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.8.4.3 Bases DC Sources - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.6.1 Battery Parameters NUREG(s)- 1430 1431 1432 Only SR 3.8.6.1 Bases Battery Parameters NUREG(s)- 1430 1431 1432 Only SR 3.8.6.2 Battery Parameters NUREG(s)- 1430 1431 1432 Only SR 3.8.6.2 Bases Battery Parameters NUREG(s)- 1430 1431 1432 Only SR 3.8.6.3 Battery Parameters NUREG(s)- 1430 1431 1432 Only SR 3.8.6.3 Bases Battery Parameters NUREG(s)- 1430 1431 1432 Only SR 3.8.6.4 Battery Parameters NUREG(s)- 1430 1431 1432 Only SR 3.8.6.4 Bases Battery Parameters NUREG(s)- 1430 1431 1432 Only SR 3.8.6.5 Battery Parameters NUREG(s)- 1430 1431 1432 Only SR 3.8.6.5 Bases Battery Parameters NUREG(s)- 1430 1431 1432 Only SR 3.8.6.6 Battery Parameters NUREG(s)- 1430 1431 1432 Only SR 3.8.6.6 Bases Battery Parameters NUREG(s)- 1430 1431 1432 Only SR 3.8.7.1 Inverters - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.7.1 Bases Inverters - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.8.1 Inverters - Shutdown NUREG(s)- 1430 1431 1432 Only SR 3.8.8.1 Bases Inverters - Shutdown NUREG(s)- 1430 1431 1432 Only SR 3.8.9.1 Distribution Systems - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.9.1 Bases Distribution Systems - Operating NUREG(s)- 1430 1431 1432 Only SR 3.8.10.1 Distribution Systems - Shutdown NUREG(s)- 1430 1431 1432 Only SR 3.8.10.1 Bases Distribution Systems - Shutdown NUREG(s)- 1430 1431 1432 Only SR 3.9.1.1 Boron Concentration NUREG(s)- 1430 1431 1432 Only SR 3.9.1.1 Bases Boron Concentration NUREG(s)- 1430 1431 1432 Only 5.5.18 Surveillance Frequency Control Program NUREG(s)- 1430 1431 1432 Only Change
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| == Description:==
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| New Program SR 3.4.12.8 LTOP System NUREG(s)- 1430 1431 Only SR 3.4.12.8 Bases LTOP System NUREG(s)- 1430 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.9.3.1 Containment Penetrations NUREG(s)- 1430 1432 Only SR 3.9.3.1 Bases Containment Penetrations NUREG(s)- 1430 1432 Only SR 3.9.3.2 Containment Penetrations NUREG(s)- 1430 1432 Only SR 3.9.3.2 Bases Containment Penetrations NUREG(s)- 1430 1432 Only SR 3.1.1.1 SDM NUREG(s)- 1430 Only SR 3.1.1.1 Bases SDM NUREG(s)- 1430 Only SR 3.1.2.1 Reactivity Balance NUREG(s)- 1430 Only SR 3.1.2.1 Bases Reactivity Balance NUREG(s)- 1430 Only SR 3.1.4.1 CONTROL ROD Group Alignment Limits NUREG(s)- 1430 Only SR 3.1.4.1 Bases CONTROL ROD Group Alignment Limits NUREG(s)- 1430 Only SR 3.1.4.2 CONTROL ROD Group Alignment Limits NUREG(s)- 1430 Only SR 3.1.4.2 CONTROL ROD Group Alignment Limits NUREG(s)- 1430 Only SR 3.1.4.2 Bases CONTROL ROD Group Alignment Limits NUREG(s)- 1430 Only SR 3.1.4.2 Bases CONTROL ROD Group Alignment Limits NUREG(s)- 1430 Only SR 3.1.5.1 Safety Rod Insertion Limits NUREG(s)- 1430 Only SR 3.1.5.1 Safety Rod Insertion Limits NUREG(s)- 1430 Only SR 3.1.6.1 APSR Alignment Limits NUREG(s)- 1430 Only SR 3.1.6.1 Bases APSR Alignment Limits NUREG(s)- 1430 Only SR 3.1.7.1 Postion Indicator Channels NUREG(s)- 1430 Only SR 3.1.7.1 Bases Postion Indicator Channels NUREG(s)- 1430 Only SR 3.1.8.1 PHYSICS TEST Exceptions - MODE 1 NUREG(s)- 1430 Only SR 3.1.8.1 Bases PHYSICS TEST Exceptions - MODE 1 NUREG(s)- 1430 Only SR 3.1.8.2 PHYSICS TEST Exceptions - MODE 1 NUREG(s)- 1430 Only SR 3.1.8.2 Bases PHYSICS TEST Exceptions - MODE 1 NUREG(s)- 1430 Only SR 3.1.8.3 PHYSICS TEST Exceptions - MODE 1 NUREG(s)- 1430 Only SR 3.1.8.3 Bases PHYSICS TEST Exceptions - MODE 1 NUREG(s)- 1430 Only SR 3.1.8.4 PHYSICS TEST Exceptions - MODE 1 NUREG(s)- 1430 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.1.8.4 Bases PHYSICS TEST Exceptions - MODE 1 NUREG(s)- 1430 Only SR 3.1.9.1 PHYSICS TESTS Exceptions - Mode 2 NUREG(s)- 1430 Only SR 3.1.9.1 Bases PHYSICS TESTS Exceptions - Mode 2 NUREG(s)- 1430 Only SR 3.1.9.2 PHYSICS TESTS Exceptions - Mode 2 NUREG(s)- 1430 Only SR 3.1.9.2 Bases PHYSICS TESTS Exceptions - Mode 2 NUREG(s)- 1430 Only SR 3.1.9.3 PHYSICS TESTS Exceptions - Mode 2 NUREG(s)- 1430 Only SR 3.1.9.3 Bases PHYSICS TESTS Exceptions - Mode 2 NUREG(s)- 1430 Only SR 3.2.1.1 Regulating Rod Insertion Limits NUREG(s)- 1430 Only SR 3.2.1.1 Bases Regulating Rod Insertion Limits NUREG(s)- 1430 Only SR 3.2.1.2 Regulating Rod Insertion Limits NUREG(s)- 1430 Only SR 3.2.1.2 Bases Regulating Rod Insertion Limits NUREG(s)- 1430 Only SR 3.2.1.3 Regulating Rod Insertion Limits NUREG(s)- 1430 Only SR 3.2.1.3 Bases Regulating Rod Insertion Limits NUREG(s)- 1430 Only SR 3.2.2.1 ASPR Insertion Limits NUREG(s)- 1430 Only SR 3.2.2.1 ASPR Insertion Limits NUREG(s)- 1430 Only SR 3.2.3.1 AXIAL POWER IMBLANCE Operating Limits NUREG(s)- 1430 Only SR 3.2.3.1 Bases AXIAL POWER IMBLANCE Operating Limits NUREG(s)- 1430 Only SR 3.2.4.1 QPT NUREG(s)- 1430 Only SR 3.2.4.1 Bases QPT NUREG(s)- 1430 Only SR 3.3.1.1 RPS Instrumentation NUREG(s)- 1430 Only SR 3.3.1.1 Bases RPS Instrumentation NUREG(s)- 1430 Only SR 3.3.1.2 RPS Instrumentation NUREG(s)- 1430 Only SR 3.3.1.2 Bases RPS Instrumentation NUREG(s)- 1430 Only SR 3.3.1.3 RPS Instrumentation NUREG(s)- 1430 Only SR 3.3.1.3 Bases RPS Instrumentation NUREG(s)- 1430 Only SR 3.3.1.4 RPS Instrumentation NUREG(s)- 1430 Only SR 3.3.1.4 Bases RPS Instrumentation NUREG(s)- 1430 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.1.5 RPS Instrumentation NUREG(s)- 1430 Only SR 3.3.1.5 Bases RPS Instrumentation NUREG(s)- 1430 Only SR 3.3.1.6 RPS Instrumentation NUREG(s)- 1430 Only SR 3.3.1.6 Bases RPS Instrumentation NUREG(s)- 1430 Only SR 3.3.3.1 RPS-RTM NUREG(s)- 1430 Only SR 3.3.3.1 Bases RPS-RTM NUREG(s)- 1430 Only SR 3.3.4.1 CRD Trip Devices NUREG(s)- 1430 Only SR 3.3.4.1 Bases CRD Trip Devices NUREG(s)- 1430 Only SR 3.3.5.1 ESFAS Instrumentation NUREG(s)- 1430 Only SR 3.3.5.1 Bases ESFAS Instrumentation NUREG(s)- 1430 Only SR 3.3.5.2 ESFAS Instrumentation NUREG(s)- 1430 Only SR 3.3.5.2 Bases ESFAS Instrumentation NUREG(s)- 1430 Only SR 3.3.5.3 ESFAS Instrumentation NUREG(s)- 1430 Only SR 3.3.5.3 Bases ESFAS Instrumentation NUREG(s)- 1430 Only SR 3.3.5.4 ESFAS Instrumentation NUREG(s)- 1430 Only SR 3.3.5.4 Bases ESFAS Instrumentation NUREG(s)- 1430 Only SR 3.3.6.1 ESFAS Manual Initiation NUREG(s)- 1430 Only SR 3.3.6.1 Bases ESFAS Manual Initiation NUREG(s)- 1430 Only SR 3.3.7.1 ESFAS Automatic Actuation Logic NUREG(s)- 1430 Only SR 3.3.7.1 Bases ESFAS Automatic Actuation Logic NUREG(s)- 1430 Only SR 3.3.8.1 EDG LOPS NUREG(s)- 1430 Only SR 3.3.8.1 Bases EDG LOPS NUREG(s)- 1430 Only SR 3.3.8.2 EDG LOPS NUREG(s)- 1430 Only SR 3.3.8.2 Bases EDG LOPS NUREG(s)- 1430 Only SR 3.3.8.3 EDG LOPS NUREG(s)- 1430 Only SR 3.3.8.3 Bases EDG LOPS NUREG(s)- 1430 Only SR 3.3.8.4 EDG LOPS NUREG(s)- 1430 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.8.4 Bases EDG LOPS NUREG(s)- 1430 Only SR 3.3.9.1 Source Range Neutron Flux NUREG(s)- 1430 Only SR 3.3.9.1 Bases Source Range Neutron Flux NUREG(s)- 1430 Only SR 3.3.9.2 Source Range Neutron Flux NUREG(s)- 1430 Only SR 3.3.9.2 Bases Source Range Neutron Flux NUREG(s)- 1430 Only SR 3.3.10.1 Intermediate Range Neutron Flux NUREG(s)- 1430 Only SR 3.3.10.1 Bases Intermediate Range Neutron Flux NUREG(s)- 1430 Only SR 3.3.10.2 Intermediate Range Neutron Flux NUREG(s)- 1430 Only SR 3.3.10.2 Bases Intermediate Range Neutron Flux NUREG(s)- 1430 Only SR 3.3.11.1 EFIC System Instrumentation NUREG(s)- 1430 Only SR 3.3.11.1 Bases EFIC System Instrumentation NUREG(s)- 1430 Only SR 3.3.11.2 EFIC System Instrumentation NUREG(s)- 1430 Only SR 3.3.11.2 Bases EFIC System Instrumentation NUREG(s)- 1430 Only SR 3.3.11.3 EFIC System Instrumentation NUREG(s)- 1430 Only SR 3.3.11.3 Bases EFIC System Instrumentation NUREG(s)- 1430 Only SR 3.3.11.4 EFIC System Instrumentation NUREG(s)- 1430 Only SR 3.3.11.4 Bases EFIC System Instrumentation NUREG(s)- 1430 Only SR 3.3.12.1 EFIC Manual Initiation NUREG(s)- 1430 Only SR 3.3.12.1 Bases EFIC Manual Initiation NUREG(s)- 1430 Only SR 3.3.13.1 EFIC Logic NUREG(s)- 1430 Only SR 3.3.13.1 Bases EFIC Logic NUREG(s)- 1430 Only SR 3.3.14.1 EFIC-EFW-Vector Valve Logic NUREG(s)- 1430 Only SR 3.3.14.1 EFIC-EFW-Vector Valve Logic NUREG(s)- 1430 Only SR 3.3.15.1 RB Purge Isolation - High Radiation NUREG(s)- 1430 Only SR 3.3.15.1 Bases RB Purge Isolation - High Radiation NUREG(s)- 1430 Only SR 3.3.15.2 RB Purge Isolation - High Radiation NUREG(s)- 1430 Only SR 3.3.15.2 Bases RB Purge Isolation - High Radiation NUREG(s)- 1430 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.15.3 RB Purge Isolation - High Radiation NUREG(s)- 1430 Only SR 3.3.15.3 Bases RB Purge Isolation - High Radiation NUREG(s)- 1430 Only SR 3.3.16.1 Control Room Isolation - High Radiation NUREG(s)- 1430 Only SR 3.3.16.1 Bases Control Room Isolation - High Radiation NUREG(s)- 1430 Only SR 3.3.16.2 Control Room Isolation - High Radiation NUREG(s)- 1430 Only SR 3.3.16.2 Bases Control Room Isolation - High Radiation NUREG(s)- 1430 Only SR 3.3.16.3 Control Room Isolation - High Radiation NUREG(s)- 1430 Only SR 3.3.16.3 Bases Control Room Isolation - High Radiation NUREG(s)- 1430 Only SR 3.3.17.1 PAM Instrumentation NUREG(s)- 1430 Only SR 3.3.17.1 Bases PAM Instrumentation NUREG(s)- 1430 Only SR 3.3.17.2 PAM Instrumentation NUREG(s)- 1430 Only SR 3.3.17.2 Bases PAM Instrumentation NUREG(s)- 1430 Only SR 3.3.18.1 Remote Shutdown System NUREG(s)- 1430 Only SR 3.3.18.1 Bases Remote Shutdown System NUREG(s)- 1430 Only SR 3.3.18.2 Remote Shutdown System NUREG(s)- 1430 Only SR 3.3.18.2 Bases Remote Shutdown System NUREG(s)- 1430 Only SR 3.3.18.3 Remote Shutdown System NUREG(s)- 1430 Only SR 3.3.18.3 Bases Remote Shutdown System NUREG(s)- 1430 Only SR 3.5.1.1 CFTs NUREG(s)- 1430 Only SR 3.5.1.1 Bases CFTs NUREG(s)- 1430 Only SR 3.5.1.2 CFTs NUREG(s)- 1430 Only SR 3.5.1.2 Bases CFTs NUREG(s)- 1430 Only SR 3.5.1.3 CFTs NUREG(s)- 1430 Only SR 3.5.1.3 Bases CFTs NUREG(s)- 1430 Only SR 3.5.1.4 CFTs NUREG(s)- 1430 Only SR 3.5.1.4 Bases CFTs NUREG(s)- 1430 Only SR 3.5.1.5 CFTs NUREG(s)- 1430 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.5.1.5 Bases CFTs NUREG(s)- 1430 Only SR 3.5.2.1 ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.1 Bases ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.2 ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.2 Bases ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.3 ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.3 Bases ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.5 ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.5 Bases ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.6 ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.6 Bases ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.7 ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.7 Bases ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.8 ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.8 Bases ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.9 ECCS - Operating NUREG(s)- 1430 Only SR 3.5.2.9 Bases ECCS - Operating NUREG(s)- 1430 Only SR 3.5.4.1 BWST NUREG(s)- 1430 Only SR 3.5.4.1 Bases BWST NUREG(s)- 1430 Only SR 3.5.4.2 BWST NUREG(s)- 1430 Only SR 3.5.4.2 Bases BWST NUREG(s)- 1430 Only SR 3.5.4.3 BWST NUREG(s)- 1430 Only SR 3.5.4.3 Bases BWST NUREG(s)- 1430 Only SR 3.6.2.2 Containment Air Locks NUREG(s)- 1430 Only SR 3.6.2.2 Bases Containment Air Locks NUREG(s)- 1430 Only SR 3.6.3.1 Containment Isolation Valves NUREG(s)- 1430 Only SR 3.6.3.1 Bases Containment Isolation Valves NUREG(s)- 1430 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.3.2 Containment Isolation Valves NUREG(s)- 1430 Only SR 3.6.3.2 Bases Containment Isolation Valves NUREG(s)- 1430 Only SR 3.6.3.3 Containment Isolation Valves NUREG(s)- 1430 Only SR 3.6.3.3 Bases Containment Isolation Valves NUREG(s)- 1430 Only SR 3.6.3.5 Containment Isolation Valves NUREG(s)- 1430 Only SR 3.6.3.5 Bases Containment Isolation Valves NUREG(s)- 1430 Only SR 3.6.3.6 Containment Isolation Valves NUREG(s)- 1430 Only SR 3.6.3.6 Bases Containment Isolation Valves NUREG(s)- 1430 Only SR 3.6.3.7 Containment Isolation Valves NUREG(s)- 1430 Only SR 3.6.3.7 Bases Containment Isolation Valves NUREG(s)- 1430 Only SR 3.6.3.8 Containment Isolation Valves NUREG(s)- 1430 Only SR 3.6.3.8 Bases Containment Isolation Valves NUREG(s)- 1430 Only SR 3.6.4.1 Containment Pressure NUREG(s)- 1430 Only SR 3.6.4.1 Bases Containment Pressure NUREG(s)- 1430 Only SR 3.6.5.1 Containment Temperature NUREG(s)- 1430 Only SR 3.6.5.1 Bases Containment Temperature NUREG(s)- 1430 Only SR 3.6.6.1 Containment Spray and Cooling Systems NUREG(s)- 1430 Only SR 3.6.6.1 Bases Containment Spray and Cooling Systems NUREG(s)- 1430 Only SR 3.6.6.2 Containment Spray and Cooling Systems NUREG(s)- 1430 Only SR 3.6.6.2 Bases Containment Spray and Cooling Systems NUREG(s)- 1430 Only SR 3.6.6.3 Containment Spray and Cooling Systems NUREG(s)- 1430 Only SR 3.6.6.3 Bases Containment Spray and Cooling Systems NUREG(s)- 1430 Only SR 3.6.6.5 Containment Spray and Cooling Systems NUREG(s)- 1430 Only SR 3.6.6.5 Bases Containment Spray and Cooling Systems NUREG(s)- 1430 Only SR 3.6.6.6 Containment Spray and Cooling Systems NUREG(s)- 1430 Only SR 3.6.6.6 Bases Containment Spray and Cooling Systems NUREG(s)- 1430 Only SR 3.6.6.7 Containment Spray and Cooling Systems NUREG(s)- 1430 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.6.7 Bases Containment Spray and Cooling Systems NUREG(s)- 1430 Only SR 3.6.6.8 Containment Spray and Cooling Systems NUREG(s)- 1430 Only SR 3.6.6.8 Bases Containment Spray and Cooling Systems NUREG(s)- 1430 Only SR 3.6.7.1 Spray Additive System NUREG(s)- 1430 Only SR 3.6.7.1 Bases Spray Additive System NUREG(s)- 1430 Only SR 3.6.7.2 Spray Additive System NUREG(s)- 1430 Only SR 3.6.7.2 Bases Spray Additive System NUREG(s)- 1430 Only SR 3.6.7.3 Spray Additive System NUREG(s)- 1430 Only SR 3.6.7.3 Bases Spray Additive System NUREG(s)- 1430 Only SR 3.6.7.4 Spray Additive System NUREG(s)- 1430 Only SR 3.6.7.4 Bases Spray Additive System NUREG(s)- 1430 Only SR 3.6.7.5 Spray Additive System NUREG(s)- 1430 Only SR 3.6.7.5 Bases Spray Additive System NUREG(s)- 1430 Only SR 3.7.3.2 [MFSVs, MFCVs, and Associated SFCVs] NUREG(s)- 1430 Only SR 3.7.3.2 Bases [MFSVs, MFCVs, and Associated SFCVs] NUREG(s)- 1430 Only SR 3.7.4.1 AVVs NUREG(s)- 1430 Only SR 3.7.4.1 Bases AVVs NUREG(s)- 1430 Only SR 3.7.4.2 AVVs NUREG(s)- 1430 Only SR 3.7.4.2 Bases AVVs NUREG(s)- 1430 Only SR 3.7.5.1 EFW System NUREG(s)- 1430 Only SR 3.7.5.1 Bases EFW System NUREG(s)- 1430 Only SR 3.7.5.3 EFW System NUREG(s)- 1430 Only SR 3.7.5.3 Bases EFW System NUREG(s)- 1430 Only SR 3.7.5.4 EFW System NUREG(s)- 1430 Only SR 3.7.5.4 Bases EFW System NUREG(s)- 1430 Only SR 3.7.5.6 EFW System NUREG(s)- 1430 Only SR 3.7.5.6 Bases EFW System NUREG(s)- 1430 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.7.5.7 EFW System NUREG(s)- 1430 Only SR 3.7.5.7 Bases EFW System NUREG(s)- 1430 Only SR 3.7.6.1 CST NUREG(s)- 1430 Only SR 3.7.6.1 Bases CST NUREG(s)- 1430 Only SR 3.7.7.1 CCW System NUREG(s)- 1430 Only SR 3.7.7.1 Bases CCW System NUREG(s)- 1430 Only SR 3.7.7.2 CCW System NUREG(s)- 1430 Only SR 3.7.7.2 Bases CCW System NUREG(s)- 1430 Only SR 3.7.7.3 CCW System NUREG(s)- 1430 Only SR 3.7.7.3 Bases CCW System NUREG(s)- 1430 Only SR 3.7.8.1 SWS NUREG(s)- 1430 Only SR 3.7.8.1 Bases SWS NUREG(s)- 1430 Only SR 3.7.8.2 SWS NUREG(s)- 1430 Only SR 3.7.8.2 Bases SWS NUREG(s)- 1430 Only SR 3.7.8.3 SWS NUREG(s)- 1430 Only SR 3.7.8.3 Bases SWS NUREG(s)- 1430 Only SR 3.7.9.1 UHS NUREG(s)- 1430 Only SR 3.7.9.1 Bases UHS NUREG(s)- 1430 Only SR 3.7.9.2 UHS NUREG(s)- 1430 Only SR 3.7.9.2 Bases UHS NUREG(s)- 1430 Only SR 3.7.9.3 UHS NUREG(s)- 1430 Only SR 3.7.9.3 Bases UHS NUREG(s)- 1430 Only SR 3.7.10.1 CREVS NUREG(s)- 1430 Only SR 3.7.10.1 Bases CREVS NUREG(s)- 1430 Only SR 3.7.10.3 CREVS NUREG(s)- 1430 Only SR 3.7.10.3 Bases CREVS NUREG(s)- 1430 Only SR 3.7.10.4 CREVS NUREG(s)- 1430 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.7.10.4 Bases CREVS NUREG(s)- 1430 Only SR 3.7.10.5 CREVS NUREG(s)- 1430 Only SR 3.7.10.5 Bases CREVS NUREG(s)- 1430 Only SR 3.7.11.1 CREATCS NUREG(s)- 1430 Only SR 3.7.11.1 Bases CREATCS NUREG(s)- 1430 Only SR 3.7.12.1 EVS NUREG(s)- 1430 Only SR 3.7.12.1 Bases EVS NUREG(s)- 1430 Only SR 3.7.12.3 EVS NUREG(s)- 1430 Only SR 3.7.12.3 Bases EVS NUREG(s)- 1430 Only SR 3.7.12.4 EVS NUREG(s)- 1430 Only SR 3.7.12.4 Bases EVS NUREG(s)- 1430 Only SR 3.7.12.5 EVS NUREG(s)- 1430 Only SR 3.7.12.5 Bases EVS NUREG(s)- 1430 Only SR 3.7.13.1 FSPVS NUREG(s)- 1430 Only SR 3.7.13.1 Bases FSPVS NUREG(s)- 1430 Only SR 3.7.13.3 FSPVS NUREG(s)- 1430 Only SR 3.7.13.3 Bases FSPVS NUREG(s)- 1430 Only SR 3.7.13.4 FSPVS NUREG(s)- 1430 Only SR 3.7.13.4 Bases FSPVS NUREG(s)- 1430 Only SR 3.7.13.5 FSPVS NUREG(s)- 1430 Only SR 3.7.13.5 Bases FSPVS NUREG(s)- 1430 Only SR 3.7.14.1 Fuel Storage Pool Water Level NUREG(s)- 1430 Only SR 3.7.14.1 Bases Fuel Storage Pool Water Level NUREG(s)- 1430 Only SR 3.7.15.1 [Spent Fuel Pool Boron Concentration] NUREG(s)- 1430 Only SR 3.7.15.1 Bases [Spent Fuel Pool Boron Concentration] NUREG(s)- 1430 Only SR 3.7.17.1 Secondary Specific Activity NUREG(s)- 1430 Only SR 3.7.17.1 Bases Secondary Specific Activity NUREG(s)- 1430 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.7.18.1 Steam Generator Level NUREG(s)- 1430 Only SR 3.7.18.1 Bases Steam Generator Level NUREG(s)- 1430 Only SR 3.9.1.2 Boron Concentration NUREG(s)- 1430 Only SR 3.9.1.2 Bases Boron Concentration NUREG(s)- 1430 Only SR 3.9.4.1 DHR and Coolant Circulation - High Water Level NUREG(s)- 1430 Only SR 3.9.4.1 Bases DHR and Coolant Circulation - High Water Level NUREG(s)- 1430 Only SR 3.9.5.1 DHR and Coolant Circulation - Low Water Level NUREG(s)- 1430 Only SR 3.9.5.1 Bases DHR and Coolant Circulation - Low Water Level NUREG(s)- 1430 Only SR 3.9.5.2 DHR and Coolant Circulation - Low Water Level NUREG(s)- 1430 Only SR 3.9.5.2 Bases DHR and Coolant Circulation - Low Water Level NUREG(s)- 1430 Only SR 3.9.6.1 Refueling Canal Water Level NUREG(s)- 1430 Only SR 3.9.6.1 Bases Refueling Canal Water Level NUREG(s)- 1430 Only SR 3.4.5.3 RCS Loops - MODE 3 NUREG(s)- 1431 1432 Only SR 3.4.5.3 Bases RCS Loops - MODE 3 NUREG(s)- 1431 1432 Only SR 3.4.6.3 RCS Loops - MODE 4 NUREG(s)- 1431 1432 Only SR 3.4.6.3 Bases RCS Loops - MODE 4 NUREG(s)- 1431 1432 Only SR 3.1.1.1 SDM NUREG(s)- 1431 Only SR 3.1.1.1 Bases SDM NUREG(s)- 1431 Only SR 3.1.2.1 Core Reactivity NUREG(s)- 1431 Only SR 3.1.2.1 Bases Core Reactivity NUREG(s)- 1431 Only SR 3.1.4.1 Rod Group Alignment Limits NUREG(s)- 1431 Only SR 3.1.4.1 Bases Rod Group Alignment Limits NUREG(s)- 1431 Only SR 3.1.4.2 Rod Group Alignment Limits NUREG(s)- 1431 Only SR 3.1.4.2 Bases Rod Group Alignment Limits NUREG(s)- 1431 Only SR 3.1.5.1 Shutdown Bank Insertion Limits NUREG(s)- 1431 Only SR 3.1.5.1 Bases Shutdown Bank Insertion Limits NUREG(s)- 1431 Only SR 3.1.6.2 Control Bank Insertion Limits NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.1.6.2 Bases Control Bank Insertion Limits NUREG(s)- 1431 Only SR 3.1.6.3 Control Bank Insertion Limits NUREG(s)- 1431 Only SR 3.1.6.3 Bases Control Bank Insertion Limits NUREG(s)- 1431 Only SR 3.1.8.2 PHYSICS TESTS Exceptions - MODE 2 NUREG(s)- 1431 Only SR 3.1.8.2 Bases PHYSICS TESTS Exceptions - MODE 2 NUREG(s)- 1431 Only SR 3.1.8.3 PHYSICS TESTS Exceptions - MODE 2 NUREG(s)- 1431 Only SR 3.1.8.3 Bases PHYSICS TESTS Exceptions - MODE 2 NUREG(s)- 1431 Only SR 3.1.8.4 PHYSICS TESTS Exceptions - MODE 2 NUREG(s)- 1431 Only SR 3.1.8.4 Bases PHYSICS TESTS Exceptions - MODE 2 NUREG(s)- 1431 Only SR 3.2.1A.1 FQ(Z) ( CAOC-FXY Methodology) NUREG(s)- 1431 Only SR 3.2.1C.1 FQ(Z) ( CAOC-W(Z) Methodology) NUREG(s)- 1431 Only SR 3.2.1B.1 FQ(Z) ( RAOC-W(Z) Methodology) NUREG(s)- 1431 Only SR 3.2.1A.1 Bases FQ(Z) ( CAOC-FXY Methodology) NUREG(s)- 1431 Only SR 3.2.1C.1 Bases FQ(Z) ( CAOC-W(Z) Methodology) NUREG(s)- 1431 Only SR 3.2.1B.1 Bases FQ(Z) ( RAOC-W(Z) Methodology) NUREG(s)- 1431 Only SR 3.2.1A.2 FQ(Z) ( CAOC-FXY Methodology) NUREG(s)- 1431 Only SR 3.2.1C.2 FQ(Z) ( CAOC-W(Z) Methodology) NUREG(s)- 1431 Only SR 3.2.1B.2 FQ(Z) ( RAOC-W(Z) Methodology) NUREG(s)- 1431 Only SR 3.2.1A.2 Bases FQ(Z) ( CAOC-FXY Methodology) NUREG(s)- 1431 Only SR 3.2.1C.2 Bases FQ(Z) ( CAOC-W(Z) Methodology) NUREG(s)- 1431 Only SR 3.2.1B.2 Bases FQ(Z) ( RAOC-W(Z) Methodology) NUREG(s)- 1431 Only SR 3.2.2.1 FNDH NUREG(s)- 1431 Only SR 3.2.2.1 Bases FNDH NUREG(s)- 1431 Only SR 3.2.3A.1 AFD (CAOC Methodology) NUREG(s)- 1431 Only SR 3.2.3B.1 AFD (RAOC Methodology) NUREG(s)- 1431 Only SR 3.2.3A.1 Bases AFD (CAOC Methodology) NUREG(s)- 1431 Only SR 3.2.3B.1 Bases AFD (RAOC Methodology) NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.2.3A.2 AFD (CAOC Methodology) NUREG(s)- 1431 Only SR 3.2.3A.2 Bases AFD (CAOC Methodology) NUREG(s)- 1431 Only SR 3.2.3A.3 AFD (CAOC Methodology) NUREG(s)- 1431 Only SR 3.2.3A.3 Bases AFD (CAOC Methodology) NUREG(s)- 1431 Only SR 3.2.4.1 QPTR NUREG(s)- 1431 Only SR 3.2.4.1 Bases QPTR NUREG(s)- 1431 Only SR 3.2.4.2 QPTR NUREG(s)- 1431 Only SR 3.2.4.2 Bases QPTR NUREG(s)- 1431 Only SR 3.3.1.1 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.1 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.2 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.2 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.3 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.3 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.4 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.4 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.5 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.5 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.6 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.6 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.7 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.7 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.8 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.8 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.9 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.9 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.10 RTS Instrumentation NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.1.10 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.11 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.11 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.12 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.12 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.13 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.13 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.14 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.14 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.16 RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.1.16 Bases RTS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.1 ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.1 Bases ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.2 ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.2 Bases ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.3 ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.3 Bases ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.4 ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.4 Bases ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.5 ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.5 Bases ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.6 ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.6 Bases ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.7 ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.7 Bases ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.8 ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.8 Bases ESFAS Instrumentation NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.2.9 ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.9 Bases ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.10 ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.2.10 Bases ESFAS Instrumentation NUREG(s)- 1431 Only SR 3.3.3.1 PAM Instrumentation NUREG(s)- 1431 Only SR 3.3.3.1 Bases PAM Instrumentation NUREG(s)- 1431 Only SR 3.3.3.2 PAM Instrumentation NUREG(s)- 1431 Only SR 3.3.3.2 Bases PAM Instrumentation NUREG(s)- 1431 Only SR 3.3.4.1 Remote Shutdown System NUREG(s)- 1431 Only SR 3.3.4.1 Bases Remote Shutdown System NUREG(s)- 1431 Only SR 3.3.4.2 Remote Shutdown System NUREG(s)- 1431 Only SR 3.3.4.2 Bases Remote Shutdown System NUREG(s)- 1431 Only SR 3.3.4.3 Remote Shutdown System NUREG(s)- 1431 Only SR 3.3.4.3 Bases Remote Shutdown System NUREG(s)- 1431 Only SR 3.3.4.4 Remote Shutdown System NUREG(s)- 1431 Only SR 3.3.4.4 Bases Remote Shutdown System NUREG(s)- 1431 Only SR 3.3.5.1 LOP DG Start Instrumentation NUREG(s)- 1431 Only SR 3.3.5.1 Bases LOP DG Start Instrumentation NUREG(s)- 1431 Only SR 3.3.5.2 LOP DG Start Instrumentation NUREG(s)- 1431 Only SR 3.3.5.2 Bases LOP DG Start Instrumentation NUREG(s)- 1431 Only SR 3.3.5.3 LOP DG Start Instrumentation NUREG(s)- 1431 Only SR 3.3.5.3 Bases LOP DG Start Instrumentation NUREG(s)- 1431 Only SR 3.3.6.1 Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.1 Bases Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.2 Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.2 Bases Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.3 Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.6.3 Bases Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.4 Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.4 Bases Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.5 Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.5 Bases Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.6 Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.6 Bases Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.7 Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.7 Bases Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.8 Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.8 Bases Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.9 Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.6.9 Bases Containment Purge and Exhaust Isolation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.1 CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.1 Bases CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.2 CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.2 Bases CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.3 CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.3 Bases CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.4 CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.4 Bases CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.5 CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.5 Bases CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.6 CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.6 Bases CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.7 CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.7 Bases CREFS Actuation Instrumentation NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.7.8 CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.8 Bases CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.9 CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.7.9 Bases CREFS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.8.1 FBACS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.8.1 Bases FBACS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.8.2 FBACS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.8.2 Bases FBACS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.8.3 FBACS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.8.3 Bases FBACS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.8.4 FBACS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.8.4 Bases FBACS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.8.5 FBACS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.8.5 Bases FBACS Actuation Instrumentation NUREG(s)- 1431 Only SR 3.3.9.1 BDPS NUREG(s)- 1431 Only SR 3.3.9.1 Bases BDPS NUREG(s)- 1431 Only SR 3.3.9.2 BDPS NUREG(s)- 1431 Only SR 3.3.9.2 Bases BDPS NUREG(s)- 1431 Only SR 3.3.9.3 BDPS NUREG(s)- 1431 Only SR 3.3.9.3 Bases BDPS NUREG(s)- 1431 Only SR 3.4.11.4 Pressurizer PORV NUREG(s)- 1431 Only SR 3.4.11.4 Bases Pressurizer PORV NUREG(s)- 1431 Only SR 3.4.12.9 LTOP System NUREG(s)- 1431 Only SR 3.4.12.9 Bases LTOP System NUREG(s)- 1431 Only SR 3.4.15.5 RCS Leakage Detection Instrumentation NUREG(s)- 1431 Only SR 3.4.15.5 Bases RCS Leakage Detection Instrumentation NUREG(s)- 1431 Only SR 3.4.17.1 RCS Loop Isolation Valves NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.4.17.1 Bases RCS Loop Isolation Valves NUREG(s)- 1431 Only SR 3.4.19.1 RCS Loops - Test Exceptions NUREG(s)- 1431 Only SR 3.4.19.1 Bases RCS Loops - Test Exceptions NUREG(s)- 1431 Only SR 3.5.1.1 Accumulators NUREG(s)- 1431 Only SR 3.5.1.1 Bases Accumulators NUREG(s)- 1431 Only SR 3.5.1.2 Accumulators NUREG(s)- 1431 Only SR 3.5.1.2 Bases Accumulators NUREG(s)- 1431 Only SR 3.5.1.3 Accumulators NUREG(s)- 1431 Only SR 3.5.1.3 Bases Accumulators NUREG(s)- 1431 Only SR 3.5.1.4 Accumulators NUREG(s)- 1431 Only SR 3.5.1.4 Bases Accumulators NUREG(s)- 1431 Only SR 3.5.1.5 Accumulators NUREG(s)- 1431 Only SR 3.5.1.5 Bases Accumulators NUREG(s)- 1431 Only SR 3.5.2.1 ECCS - Operating NUREG(s)- 1431 Only SR 3.5.2.1 Bases ECCS - Operating NUREG(s)- 1431 Only SR 3.5.2.2 ECCS - Operating NUREG(s)- 1431 Only SR 3.5.2.2 Bases ECCS - Operating NUREG(s)- 1431 Only SR 3.5.2.3 ECCS - Operating NUREG(s)- 1431 Only SR 3.5.2.3 Bases ECCS - Operating NUREG(s)- 1431 Only SR 3.5.2.5 ECCS - Operating NUREG(s)- 1431 Only SR 3.5.2.5 Bases ECCS - Operating NUREG(s)- 1431 Only SR 3.5.2.6 ECCS - Operating NUREG(s)- 1431 Only SR 3.5.2.6 Bases ECCS - Operating NUREG(s)- 1431 Only SR 3.5.2.7 ECCS - Operating NUREG(s)- 1431 Only SR 3.5.2.7 Bases ECCS - Operating NUREG(s)- 1431 Only SR 3.5.2.8 ECCS - Operating NUREG(s)- 1431 Only SR 3.5.2.8 Bases ECCS - Operating NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.5.4.1 RWST NUREG(s)- 1431 Only SR 3.5.4.1 Bases RWST NUREG(s)- 1431 Only SR 3.5.4.2 RWST NUREG(s)- 1431 Only SR 3.5.4.2 Bases RWST NUREG(s)- 1431 Only SR 3.5.4.3 RWST NUREG(s)- 1431 Only SR 3.5.4.3 Bases RWST NUREG(s)- 1431 Only SR 3.5.5.1 Seal Injection Flow NUREG(s)- 1431 Only SR 3.5.5.1 Bases Seal Injection Flow NUREG(s)- 1431 Only SR 3.5.6.1 BIT NUREG(s)- 1431 Only SR 3.5.6.1 Bases BIT NUREG(s)- 1431 Only SR 3.5.6.2 BIT NUREG(s)- 1431 Only SR 3.5.6.2 Bases BIT NUREG(s)- 1431 Only SR 3.5.6.3 BIT NUREG(s)- 1431 Only SR 3.5.6.3 Bases BIT NUREG(s)- 1431 Only SR 3.6.2.2 Containment Air Locks (Atmospheric, Subatmospheric, Ice NUREG(s)- 1431 Only Condenser, and Dual)
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| SR 3.6.2.2 Bases Containment Air Locks (Atmospheric, Subatmospheric, Ice NUREG(s)- 1431 Only Condenser, and Dual)
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| SR 3.6.3.1 Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.1 Bases Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.2 Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.2 Bases Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.3 Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.3 Bases Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.5 Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual) 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.3.5 Bases Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.6 Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.6 Bases Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.7 Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.7 Bases Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.8 Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.8 Bases Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.9 Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.9 Bases Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.10 Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.3.10 Bases Containment Isolation Valves (Atmospheric, Subatmospheric, NUREG(s)- 1431 Only Ice Condenser, and Dual)
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| SR 3.6.4A.1 Containment Pressure (Atmospheric, Dual, and Ice Condenser) NUREG(s)- 1431 Only SR 3.6.4B.1 Containment Pressure (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.4A.1 Bases Containment Pressure (Atmospheric, Dual, and Ice Condenser) NUREG(s)- 1431 Only SR 3.6.4B.1 Bases Containment Pressure (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.5A.1 Containment Air Temperature (Atmospheric and Dual) NUREG(s)- 1431 Only SR 3.6.5B.1 Containment Air Temperature (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.5C.1 Containment Air Temperature (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.5A.1 Bases Containment Air Temperature (Atmospheric and Dual) NUREG(s)- 1431 Only SR 3.6.5B.1 Bases Containment Air Temperature (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.5C.1 Bases Containment Air Temperature (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.5B.2 Containment Air Temperature (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.5B.2 Bases Containment Air Temperature (Ice Condenser) NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.6A.1 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6B.1 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6C.1 Containment Spray System (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.6D.1 QS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6E.1 RS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6A.1 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6B.1 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6C.1 Bases Containment Spray System (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.6D.1 Bases QS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6E.1 Bases RS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6B.2 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6A.2 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6E.2 RS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6B.2 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6A.2 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6E.2 Bases RS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6B.3 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6A.3 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6C.3 Containment Spray System (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.6D.3 QS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6E.3 RS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6A.3 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual) 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.6B.3 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6C.3 Bases Containment Spray System (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.6D.3 Bases QS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6E.3 Bases RS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6C.4 Containment Spray System (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.6D.4 QS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6E.4 RS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6C.4 Bases Containment Spray System (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.6D.4 Bases QS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6E.4 Bases RS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6B.5 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6A.5 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6C.5 Containment Spray System (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.6D.5 QS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6A.5 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6B.5 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6C.5 Bases Containment Spray System (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.6D.5 Bases QS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6A.6 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6B.6 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6E.6 RS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6A.6 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6B.6 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual) 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.6E.6 Bases RS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6B.7 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6A.7 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6E.7 RS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6A.7 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6B.7 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6E.7 Bases RS System (Subatmospheric) NUREG(s)- 1431 Only SR 3.6.6A.8 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6B.8 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6B.8 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.6A.8 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1431 Only Dual)
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| SR 3.6.7.1 Spray Additive System (Atmospheric, Subatmospheric, Ice NUREG(s)- 1431 Only Condenser, and Dual)
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| SR 3.6.7.1 Bases Spray Additive System (Atmospheric, Subatmospheric, Ice NUREG(s)- 1431 Only Condenser, and Dual)
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| SR 3.6.7.2 Spray Additive System (Atmospheric, Subatmospheric, Ice NUREG(s)- 1431 Only Condenser, and Dual)
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| SR 3.6.7.2 Bases Spray Additive System (Atmospheric, Subatmospheric, Ice NUREG(s)- 1431 Only Condenser, and Dual)
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| SR 3.6.7.3 Spray Additive System (Atmospheric, Subatmospheric, Ice NUREG(s)- 1431 Only Condenser, and Dual)
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| SR 3.6.7.3 Bases Spray Additive System (Atmospheric, Subatmospheric, Ice NUREG(s)- 1431 Only Condenser, and Dual)
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| SR 3.6.7.4 Spray Additive System (Atmospheric, Subatmospheric, Ice NUREG(s)- 1431 Only Condenser, and Dual)
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| SR 3.6.7.4 Bases Spray Additive System (Atmospheric, Subatmospheric, Ice NUREG(s)- 1431 Only Condenser, and Dual)
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| SR 3.6.7.5 Spray Additive System (Atmospheric, Subatmospheric, Ice NUREG(s)- 1431 Only Condenser, and Dual) 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.7.5 Bases Spray Additive System (Atmospheric, Subatmospheric, Ice NUREG(s)- 1431 Only Condenser, and Dual)
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| SR 3.6.8.1 Shield Buidling (Dual and Ice Condenser) NUREG(s)- 1431 Only SR 3.6.8.1 Bases Shield Buidling (Dual and Ice Condenser) NUREG(s)- 1431 Only SR 3.6.8.2 Shield Buidling (Dual and Ice Condenser) NUREG(s)- 1431 Only SR 3.6.8.2 Bases Shield Buidling (Dual and Ice Condenser) NUREG(s)- 1431 Only SR 3.6.8.4 Shield Buidling (Dual and Ice Condenser) NUREG(s)- 1431 Only SR 3.6.8.4 Bases Shield Buidling (Dual and Ice Condenser) NUREG(s)- 1431 Only SR 3.6.9.1 HMS (Atmospheric, Ice Condenser, and Dual) NUREG(s)- 1431 Only SR 3.6.9.1 Bases HMS (Atmospheric, Ice Condenser, and Dual) NUREG(s)- 1431 Only SR 3.6.9.2 HMS (Atmospheric, Ice Condenser, and Dual) NUREG(s)- 1431 Only SR 3.6.9.2 Bases HMS (Atmospheric, Ice Condenser, and Dual) NUREG(s)- 1431 Only SR 3.6.9.3 HMS (Atmospheric, Ice Condenser, and Dual) NUREG(s)- 1431 Only SR 3.6.9.3 Bases HMS (Atmospheric, Ice Condenser, and Dual) NUREG(s)- 1431 Only SR 3.6.10.1 HIS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.10.1 Bases HIS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.10.2 HIS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.10.2 Bases HIS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.10.3 HIS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.10.3 Bases HIS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.11.1 ICS (Atmospheric and Dual) NUREG(s)- 1431 Only SR 3.6.11.1 Bases ICS (Atmospheric and Dual) NUREG(s)- 1431 Only SR 3.6.11.3 ICS (Atmospheric and Dual) NUREG(s)- 1431 Only SR 3.6.11.3 Bases ICS (Atmospheric and Dual) NUREG(s)- 1431 Only SR 3.6.11.4 ICS (Atmospheric and Dual) NUREG(s)- 1431 Only SR 3.6.11.4 Bases ICS (Atmospheric and Dual) NUREG(s)- 1431 Only SR 3.6.13.1 SBACS (Dual and Ice Condener) NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.13.1 Bases SBACS (Dual and Ice Condener) NUREG(s)- 1431 Only SR 3.6.13.3 SBACS (Dual and Ice Condener) NUREG(s)- 1431 Only SR 3.6.13.3 Bases SBACS (Dual and Ice Condener) NUREG(s)- 1431 Only SR 3.6.13.4 SBACS (Dual and Ice Condener) NUREG(s)- 1431 Only SR 3.6.13.4 Bases SBACS (Dual and Ice Condener) NUREG(s)- 1431 Only SR 3.6.13.5 SBACS (Dual and Ice Condener) NUREG(s)- 1431 Only SR 3.6.13.5 Bases SBACS (Dual and Ice Condener) NUREG(s)- 1431 Only SR 3.6.14.1 ARS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.14.1 Bases ARS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.14.2 ARS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.14.2 Bases ARS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.14.3 ARS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.14.3 Bases ARS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.14.4 ARS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.14.4 Bases ARS (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.15.1 Ice Bed (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.15.1 Bases Ice Bed (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.15.2 Ice Bed (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.15.2 Bases Ice Bed (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.15.3 Ice Bed (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.15.3 Bases Ice Bed (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.15.4 Ice Bed (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.15.4 Bases Ice Bed (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.15.5 Ice Bed (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.15.5 Bases Ice Bed (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.15.6 Ice Bed (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.15.6 Bases Ice Bed (Ice Condenser) NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.16.1 Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.16.1 Bases Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.16.2 Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.16.2 Bases Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.16.3 Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.16.3 Bases Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.16.4 Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.16.4 Bases Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.16.5 Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.16.5 Bases Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.16.6 Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.16.6 Bases Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.16.7 Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.16.7 Bases Ice Condenser Doors (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.17.2 Divider Barrier Integrity (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.17.2 Bases Divider Barrier Integrity (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.17.4 Divider Barrier Integrity (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.17.4 Bases Divider Barrier Integrity (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.17.5 Divider Barrier Integrity (Ice Condenser) NUREG(s)- 1431 Only SR 3.6.17.5 Bases Divider Barrier Integrity (Ice Condenser) NUREG(s)- 1431 Only SR 3.7.3.2 MSIVs and MFRVs and [Associated Bypass Valves] NUREG(s)- 1431 Only SR 3.7.3.2 Bases MSIVs and MFRVs and [Associated Bypass Valves] NUREG(s)- 1431 Only SR 3.7.4.1 ADVs NUREG(s)- 1431 Only SR 3.7.4.1 Bases ADVs NUREG(s)- 1431 Only SR 3.7.4.2 ADVs NUREG(s)- 1431 Only SR 3.7.4.2 Bases ADVs NUREG(s)- 1431 Only SR 3.7.5.1 AFW System NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.7.5.1 Bases AFW System NUREG(s)- 1431 Only SR 3.7.5.3 AFW System NUREG(s)- 1431 Only SR 3.7.5.3 Bases AFW System NUREG(s)- 1431 Only SR 3.7.5.4 AFW System NUREG(s)- 1431 Only SR 3.7.5.4 Bases AFW System NUREG(s)- 1431 Only SR 3.7.6.1 CST NUREG(s)- 1431 Only SR 3.7.6.1 Bases CST NUREG(s)- 1431 Only SR 3.7.7.1 CCW System NUREG(s)- 1431 Only SR 3.7.7.1 Bases CCW System NUREG(s)- 1431 Only SR 3.7.7.2 CCW System NUREG(s)- 1431 Only SR 3.7.7.2 Bases CCW System NUREG(s)- 1431 Only SR 3.7.7.3 CCW System NUREG(s)- 1431 Only SR 3.7.7.3 Bases CCW System NUREG(s)- 1431 Only SR 3.7.8.1 SWS NUREG(s)- 1431 Only SR 3.7.8.1 Bases SWS NUREG(s)- 1431 Only SR 3.7.8.2 SWS NUREG(s)- 1431 Only SR 3.7.8.2 Bases SWS NUREG(s)- 1431 Only SR 3.7.8.3 SWS NUREG(s)- 1431 Only SR 3.7.8.3 Bases SWS NUREG(s)- 1431 Only SR 3.7.9.1 UHS NUREG(s)- 1431 Only SR 3.7.9.1 Bases UHS NUREG(s)- 1431 Only SR 3.7.9.2 UHS NUREG(s)- 1431 Only SR 3.7.9.2 Bases UHS NUREG(s)- 1431 Only SR 3.7.9.3 UHS NUREG(s)- 1431 Only SR 3.7.9.3 Bases UHS NUREG(s)- 1431 Only SR 3.7.9.4 UHS NUREG(s)- 1431 Only SR 3.7.9.4 Bases UHS NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.7.10.1 CREFS NUREG(s)- 1431 Only SR 3.7.10.1 Bases CREFS NUREG(s)- 1431 Only SR 3.7.10.3 CREFS NUREG(s)- 1431 Only SR 3.7.10.3 Bases CREFS NUREG(s)- 1431 Only SR 3.7.10.4 CREFS NUREG(s)- 1431 Only SR 3.7.10.4 Bases CREFS NUREG(s)- 1431 Only SR 3.7.11.1 CREATCS NUREG(s)- 1431 Only SR 3.7.11.1 Bases CREATCS NUREG(s)- 1431 Only SR 3.7.12.1 ECCS PREACS NUREG(s)- 1431 Only SR 3.7.12.1 Bases ECCS PREACS NUREG(s)- 1431 Only SR 3.7.12.3 ECCS PREACS NUREG(s)- 1431 Only SR 3.7.12.3 Bases ECCS PREACS NUREG(s)- 1431 Only SR 3.7.12.4 ECCS PREACS NUREG(s)- 1431 Only SR 3.7.12.4 Bases ECCS PREACS NUREG(s)- 1431 Only SR 3.7.12.5 ECCS PREACS NUREG(s)- 1431 Only SR 3.7.12.5 Bases ECCS PREACS NUREG(s)- 1431 Only SR 3.7.13.1 FBACS NUREG(s)- 1431 Only SR 3.7.13.1 Bases FBACS NUREG(s)- 1431 Only SR 3.7.13.3 FBACS NUREG(s)- 1431 Only SR 3.7.13.3 FBACS NUREG(s)- 1431 Only SR 3.7.13.4 FBACS NUREG(s)- 1431 Only SR 3.7.13.4 Bases FBACS NUREG(s)- 1431 Only SR 3.7.13.5 FBACS NUREG(s)- 1431 Only SR 3.7.13.5 Bases FBACS NUREG(s)- 1431 Only SR 3.7.14.1 PREACS NUREG(s)- 1431 Only SR 3.7.14.1 Bases PREACS NUREG(s)- 1431 Only SR 3.7.14.3 PREACS NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.7.14.3 Bases PREACS NUREG(s)- 1431 Only SR 3.7.14.4 PREACS NUREG(s)- 1431 Only SR 3.7.14.4 Bases PREACS NUREG(s)- 1431 Only SR 3.7.14.5 PREACS NUREG(s)- 1431 Only SR 3.7.14.5 Bases PREACS NUREG(s)- 1431 Only SR 3.7.15.1 Fuel Storage Pool Water Level NUREG(s)- 1431 Only SR 3.7.15.1 Bases Fuel Storage Pool Water Level NUREG(s)- 1431 Only SR 3.7.16.1 Fuel Storage Pool Boron Concentration NUREG(s)- 1431 Only SR 3.7.16.1 Bases Fuel Storage Pool Boron Concentration NUREG(s)- 1431 Only SR 3.7.18.1 Secondary Specific Activity NUREG(s)- 1431 Only SR 3.7.18.1 Bases Secondary Specific Activity NUREG(s)- 1431 Only SR 3.9.2.1 [Unborated Water Source Isolation Valves] NUREG(s)- 1431 Only SR 3.9.2.1 Bases [Unborated Water Source Isolation Valves] NUREG(s)- 1431 Only SR 3.9.3.1 Nuclear Instrumentation NUREG(s)- 1431 Only SR 3.9.3.1 Bases Nuclear Instrumentation NUREG(s)- 1431 Only SR 3.9.3.2 Nuclear Instrumentation NUREG(s)- 1431 Only SR 3.9.3.2 Bases Nuclear Instrumentation NUREG(s)- 1431 Only SR 3.9.4.1 Containment Penetrations NUREG(s)- 1431 Only SR 3.9.4.1 Bases Containment Penetrations NUREG(s)- 1431 Only SR 3.9.4.2 Containment Penetrations NUREG(s)- 1431 Only SR 3.9.4.2 Bases Containment Penetrations NUREG(s)- 1431 Only SR 3.9.5.1 RHR and Coolant Circulation - High Water Level NUREG(s)- 1431 Only SR 3.9.5.1 Bases RHR and Coolant Circulation - High Water Level NUREG(s)- 1431 Only SR 3.9.6.1 RHR and Coolant Circulation - Low Water Level NUREG(s)- 1431 Only SR 3.9.6.1 Bases RHR and Coolant Circulation - Low Water Level NUREG(s)- 1431 Only SR 3.9.6.2 RHR and Coolant Circulation - Low Water Level NUREG(s)- 1431 Only SR 3.9.6.2 Bases RHR and Coolant Circulation - Low Water Level NUREG(s)- 1431 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.9.7.1 Refueling Cavity Water Level NUREG(s)- 1431 Only SR 3.9.7.1 Bases Refueling Cavity Water Level NUREG(s)- 1431 Only SR 3.1.1.1 SDM (Analog) NUREG(s)- 1432 Only SR 3.1.1.1 SDM (Digital) NUREG(s)- 1432 Only SR 3.1.1.1 Bases SDM (Analog) NUREG(s)- 1432 Only SR 3.1.1.1 Bases SDM (Digital) NUREG(s)- 1432 Only SR 3.1.2.1 Reactivity Balance (Analog) NUREG(s)- 1432 Only SR 3.1.2.1 Reactivity Balance (Digital) NUREG(s)- 1432 Only SR 3.1.2.1 Bases Reactivity Balance (Analog) NUREG(s)- 1432 Only SR 3.1.2.1 Bases Reactivity Balance (Digital) NUREG(s)- 1432 Only SR 3.1.4.1 CEA Alignment (Analog) NUREG(s)- 1432 Only SR 3.1.4.1 CEA Alignment (Digital) NUREG(s)- 1432 Only SR 3.1.4.1 Bases CEA Alignment (Analog) NUREG(s)- 1432 Only SR 3.1.4.1 Bases CEA Alignment (Digital) NUREG(s)- 1432 Only SR 3.1.4.2 CEA Alignment (Analog) NUREG(s)- 1432 Only SR 3.1.4.2 CEA Alignment (Digital) NUREG(s)- 1432 Only SR 3.1.4.2 Bases CEA Alignment (Analog) NUREG(s)- 1432 Only SR 3.1.4.2 Bases CEA Alignment (Digital) NUREG(s)- 1432 Only SR 3.1.4.3 CEA Alignment (Analog) NUREG(s)- 1432 Only SR 3.1.4.3 CEA Alignment (Digital) NUREG(s)- 1432 Only SR 3.1.4.3 Bases CEA Alignment (Analog) NUREG(s)- 1432 Only SR 3.1.4.3 Bases CEA Alignment (Digital) NUREG(s)- 1432 Only SR 3.1.4.4 CEA Alignment (Analog) NUREG(s)- 1432 Only SR 3.1.4.4 CEA Alignment (Digital) NUREG(s)- 1432 Only SR 3.1.4.4 Bases CEA Alignment (Analog) NUREG(s)- 1432 Only SR 3.1.4.4 Bases CEA Alignment (Digital) NUREG(s)- 1432 Only SR 3.1.4.5 CEA Alignment (Analog) NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.1.4.5 Bases CEA Alignment (Analog) NUREG(s)- 1432 Only SR 3.1.5.1 Shutdown CEA Insertion Limits (Analog) NUREG(s)- 1432 Only SR 3.1.5.1 Shutdown CEA Insertion Limits (Digital) NUREG(s)- 1432 Only SR 3.1.5.1 Bases Shutdown CEA Insertion Limits (Analog) NUREG(s)- 1432 Only SR 3.1.5.1 Bases Shutdown CEA Insertion Limits (Digital) NUREG(s)- 1432 Only SR 3.1.6.1 Regulating CEA Insertion Limits (Analog) NUREG(s)- 1432 Only SR 3.1.6.1 Regulating CEA Insertion Limits (Digital) NUREG(s)- 1432 Only SR 3.1.6.1 Bases Regulating CEA Insertion Limits (Analog) NUREG(s)- 1432 Only SR 3.1.6.1 Bases Regulating CEA Insertion Limits (Digital) NUREG(s)- 1432 Only SR 3.1.6.2 Regulating CEA Insertion Limits (Analog) NUREG(s)- 1432 Only SR 3.1.6.2 Regulating CEA Insertion Limits (Digital) NUREG(s)- 1432 Only SR 3.1.6.2 Bases Regulating CEA Insertion Limits (Analog) NUREG(s)- 1432 Only SR 3.1.6.2 Bases Regulating CEA Insertion Limits (Digital) NUREG(s)- 1432 Only SR 3.1.6.3 Regulating CEA Insertion Limits (Analog) NUREG(s)- 1432 Only SR 3.1.6.3 Regulating CEA Insertion Limits (Digital) NUREG(s)- 1432 Only SR 3.1.6.3 Bases Regulating CEA Insertion Limits (Analog) NUREG(s)- 1432 Only SR 3.1.6.3 Bases Regulating CEA Insertion Limits (Digital) NUREG(s)- 1432 Only SR 3.1.7.1 Part Length CEA Insertion Limits (Digital) NUREG(s)- 1432 Only SR 3.1.7.1 STE-SDM (Analog) NUREG(s)- 1432 Only SR 3.1.7.1 Bases Part Length CEA Insertion Limits (Digital) NUREG(s)- 1432 Only SR 3.1.7.1 Bases STE-SDM (Analog) NUREG(s)- 1432 Only SR 3.1.8.1 STE-MODES 1 and 2 (Analog) NUREG(s)- 1432 Only SR 3.1.8.1 STE-SDM (Digital) NUREG(s)- 1432 Only SR 3.1.8.1 Bases STE-MODES 1 and 2 (Analog) NUREG(s)- 1432 Only SR 3.1.8.1 Bases STE-SDM (Digital) NUREG(s)- 1432 Only SR 3.1.9.1 STE - MODES 1 and 2 (Digital) NUREG(s)- 1432 Only SR 3.1.9.1 Bases STE - MODES 1 and 2 (Digital) NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.2.1.1 LHR (Analog) NUREG(s)- 1432 Only SR 3.2.1.1 LHR (Digital) NUREG(s)- 1432 Only SR 3.2.1.1 Bases LHR (Analog) NUREG(s)- 1432 Only SR 3.2.1.1 Bases LHR (Digital) NUREG(s)- 1432 Only SR 3.2.1.2 LHR (Analog) NUREG(s)- 1432 Only SR 3.2.1.2 LHR (Digital) NUREG(s)- 1432 Only SR 3.2.1.2 Bases LHR (Analog) NUREG(s)- 1432 Only SR 3.2.1.2 Bases LHR (Digital) NUREG(s)- 1432 Only SR 3.2.1.3 LHR (Analog) NUREG(s)- 1432 Only SR 3.2.1.3 Bases LHR (Analog) NUREG(s)- 1432 Only SR 3.2.2.1 Fxy (Digital) NUREG(s)- 1432 Only SR 3.2.2.1 FxyT (Analog) NUREG(s)- 1432 Only SR 3.2.2.1 Tq (Analog) NUREG(s)- 1432 Only SR 3.2.2.1 Bases Fxy (Digital) NUREG(s)- 1432 Only SR 3.2.2.1 Bases FxyT (Analog) NUREG(s)- 1432 Only SR 3.2.2.1 Bases Tq (Analog) NUREG(s)- 1432 Only SR 3.2.3.1 FrT (Analog) NUREG(s)- 1432 Only SR 3.2.3.1 Tq (Digital) NUREG(s)- 1432 Only SR 3.2.3.1 Bases FrT (Analog) NUREG(s)- 1432 Only SR 3.2.3.1 Bases Tq (Digital) NUREG(s)- 1432 Only SR 3.2.3.2 Tq (Digital) NUREG(s)- 1432 Only SR 3.2.3.2 Bases Tq (Digital) NUREG(s)- 1432 Only SR 3.2.3.3 Tq (Digital) NUREG(s)- 1432 Only SR 3.2.3.3 Bases Tq (Digital) NUREG(s)- 1432 Only SR 3.2.4.1 DNBR (Digital) NUREG(s)- 1432 Only SR 3.2.4.1 Bases DNBR (Digital) NUREG(s)- 1432 Only SR 3.2.4.2 DNBR (Digital) NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.2.4.2 Bases DNBR (Digital) NUREG(s)- 1432 Only SR 3.2.5.1 ASI (Analog) NUREG(s)- 1432 Only SR 3.2.5.1 ASI (Digital) NUREG(s)- 1432 Only SR 3.2.5.1 Bases ASI (Analog) NUREG(s)- 1432 Only SR 3.2.5.1 Bases ASI (Digital) NUREG(s)- 1432 Only SR 3.3.1.1 RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.1 RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.1 Bases RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.1 Bases RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.2 RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.2 RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.2 Bases RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.2 Bases RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.3 RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.3 RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.3 Bases RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.3 Bases RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.4 RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.4 RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.4 Bases RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.4 Bases RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.5 RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.5 RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.5 Bases RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.5 Bases RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.6 RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.6 Bases RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.1.7 RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.7 Bases RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.8 RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.8 RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.8 Bases RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.8 Bases RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.9 RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.9 RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.9 Bases RPS Instrumentation - Operating (Analog) NUREG(s)- 1432 Only SR 3.3.1.9 Bases RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.10 RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.10 Bases RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.11 RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.11 Bases RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.14 RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.1.14 Bases RPS Instrumentation - Operating (Digital) NUREG(s)- 1432 Only SR 3.3.2.1 RPS Instrumentation - Shutdown (Analog) NUREG(s)- 1432 Only SR 3.3.2.1 RPS Instrumentation - Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.2.1 Bases RPS Instrumentation - Shutdown (Analog) NUREG(s)- 1432 Only SR 3.3.2.1 Bases RPS Instrumentation - Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.2.2 RPS Instrumentation - Shutdown (Analog) NUREG(s)- 1432 Only SR 3.3.2.2 RPS Instrumentation - Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.2.2 Bases RPS Instrumentation - Shutdown (Analog) NUREG(s)- 1432 Only SR 3.3.2.2 Bases RPS Instrumentation - Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.2.3 RPS Instrumentation - Shutdown (Analog) NUREG(s)- 1432 Only SR 3.3.2.3 Bases RPS Instrumentation - Shutdown (Analog) NUREG(s)- 1432 Only SR 3.3.2.4 RPS Instrumentation - Shutdown (Analog) NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.2.4 RPS Instrumentation - Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.2.4 Bases RPS Instrumentation - Shutdown (Analog) NUREG(s)- 1432 Only SR 3.3.2.4 Bases RPS Instrumentation - Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.2.5 RPS Instrumentation - Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.2.5 Bases RPS Instrumentation - Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.3.1 CEACs (Digital) NUREG(s)- 1432 Only SR 3.3.3.1 RPS Logic and Trip Initiation (Analog) NUREG(s)- 1432 Only SR 3.3.3.1 Bases CEACs (Digital) NUREG(s)- 1432 Only SR 3.3.3.1 Bases RPS Logic and Trip Initiation (Analog) NUREG(s)- 1432 Only SR 3.3.3.2 CEACs (Digital) NUREG(s)- 1432 Only SR 3.3.3.2 RPS Logic and Trip Initiation (Analog) NUREG(s)- 1432 Only SR 3.3.3.2 Bases CEACs (Digital) NUREG(s)- 1432 Only SR 3.3.3.2 Bases RPS Logic and Trip Initiation (Analog) NUREG(s)- 1432 Only SR 3.3.3.3 CEACs (Digital) NUREG(s)- 1432 Only SR 3.3.3.3 Bases CEACs (Digital) NUREG(s)- 1432 Only SR 3.3.3.4 CEACs (Digital) NUREG(s)- 1432 Only SR 3.3.3.4 RPS Logic and Trip Initiation (Analog) NUREG(s)- 1432 Only SR 3.3.3.4 Bases CEACs (Digital) NUREG(s)- 1432 Only SR 3.3.3.4 Bases RPS Logic and Trip Initiation (Analog) NUREG(s)- 1432 Only SR 3.3.3.5 CEACs (Digital) NUREG(s)- 1432 Only SR 3.3.3.5 Bases CEACs (Digital) NUREG(s)- 1432 Only SR 3.3.3.6 CEACs (Digital) NUREG(s)- 1432 Only SR 3.3.3.6 Bases CEACs (Digital) NUREG(s)- 1432 Only SR 3.3.4.1 ESFAS Instrumentation (Analog) NUREG(s)- 1432 Only SR 3.3.4.1 RPS Logic and Trip Initiation (Digital) NUREG(s)- 1432 Only SR 3.3.4.1 Bases ESFAS Instrumentation (Analog) NUREG(s)- 1432 Only SR 3.3.4.1 Bases RPS Logic and Trip Initiation (Digital) NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.4.2 ESFAS Instrumentation (Analog) NUREG(s)- 1432 Only SR 3.3.4.2 RPS Logic and Trip Initiation (Digital) NUREG(s)- 1432 Only SR 3.3.4.2 Bases ESFAS Instrumentation (Analog) NUREG(s)- 1432 Only SR 3.3.4.2 Bases RPS Logic and Trip Initiation (Digital) NUREG(s)- 1432 Only SR 3.3.4.3 RPS Logic and Trip Initiation (Digital) NUREG(s)- 1432 Only SR 3.3.4.3 Bases RPS Logic and Trip Initiation (Digital) NUREG(s)- 1432 Only SR 3.3.4.4 ESFAS Instrumentation (Analog) NUREG(s)- 1432 Only SR 3.3.4.4 Bases ESFAS Instrumentation (Analog) NUREG(s)- 1432 Only SR 3.3.4.5 ESFAS Instrumentation (Analog) NUREG(s)- 1432 Only SR 3.3.4.5 Bases ESFAS Instrumentation (Analog) NUREG(s)- 1432 Only SR 3.3.5.1 ESFAS Instrumentation (Digital) NUREG(s)- 1432 Only SR 3.3.5.1 ESFAS Logic and Manual Trip (Analog) NUREG(s)- 1432 Only SR 3.3.5.1 Bases ESFAS Instrumentation (Digital) NUREG(s)- 1432 Only SR 3.3.5.1 Bases ESFAS Logic and Manual Trip (Analog) NUREG(s)- 1432 Only SR 3.3.5.2 ESFAS Instrumentation (Digital) NUREG(s)- 1432 Only SR 3.3.5.2 ESFAS Logic and Manual Trip (Analog) NUREG(s)- 1432 Only SR 3.3.5.2 Bases ESFAS Instrumentation (Digital) NUREG(s)- 1432 Only SR 3.3.5.2 Bases ESFAS Logic and Manual Trip (Analog) NUREG(s)- 1432 Only SR 3.3.5.3 ESFAS Instrumentation (Digital) NUREG(s)- 1432 Only SR 3.3.5.3 Bases ESFAS Instrumentation (Digital) NUREG(s)- 1432 Only SR 3.3.5.4 ESFAS Instrumentation (Digital) NUREG(s)- 1432 Only SR 3.3.5.4 Bases ESFAS Instrumentation (Digital) NUREG(s)- 1432 Only SR 3.3.6.1 DG LOVS (Analog) NUREG(s)- 1432 Only SR 3.3.6.1 ESFAS Logic and Manual Trip (Digital) NUREG(s)- 1432 Only SR 3.3.6.1 Bases DG LOVS (Analog) NUREG(s)- 1432 Only SR 3.3.6.1 Bases ESFAS Logic and Manual Trip (Digital) NUREG(s)- 1432 Only SR 3.3.6.2 DG LOVS (Analog) NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.6.2 ESFAS Logic and Manual Trip (Digital) NUREG(s)- 1432 Only SR 3.3.6.2 Bases DG LOVS (Analog) NUREG(s)- 1432 Only SR 3.3.6.2 Bases ESFAS Logic and Manual Trip (Digital) NUREG(s)- 1432 Only SR 3.3.6.3 DG LOVS (Analog) NUREG(s)- 1432 Only SR 3.3.6.3 ESFAS Logic and Manual Trip (Digital) NUREG(s)- 1432 Only SR 3.3.6.3 Bases DG LOVS (Analog) NUREG(s)- 1432 Only SR 3.3.6.3 Bases ESFAS Logic and Manual Trip (Digital) NUREG(s)- 1432 Only SR 3.3.7.1 CPIS (Analog) NUREG(s)- 1432 Only SR 3.3.7.1 DG-LOVS (Digital) NUREG(s)- 1432 Only SR 3.3.7.1 Bases CPIS (Analog) NUREG(s)- 1432 Only SR 3.3.7.1 Bases DG-LOVS (Digital) NUREG(s)- 1432 Only SR 3.3.7.2 CPIS (Analog) NUREG(s)- 1432 Only SR 3.3.7.2 DG-LOVS (Digital) NUREG(s)- 1432 Only SR 3.3.7.2 Bases CPIS (Analog) NUREG(s)- 1432 Only SR 3.3.7.2 Bases DG-LOVS (Digital) NUREG(s)- 1432 Only SR 3.3.7.3 CPIS (Analog) NUREG(s)- 1432 Only SR 3.3.7.3 DG-LOVS (Digital) NUREG(s)- 1432 Only SR 3.3.7.3 Bases CPIS (Analog) NUREG(s)- 1432 Only SR 3.3.7.3 Bases DG-LOVS (Digital) NUREG(s)- 1432 Only SR 3.3.7.4 CPIS (Analog) NUREG(s)- 1432 Only SR 3.3.7.4 Bases CPIS (Analog) NUREG(s)- 1432 Only SR 3.3.7.5 CPIS (Analog) NUREG(s)- 1432 Only SR 3.3.7.5 Bases CPIS (Analog) NUREG(s)- 1432 Only SR 3.3.7.6 CPIS (Analog) NUREG(s)- 1432 Only SR 3.3.7.6 Bases CPIS (Analog) NUREG(s)- 1432 Only SR 3.3.8.1 CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.1 CRIS (Analog) NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.8.1 Bases CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.1 Bases CRIS (Analog) NUREG(s)- 1432 Only SR 3.3.8.2 CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.2 CRIS (Analog) NUREG(s)- 1432 Only SR 3.3.8.2 Bases CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.2 Bases CRIS (Analog) NUREG(s)- 1432 Only SR 3.3.8.3 CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.3 CRIS (Analog) NUREG(s)- 1432 Only SR 3.3.8.3 Bases CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.3 Bases CRIS (Analog) NUREG(s)- 1432 Only SR 3.3.8.4 CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.4 CRIS (Analog) NUREG(s)- 1432 Only SR 3.3.8.4 Bases CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.4 Bases CRIS (Analog) NUREG(s)- 1432 Only SR 3.3.8.5 CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.5 CRIS (Analog) NUREG(s)- 1432 Only SR 3.3.8.5 Bases CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.5 Bases CRIS (Analog) NUREG(s)- 1432 Only SR 3.3.8.6 CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.6 CRIS (Analog) NUREG(s)- 1432 Only SR 3.3.8.6 Bases CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.6 Bases CRIS (Analog) NUREG(s)- 1432 Only SR 3.3.8.7 CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.7 Bases CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.8 CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.8.8 Bases CPIS (Digital) NUREG(s)- 1432 Only SR 3.3.9.1 CRIS (Digital) NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.9.1 CVCS Isolation Signal (Analog) NUREG(s)- 1432 Only SR 3.3.9.1 Bases CRIS (Digital) NUREG(s)- 1432 Only SR 3.3.9.1 Bases CVCS Isolation Signal (Analog) NUREG(s)- 1432 Only SR 3.3.9.2 CRIS (Digital) NUREG(s)- 1432 Only SR 3.3.9.2 CVCS Isolation Signal (Analog) NUREG(s)- 1432 Only SR 3.3.9.2 Bases CRIS (Digital) NUREG(s)- 1432 Only SR 3.3.9.2 Bases CVCS Isolation Signal (Analog) NUREG(s)- 1432 Only SR 3.3.9.3 CRIS (Digital) NUREG(s)- 1432 Only SR 3.3.9.3 CVCS Isolation Signal (Analog) NUREG(s)- 1432 Only SR 3.3.9.3 Bases CRIS (Digital) NUREG(s)- 1432 Only SR 3.3.9.3 Bases CVCS Isolation Signal (Analog) NUREG(s)- 1432 Only SR 3.3.9.4 CRIS (Digital) NUREG(s)- 1432 Only SR 3.3.9.4 Bases CRIS (Digital) NUREG(s)- 1432 Only SR 3.3.9.5 CRIS (Digital) NUREG(s)- 1432 Only SR 3.3.9.5 Bases CRIS (Digital) NUREG(s)- 1432 Only SR 3.3.9.6 CRIS (Digital) NUREG(s)- 1432 Only SR 3.3.9.6 Bases CRIS (Digital) NUREG(s)- 1432 Only SR 3.3.10.1 FHIS (Digital) NUREG(s)- 1432 Only SR 3.3.10.1 SBFAS (Analog) NUREG(s)- 1432 Only SR 3.3.10.1 Bases FHIS (Digital) NUREG(s)- 1432 Only SR 3.3.10.1 Bases SBFAS (Analog) NUREG(s)- 1432 Only SR 3.3.10.2 FHIS (Digital) NUREG(s)- 1432 Only SR 3.3.10.2 SBFAS (Analog) NUREG(s)- 1432 Only SR 3.3.10.2 Bases FHIS (Digital) NUREG(s)- 1432 Only SR 3.3.10.2 Bases SBFAS (Analog) NUREG(s)- 1432 Only SR 3.3.10.3 FHIS (Digital) NUREG(s)- 1432 Only SR 3.3.10.3 Bases FHIS (Digital) NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.10.4 FHIS (Digital) NUREG(s)- 1432 Only SR 3.3.10.4 Bases FHIS (Digital) NUREG(s)- 1432 Only SR 3.3.10.5 FHIS (Digital) NUREG(s)- 1432 Only SR 3.3.10.5 Bases FHIS (Digital) NUREG(s)- 1432 Only SR 3.3.10.6 FHIS (Digital) NUREG(s)- 1432 Only SR 3.3.10.6 Bases FHIS (Digital) NUREG(s)- 1432 Only SR 3.3.11.1 PAM Instrumentation (Analog) NUREG(s)- 1432 Only SR 3.3.11.1 PAM Instrumentation (Digital) NUREG(s)- 1432 Only SR 3.3.11.1 Bases PAM Instrumentation (Analog) NUREG(s)- 1432 Only SR 3.3.11.1 Bases PAM Instrumentation (Digital) NUREG(s)- 1432 Only SR 3.3.11.2 PAM Instrumentation (Analog) NUREG(s)- 1432 Only SR 3.3.11.2 PAM Instrumentation (Digital) NUREG(s)- 1432 Only SR 3.3.11.2 Bases PAM Instrumentation (Analog) NUREG(s)- 1432 Only SR 3.3.11.2 Bases PAM Instrumentation (Digital) NUREG(s)- 1432 Only SR 3.3.12.1 Remote Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.12.1 Remote Shutdown System (Analog) NUREG(s)- 1432 Only SR 3.3.12.1 Bases Remote Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.12.1 Bases Remote Shutdown System (Analog) NUREG(s)- 1432 Only SR 3.3.12.2 Remote Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.12.2 Remote Shutdown System (Analog) NUREG(s)- 1432 Only SR 3.3.12.2 Bases Remote Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.12.2 Bases Remote Shutdown System (Analog) NUREG(s)- 1432 Only SR 3.3.12.3 Remote Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.12.3 Remote Shutdown System (Analog) NUREG(s)- 1432 Only SR 3.3.12.3 Bases Remote Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.12.3 Bases Remote Shutdown System (Analog) NUREG(s)- 1432 Only SR 3.3.12.4 Remote Shutdown (Digital) NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.12.4 Remote Shutdown System (Analog) NUREG(s)- 1432 Only SR 3.3.12.4 Bases Remote Shutdown (Digital) NUREG(s)- 1432 Only SR 3.3.12.4 Bases Remote Shutdown System (Analog) NUREG(s)- 1432 Only SR 3.3.13.1 [Logarithmic] Power Monitoring Channels (Analog) NUREG(s)- 1432 Only SR 3.3.13.1 [Logarithmic] Power Monitoring Channels (Digital) NUREG(s)- 1432 Only SR 3.3.13.1 Bases [Logarithmic] Power Monitoring Channels (Analog) NUREG(s)- 1432 Only SR 3.3.13.1 Bases [Logarithmic] Power Monitoring Channels (Digital) NUREG(s)- 1432 Only SR 3.3.13.2 [Logarithmic] Power Monitoring Channels (Analog) NUREG(s)- 1432 Only SR 3.3.13.2 [Logarithmic] Power Monitoring Channels (Digital) NUREG(s)- 1432 Only SR 3.3.13.2 Bases [Logarithmic] Power Monitoring Channels (Analog) NUREG(s)- 1432 Only SR 3.3.13.2 Bases [Logarithmic] Power Monitoring Channels (Digital) NUREG(s)- 1432 Only SR 3.3.13.3 [Logarithmic] Power Monitoring Channels (Analog) NUREG(s)- 1432 Only SR 3.3.13.3 [Logarithmic] Power Monitoring Channels (Digital) NUREG(s)- 1432 Only SR 3.3.13.3 Bases [Logarithmic] Power Monitoring Channels (Analog) NUREG(s)- 1432 Only SR 3.3.13.3 Bases [Logarithmic] Power Monitoring Channels (Digital) NUREG(s)- 1432 Only SR 3.4.11.4 Pressurizer PORV NUREG(s)- 1432 Only SR 3.4.11.4 Bases Pressurizer PORV NUREG(s)- 1432 Only SR 3.4.15.5 RCS LEAKAGE Detection Instrumentation NUREG(s)- 1432 Only SR 3.4.15.5 Bases RCS LEAKAGE Detection Instrumentation NUREG(s)- 1432 Only SR 3.4.17.1 STE-RCS Loops NUREG(s)- 1432 Only SR 3.4.17.1 Bases STE-RCS Loops NUREG(s)- 1432 Only SR 3.4.17.2 STE-RCS Loops NUREG(s)- 1432 Only SR 3.4.17.2 Bases STE-RCS Loops NUREG(s)- 1432 Only SR 3.5.1.1 SITs NUREG(s)- 1432 Only SR 3.5.1.1 Bases SITs NUREG(s)- 1432 Only SR 3.5.1.2 SITs NUREG(s)- 1432 Only SR 3.5.1.2 Bases SITs NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.5.1.3 SITs NUREG(s)- 1432 Only SR 3.5.1.3 Bases SITs NUREG(s)- 1432 Only SR 3.5.1.4 SITs NUREG(s)- 1432 Only SR 3.5.1.4 Bases SITs NUREG(s)- 1432 Only SR 3.5.1.5 SITs NUREG(s)- 1432 Only SR 3.5.1.5 Bases SITs NUREG(s)- 1432 Only SR 3.5.2.1 ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.1 Bases ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.2 ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.2 Bases ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.3 ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.3 Bases ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.6 ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.6 Bases ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.7 ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.7 Bases ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.8 ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.8 Bases ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.9 ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.9 Bases ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.10 ECCS - Operating NUREG(s)- 1432 Only SR 3.5.2.10 Bases ECCS - Operating NUREG(s)- 1432 Only SR 3.5.4.1 RWT NUREG(s)- 1432 Only SR 3.5.4.1 Bases RWT NUREG(s)- 1432 Only SR 3.5.4.2 RWT NUREG(s)- 1432 Only SR 3.5.4.2 Bases RWT NUREG(s)- 1432 Only SR 3.5.4.3 RWT NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.5.4.3 Bases RWT NUREG(s)- 1432 Only SR 3.5.5.1 TSP NUREG(s)- 1432 Only SR 3.5.5.1 Bases TSP NUREG(s)- 1432 Only SR 3.5.5.2 TSP NUREG(s)- 1432 Only SR 3.5.5.2 Bases TSP NUREG(s)- 1432 Only SR 3.6.2.2 Containment Air Locks (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.2.2 Bases Containment Air Locks (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.1 Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.1 Bases Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.2 Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.2 Bases Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.3 Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.3 Bases Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.5 Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.5 Bases Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.6 Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.6 Bases Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.7 Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.7 Bases Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.8 Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.3.8 Bases Containment Isolation Valves (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.4.1 Containment Pressure (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.4.1 Bases Containment Pressure (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.5.1 Containment Air Temperature (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.5.1 Bases Containment Air Temperature (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.6B.1 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual) 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.6A.1 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.1 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.1 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.2 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.2 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.2 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.2 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.3 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.3 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.3 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.3 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.4 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.4 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.4 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.4 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.6 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.6 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.6 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.6 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.7 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual) 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.6B.7 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.7 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.7 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.8 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.8 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.8 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.8 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.9 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.9 Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6B.9 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.6A.9 Bases Containment Spray and Cooling Systems (Atmospheric and NUREG(s)- 1432 Only Dual)
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| SR 3.6.7.1 Spray Additative System (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.7.1 Bases Spray Additative System (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.7.2 Spray Additative System (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.7.2 Bases Spray Additative System (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.7.3 Spray Additative System (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.7.3 Bases Spray Additative System (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.7.5 Spray Additative System (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.7.5 Bases Spray Additative System (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.7.6 Spray Additative System (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.7.6 Bases Spray Additative System (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.8.1 SBEACS (Dual) NUREG(s)- 1432 Only SR 3.6.8.1 Bases SBEACS (Dual) NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.8.3 SBEACS (Dual) NUREG(s)- 1432 Only SR 3.6.8.3 Bases SBEACS (Dual) NUREG(s)- 1432 Only SR 3.6.8.4 SBEACS (Dual) NUREG(s)- 1432 Only SR 3.6.8.4 Bases SBEACS (Dual) NUREG(s)- 1432 Only SR 3.6.8.5 SBEACS (Dual) NUREG(s)- 1432 Only SR 3.6.8.5 Bases SBEACS (Dual) NUREG(s)- 1432 Only SR 3.6.9.1 HMS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.9.1 Bases HMS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.9.2 HMS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.9.2 Bases HMS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.9.3 HMS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.9.3 Bases HMS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.10.1 ICS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.10.1 Bases ICS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.10.3 ICS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.10.3 Bases ICS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.10.4 ICS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.10.4 Bases ICS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.11.1 ICS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.11.1 Bases ICS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.11.2 ICS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.11.2 Bases ICS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.11.4 ICS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.6.11.4 Bases ICS (Atmospheric and Dual) NUREG(s)- 1432 Only SR 3.7.3.2 MSIVs [and [MFIV] Bypass Valves] NUREG(s)- 1432 Only SR 3.7.3.2 Bases MSIVs [and [MFIV] Bypass Valves] NUREG(s)- 1432 Only SR 3.7.4.1 ADVs NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.7.4.1 Bases ADVs NUREG(s)- 1432 Only SR 3.7.4.2 ADVs NUREG(s)- 1432 Only SR 3.7.4.2 Bases ADVs NUREG(s)- 1432 Only SR 3.7.5.1 AFW System NUREG(s)- 1432 Only SR 3.7.5.1 Bases AFW System NUREG(s)- 1432 Only SR 3.7.5.3 AFW System NUREG(s)- 1432 Only SR 3.7.5.3 Bases AFW System NUREG(s)- 1432 Only SR 3.7.5.4 AFW System NUREG(s)- 1432 Only SR 3.7.5.4 Bases AFW System NUREG(s)- 1432 Only SR 3.7.6.1 CST NUREG(s)- 1432 Only SR 3.7.6.1 Bases CST NUREG(s)- 1432 Only SR 3.7.7.1 CCW System NUREG(s)- 1432 Only SR 3.7.7.1 Bases CCW System NUREG(s)- 1432 Only SR 3.7.7.2 CCW System NUREG(s)- 1432 Only SR 3.7.7.2 Bases CCW System NUREG(s)- 1432 Only SR 3.7.7.3 CCW System NUREG(s)- 1432 Only SR 3.7.7.3 Bases CCW System NUREG(s)- 1432 Only SR 3.7.8.1 SWS NUREG(s)- 1432 Only SR 3.7.8.1 Bases SWS NUREG(s)- 1432 Only SR 3.7.8.2 SWS NUREG(s)- 1432 Only SR 3.7.8.2 Bases SWS NUREG(s)- 1432 Only SR 3.7.8.3 SWS NUREG(s)- 1432 Only SR 3.7.8.3 Bases SWS NUREG(s)- 1432 Only SR 3.7.9.1 UHS NUREG(s)- 1432 Only SR 3.7.9.1 Bases UHS NUREG(s)- 1432 Only SR 3.7.9.2 UHS NUREG(s)- 1432 Only SR 3.7.9.2 Bases UHS NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.7.9.3 UHS NUREG(s)- 1432 Only SR 3.7.9.3 Bases UHS NUREG(s)- 1432 Only SR 3.7.10.1 ECW NUREG(s)- 1432 Only SR 3.7.10.1 Bases ECW NUREG(s)- 1432 Only SR 3.7.10.2 ECW NUREG(s)- 1432 Only SR 3.7.10.2 Bases ECW NUREG(s)- 1432 Only SR 3.7.11.1 CREACS NUREG(s)- 1432 Only SR 3.7.11.1 Bases CREACS NUREG(s)- 1432 Only SR 3.7.11.3 CREACS NUREG(s)- 1432 Only SR 3.7.11.3 Bases CREACS NUREG(s)- 1432 Only SR 3.7.11.4 CREACS NUREG(s)- 1432 Only SR 3.7.11.4 Bases CREACS NUREG(s)- 1432 Only SR 3.7.12.1 CREATCS NUREG(s)- 1432 Only SR 3.7.12.1 Bases CREATCS NUREG(s)- 1432 Only SR 3.7.13.1 ECCS PREACS NUREG(s)- 1432 Only SR 3.7.13.1 Bases ECCS PREACS NUREG(s)- 1432 Only SR 3.7.13.3 ECCS PREACS NUREG(s)- 1432 Only SR 3.7.13.3 Bases ECCS PREACS NUREG(s)- 1432 Only SR 3.7.13.4 ECCS PREACS NUREG(s)- 1432 Only SR 3.7.13.4 Bases ECCS PREACS NUREG(s)- 1432 Only SR 3.7.13.5 ECCS PREACS NUREG(s)- 1432 Only SR 3.7.13.5 Bases ECCS PREACS NUREG(s)- 1432 Only SR 3.7.14.1 FBACS NUREG(s)- 1432 Only SR 3.7.14.1 Bases FBACS NUREG(s)- 1432 Only SR 3.7.14.3 FBACS NUREG(s)- 1432 Only SR 3.7.14.3 Bases FBACS NUREG(s)- 1432 Only SR 3.7.14.4 FBACS NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.7.14.4 Bases FBACS NUREG(s)- 1432 Only SR 3.7.14.5 FBACS NUREG(s)- 1432 Only SR 3.7.14.5 Bases FBACS NUREG(s)- 1432 Only SR 3.7.15.1 PREACS NUREG(s)- 1432 Only SR 3.7.15.1 Bases PREACS NUREG(s)- 1432 Only SR 3.7.15.3 PREACS NUREG(s)- 1432 Only SR 3.7.15.3 Bases PREACS NUREG(s)- 1432 Only SR 3.7.15.4 PREACS NUREG(s)- 1432 Only SR 3.7.15.4 Bases PREACS NUREG(s)- 1432 Only SR 3.7.15.5 PREACS NUREG(s)- 1432 Only SR 3.7.15.5 Bases PREACS NUREG(s)- 1432 Only SR 3.7.16.1 Fuel Storage Pool Water Level NUREG(s)- 1432 Only SR 3.7.16.1 Bases Fuel Storage Pool Water Level NUREG(s)- 1432 Only SR 3.7.17.1 Fuel Storage Pool Boron Concentration NUREG(s)- 1432 Only SR 3.7.17.1 Bases Fuel Storage Pool Boron Concentration NUREG(s)- 1432 Only SR 3.7.19.1 Secondary Specific Activity NUREG(s)- 1432 Only SR 3.7.19.1 Bases Secondary Specific Activity NUREG(s)- 1432 Only SR 3.9.2.1 Nuclear Instrumentation NUREG(s)- 1432 Only SR 3.9.2.1 Bases Nuclear Instrumentation NUREG(s)- 1432 Only SR 3.9.2.2 Nuclear Instrumentation NUREG(s)- 1432 Only SR 3.9.2.2 Bases Nuclear Instrumentation NUREG(s)- 1432 Only SR 3.9.4.1 SDC and Coolant Circulation - High Water Level NUREG(s)- 1432 Only SR 3.9.4.1 Bases SDC and Coolant Circulation - High Water Level NUREG(s)- 1432 Only SR 3.9.5.1 SDC and Coolant Circulation - Low Water Level NUREG(s)- 1432 Only SR 3.9.5.1 Bases SDC and Coolant Circulation - Low Water Level NUREG(s)- 1432 Only SR 3.9.5.2 SDC and Coolant Circulation - Low Water Level NUREG(s)- 1432 Only SR 3.9.5.2 Bases SDC and Coolant Circulation - Low Water Level NUREG(s)- 1432 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.9.6.1 Refueling Water Level NUREG(s)- 1432 Only SR 3.9.6.1 Bases Refueling Water Level NUREG(s)- 1432 Only SR 3.1.1.1 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.1 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.1 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.2 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.2 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.3 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.3 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.4 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.4 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.5 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.5 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.6 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.6 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.7 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.7 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.8 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.8 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.9 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.9 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.10 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.10 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.11 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.11 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.12 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.12 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.1.1.13 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.13 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.14 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.14 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.15 RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.1.15 Bases RPS Instrumentation NUREG(s)- 1433 1434 Only SR 3.1.3.1 Control Rod OPERABILITY NUREG(s)- 1433 1434 Only SR 3.1.3.1 Bases Control Rod OPERABILITY NUREG(s)- 1433 1434 Only SR 3.1.3.2 Control Rod OPERABILITY NUREG(s)- 1433 1434 Only SR 3.1.3.2 Bases Control Rod OPERABILITY NUREG(s)- 1433 1434 Only SR 3.1.3.3 Control Rod OPERABILITY NUREG(s)- 1433 1434 Only SR 3.1.3.3 Bases Control Rod OPERABILITY NUREG(s)- 1433 1434 Only SR 3.1.4.2 Control Rod Scram Times NUREG(s)- 1433 1434 Only SR 3.1.4.2 Bases Control Rod Scram Times NUREG(s)- 1433 1434 Only SR 3.1.5.1 Control Rod Scram Accumulators NUREG(s)- 1433 1434 Only SR 3.1.5.1 Bases Control Rod Scram Accumulators NUREG(s)- 1433 1434 Only SR 3.1.6.1 Rod Pattern Control NUREG(s)- 1433 1434 Only SR 3.1.6.1 Bases Rod Pattern Control NUREG(s)- 1433 1434 Only SR 3.1.7.1 SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.1 Bases SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.2 SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.2 Bases SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.3 SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.3 Bases SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.4 SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.4 Bases SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.5 SLC System NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.1.7.5 Bases SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.6 SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.6 Bases SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.7 SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.7 Bases SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.8 SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.8 Bases SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.9 SLC System NUREG(s)- 1433 1434 Only SR 3.1.7.9 Bases SLC System NUREG(s)- 1433 1434 Only SR 3.1.8.1 SDV Vent and Drain Valves NUREG(s)- 1433 1434 Only SR 3.1.8.1 Bases SDV Vent and Drain Valves NUREG(s)- 1433 1434 Only SR 3.1.8.2 SDV Vent and Drain Valves NUREG(s)- 1433 1434 Only SR 3.1.8.2 Bases SDV Vent and Drain Valves NUREG(s)- 1433 1434 Only SR 3.1.8.3 SDV Vent and Drain Valves NUREG(s)- 1433 1434 Only SR 3.1.8.3 SDV Vent and Drain Valves NUREG(s)- 1433 1434 Only SR 3.2.1.1 APLHGR NUREG(s)- 1433 1434 Only SR 3.2.1.1 Bases APLHGR NUREG(s)- 1433 1434 Only SR 3.2.2.1 MCPR NUREG(s)- 1433 1434 Only SR 3.2.2.1 Bases MCPR NUREG(s)- 1433 1434 Only SR 3.2.3.1 LHGR NUREG(s)- 1433 1434 Only SR 3.2.3.1 Bases LHGR NUREG(s)- 1433 1434 Only SR 3.2.4.1 APRM Gain and Setpoints NUREG(s)- 1433 1434 Only SR 3.2.4.1 Bases APRM Gain and Setpoints NUREG(s)- 1433 1434 Only SR 3.3.1.2.1 SRM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.1.2.1 Bases SRM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.1.2.2 SRM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.1.2.2 Bases SRM Instrumentation NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.1.2.3 SRM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.1.2.3 Bases SRM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.1.2.4 SRM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.1.2.4 Bases SRM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.1.2.5 SRM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.1.2.5 Bases SRM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.1.2.6 SRM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.1.2.6 Bases SRM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.1.2.7 SRM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.1.2.7 Bases SRM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.1 Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.1 Bases Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.2 Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.2 Bases Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.3 Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.3 Bases Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.4 Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.4 Bases Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.5 Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.5 Bases Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.6 Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.6 Bases Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.7 Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.2.1.7 Bases Control Rod Block Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.3.1.1 PAM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.3.1.1 Bases PAM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.3.1.2 PAM Instrumentation NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.3.1.2 Bases PAM Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.3.2.1 Remote Shutdown Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.3.2.1 Bases Remote Shutdown Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.3.2.2 Remote Shutdown Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.3.2.2 Bases Remote Shutdown Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.3.2.3 Remote Shutdown Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.3.2.3 Bases Remote Shutdown Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4..12 Bases EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.1.1 EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.1.1 Bases EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.1.2 EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.1.3 EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.1.3 Bases EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.1.4 EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.1.4 Bases EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.1.5 EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.1.5 Bases EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.1.6 EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.1.6 Bases EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.1.7 EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.1.7 Bases EOC-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.2.1 ATWS-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.2.1 Bases ATWS-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.2.2 ATWS-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.2.2 Bases ATWS-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.2.3 ATWS-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.2.3 Bases ATWS-RPT Instrumentation NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.4.2.4 ATWS-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.2.4 Bases ATWS-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.2.5 ATWS-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.4.2.5 Bases ATWS-RPT Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.1 ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.1 Bases ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.2 ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.2 Bases ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.3 ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.3 Bases ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.4 ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.4 Bases ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.5 ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.5 Bases ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.6 ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.6 Bases ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.7 ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.1.7 Bases ECCS Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.2.1 RCIC Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.2.1 Bases RCIC Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.2.2 RCIC Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.2.2 Bases RCIC Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.2.3 RCIC Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.2.3 Bases RCIC Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.2.4 RCIC Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.2.4 Bases RCIC Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.5.2.5 RCIC Instrumentation NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.5.2.5 Bases RCIC Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.1 Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.1 Bases Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.2 Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.2 Bases Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.3 Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.3 Bases Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.4 Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.4 Bases Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.5 Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.5 Bases Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.6 Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.6 Bases Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.7 Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.1.7 Bases Primary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.2.1 Secondary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.2.1 Bases Secondary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.2.2 Secondary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.2.2 Bases Secondary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.2.3 Secondary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.2.3 Bases Secondary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.2.4 Secondary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.2.4 Bases Secondary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.2.5 Secondary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.2.5 Bases Secondary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.2.6 Secondary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.6.2.6 Bases Secondary Containment Isolation Instrumentation NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.8.1.1 LOP Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.8.1.1 Bases LOP Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.8.1.2 LOP Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.8.1.2 Bases LOP Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.8.1.3 LOP Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.8.1.3 Bases LOP Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.8.1.4 LOP Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.8.1.4 Bases LOP Instrumentation NUREG(s)- 1433 1434 Only SR 3.3.8.2.1 RPS Electric Power Monitoring NUREG(s)- 1433 1434 Only SR 3.3.8.2.1 Bases RPS Electric Power Monitoring NUREG(s)- 1433 1434 Only SR 3.3.8.2.2 RPS Electric Power Monitoring NUREG(s)- 1433 1434 Only SR 3.3.8.2.2 Bases RPS Electric Power Monitoring NUREG(s)- 1433 1434 Only SR 3.3.8.2.3 RPS Electric Power Monitoring NUREG(s)- 1433 1434 Only SR 3.3.8.2.3 Bases RPS Electric Power Monitoring NUREG(s)- 1433 1434 Only SR 3.4.1.1 Recirculation Loops Operating NUREG(s)- 1433 1434 Only SR 3.4.1.1 Bases Recirculation Loops Operating NUREG(s)- 1433 1434 Only SR 3.5.1.1 ECCS - Operating NUREG(s)- 1433 1434 Only SR 3.5.1.1 Bases ECCS - Operating NUREG(s)- 1433 1434 Only SR 3.5.1.2 ECCS - Operating NUREG(s)- 1433 1434 Only SR 3.5.1.2 Bases ECCS - Operating NUREG(s)- 1433 1434 Only SR 3.5.1.3 ECCS - Operating NUREG(s)- 1433 1434 Only SR 3.5.1.3 Bases ECCS - Operating NUREG(s)- 1433 1434 Only SR 3.5.1.4 ECCS - Operating NUREG(s)- 1433 1434 Only SR 3.5.1.4 Bases ECCS - Operating NUREG(s)- 1433 1434 Only SR 3.5.1.5 Bases ECCS - Operating NUREG(s)- 1433 1434 Only SR 3.5.1.7 ECCS - Operating NUREG(s)- 1433 1434 Only SR 3.5.1.7 Bases ECCS - Operating NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.5.2.1 ECCS - Shutdown NUREG(s)- 1433 1434 Only SR 3.5.2.1 Bases ECCS - Shutdown NUREG(s)- 1433 1434 Only SR 3.5.2.2 ECCS - Shutdown NUREG(s)- 1433 1434 Only SR 3.5.2.2 Bases ECCS - Shutdown NUREG(s)- 1433 1434 Only SR 3.5.2.3 ECCS - Shutdown NUREG(s)- 1433 1434 Only SR 3.5.2.3 Bases ECCS - Shutdown NUREG(s)- 1433 1434 Only SR 3.5.2.4 ECCS - Shutdown NUREG(s)- 1433 1434 Only SR 3.5.2.4 Bases ECCS - Shutdown NUREG(s)- 1433 1434 Only SR 3.5.2.5 ECCS - Shutdown NUREG(s)- 1433 1434 Only SR 3.5.2.5 Bases ECCS - Shutdown NUREG(s)- 1433 1434 Only SR 3.5.2.6 ECCS - Shutdown NUREG(s)- 1433 1434 Only SR 3.5.2.6 Bases ECCS - Shutdown NUREG(s)- 1433 1434 Only SR 3.5.3.1 RCIC System NUREG(s)- 1433 1434 Only SR 3.5.3.1 Bases RCIC System NUREG(s)- 1433 1434 Only SR 3.5.3.2 RCIC System NUREG(s)- 1433 1434 Only SR 3.5.3.2 Bases RCIC System NUREG(s)- 1433 1434 Only SR 3.5.3.3 RCIC System NUREG(s)- 1433 1434 Only SR 3.5.3.3 Bases RCIC System NUREG(s)- 1433 1434 Only SR 3.5.3.4 RCIC System NUREG(s)- 1433 1434 Only SR 3.5.3.4 Bases RCIC System NUREG(s)- 1433 1434 Only SR 3.5.3.5 RCIC System NUREG(s)- 1433 1434 Only SR 3.5.3.5 Bases RCIC System NUREG(s)- 1433 1434 Only SR 3.6.1.2.2 Primary Containment Air Locks NUREG(s)- 1433 1434 Only SR 3.6.1.2.2 Bases Primary Containment Air Locks NUREG(s)- 1433 1434 Only SR 3.6.1.3.1 PCIVs NUREG(s)- 1433 1434 Only SR 3.6.1.3.2 PCIVs NUREG(s)- 1433 1434 Only SR 3.6.1.3.3 PCIVs NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.1.3.5 PCIVs NUREG(s)- 1433 1434 Only SR 3.6.1.3.6 PCIVs NUREG(s)- 1433 1434 Only SR 3.6.1.3.7 PCIVs NUREG(s)- 1433 1434 Only SR 3.6.1.3.8 PCIVs NUREG(s)- 1433 1434 Only SR 3.6.1.3.10 PCIVs NUREG(s)- 1433 1434 Only SR 3.6.1.6.1 LLS Valves NUREG(s)- 1433 1434 Only SR 3.6.1.6.1 Bases LLS Valves NUREG(s)- 1433 1434 Only SR 3.6.1.6.2 LLS Valves NUREG(s)- 1433 1434 Only SR 3.6.1.6.2 Bases LLS Valves NUREG(s)- 1433 1434 Only SR 3.6.1.9.1 MSIV LCS NUREG(s)- 1433 1434 Only SR 3.6.1.9.1 Bases MSIV LCS NUREG(s)- 1433 1434 Only SR 3.6.1.9.2 MSIV LCS NUREG(s)- 1433 1434 Only SR 3.6.1.9.2 Bases MSIV LCS NUREG(s)- 1433 1434 Only SR 3.6.1.9.3 MSIV LCS NUREG(s)- 1433 1434 Only SR 3.6.1.9.3 Bases MSIV LCS NUREG(s)- 1433 1434 Only SR 3.6.2.1.1 Supression Pool Average Temperature NUREG(s)- 1433 1434 Only SR 3.6.2.1.1 Bases Supression Pool Average Temperature NUREG(s)- 1433 1434 Only SR 3.6.2.2.1 Supression Pool Water Level NUREG(s)- 1433 1434 Only SR 3.6.2.2.1 Bases Supression Pool Water Level NUREG(s)- 1433 1434 Only SR 3.6.3.2.1 RHR Suppression Pool Cooling NUREG(s)- 1433 1434 Only SR 3.6.3.2.1 Bases RHR Suppression Pool Cooling NUREG(s)- 1433 1434 Only SR 3.6.3.2.2 RHR Suppression Pool Cooling NUREG(s)- 1433 1434 Only SR 3.6.3.2.2 Bases RHR Suppression Pool Cooling NUREG(s)- 1433 1434 Only SR 3.6.4.1.1 Secondary Containment NUREG(s)- 1433 1434 Only SR 3.6.4.1.1 Bases Secondary Containment NUREG(s)- 1433 1434 Only SR 3.6.4.1.2 Secondary Containment NUREG(s)- 1433 1434 Only SR 3.6.4.1.2 Bases Secondary Containment NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.4.1.3 Secondary Containment NUREG(s)- 1433 1434 Only SR 3.6.4.1.3 Bases Secondary Containment NUREG(s)- 1433 1434 Only SR 3.6.4.1.4 Secondary Containment NUREG(s)- 1433 1434 Only SR 3.6.4.1.4 Bases Secondary Containment NUREG(s)- 1433 1434 Only SR 3.6.4.1.5 Secondary Containment NUREG(s)- 1433 1434 Only SR 3.6.4.1.5 Bases Secondary Containment NUREG(s)- 1433 1434 Only SR 3.6.4.2.1 SCIVs NUREG(s)- 1433 1434 Only SR 3.6.4.2.1 Bases SCIVs NUREG(s)- 1433 1434 Only SR 3.6.4.2.2 SCIVs NUREG(s)- 1433 1434 Only SR 3.6.4.2.2 SCIVs NUREG(s)- 1433 1434 Only SR 3.6.4.2.3 SCIVs NUREG(s)- 1433 1434 Only SR 3.6.4.2.3 Bases SCIVs NUREG(s)- 1433 1434 Only SR 3.6.4.3.1 SGT System NUREG(s)- 1433 1434 Only SR 3.6.4.3.1 Bases SGT System NUREG(s)- 1433 1434 Only SR 3.6.4.3.3 SGT System NUREG(s)- 1433 1434 Only SR 3.6.4.3.3 Bases SGT System NUREG(s)- 1433 1434 Only SR 3.6.4.3.4 SGT System NUREG(s)- 1433 1434 Only SR 3.6.4.3.4 Bases SGT System NUREG(s)- 1433 1434 Only SR 3.8.1.1 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.1 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.2 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.2 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.3 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.3 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.4 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.4 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.5 AC Sources - Operating NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.8.1.5 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.6 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.6 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.7 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.7 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.8 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.8 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.9 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.9 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.10 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.11 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.11 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.12 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.12 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.13 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.13 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.14 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.14 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.15 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.15 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.16 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.16 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.17 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.17 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.18 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.18 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.19 AC Sources - Operating NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.8.1.19 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.20 AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.1.20 Bases AC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.2.1 Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1433 1434 Only SR 3.8.2.1 Bases Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1433 1434 Only SR 3.8.2.2 Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1433 1434 Only SR 3.8.2.2 Bases Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1433 1434 Only SR 3.8.2.4 Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1433 1434 Only SR 3.8.2.4 Bases Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1433 1434 Only SR 3.8.2.5 Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1433 1434 Only SR 3.8.2.5 Bases Diesel Fuel Oil, Lube Oil, and Starting Air NUREG(s)- 1433 1434 Only SR 3.8.4.1 DC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.4.1 Bases DC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.4.2 DC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.4.2 Bases DC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.4.3 DC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.4.3 Bases DC Sources - Operating NUREG(s)- 1433 1434 Only SR 3.8.6.1 Battery Parameters NUREG(s)- 1433 1434 Only SR 3.8.6.1 Bases Battery Parameters NUREG(s)- 1433 1434 Only SR 3.8.6.2 Battery Parameters NUREG(s)- 1433 1434 Only SR 3.8.6.2 Bases Battery Parameters NUREG(s)- 1433 1434 Only SR 3.8.6.3 Battery Parameters NUREG(s)- 1433 1434 Only SR 3.8.6.3 Bases Battery Parameters NUREG(s)- 1433 1434 Only SR 3.8.6.4 Battery Parameters NUREG(s)- 1433 1434 Only SR 3.8.6.4 Bases Battery Parameters NUREG(s)- 1433 1434 Only SR 3.8.6.5 Battery Parameters NUREG(s)- 1433 1434 Only SR 3.8.6.5 Bases Battery Parameters NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.8.6.6 Battery Parameters NUREG(s)- 1433 1434 Only SR 3.8.6.6 Bases Battery Parameters NUREG(s)- 1433 1434 Only SR 3.8.7.1 Inverters - Operating NUREG(s)- 1433 1434 Only SR 3.8.7.1 Bases Inverters - Operating NUREG(s)- 1433 1434 Only SR 3.8.8.1 Inverters - Shutdown NUREG(s)- 1433 1434 Only SR 3.8.8.1 Bases Inverters - Shutdown NUREG(s)- 1433 1434 Only SR 3.8.9.1 Distribution Systems - Operating NUREG(s)- 1433 1434 Only SR 3.8.9.1 Bases Distribution Systems - Operating NUREG(s)- 1433 1434 Only SR 3.8.10.1 Distribution Systems - Shutdown NUREG(s)- 1433 1434 Only SR 3.8.10.1 Bases Distribution Systems - Shutdown NUREG(s)- 1433 1434 Only SR 3.9.1.1 Refueling Equipment Interlocks NUREG(s)- 1433 1434 Only SR 3.9.1.1 Bases Refueling Equipment Interlocks NUREG(s)- 1433 1434 Only SR 3.9.2.1 Refueling Position One-Rod-Out Interlock NUREG(s)- 1433 1434 Only SR 3.9.2.1 Bases Refueling Position One-Rod-Out Interlock NUREG(s)- 1433 1434 Only SR 3.9.2.2 Refueling Position One-Rod-Out Interlock NUREG(s)- 1433 1434 Only SR 3.9.2.2 Bases Refueling Position One-Rod-Out Interlock NUREG(s)- 1433 1434 Only SR 3.9.3.1 Control Rod Position NUREG(s)- 1433 1434 Only SR 3.9.3.1 Bases Control Rod Position NUREG(s)- 1433 1434 Only SR 3.9.5.1 Control Rod OPERABILITY - Refueling NUREG(s)- 1433 1434 Only SR 3.9.5.1 Bases Control Rod OPERABILITY - Refueling NUREG(s)- 1433 1434 Only SR 3.9.5.2 Control Rod OPERABILITY - Refueling NUREG(s)- 1433 1434 Only SR 3.9.5.2 Bases Control Rod OPERABILITY - Refueling NUREG(s)- 1433 1434 Only SR 3.9.6.1 [RPV] Water Level - [Irradiated Fuel] NUREG(s)- 1433 1434 Only SR 3.9.6.1 Bases [RPV] Water Level - [Irradiated Fuel] NUREG(s)- 1433 1434 Only SR 3.9.7.1 [RPV] Water Level - [New Fuel or Control Rods] NUREG(s)- 1433 1434 Only SR 3.9.7.1 Bases [RPV] Water Level - [New Fuel or Control Rods] NUREG(s)- 1433 1434 Only SR 3.9.8.1 RHR - High Water Level NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.9.8.1 Bases RHR - High Water Level NUREG(s)- 1433 1434 Only SR 3.9.9.1 RHR - Low Water Level NUREG(s)- 1433 1434 Only SR 3.9.9.1 Bases RHR - Low Water Level NUREG(s)- 1433 1434 Only SR 3.10.2.1 Reactor Mode Switch Interlock Testing NUREG(s)- 1433 1434 Only SR 3.10.2.1 Bases Reactor Mode Switch Interlock Testing NUREG(s)- 1433 1434 Only SR 3.10.2.2 Reactor Mode Switch Interlock Testing NUREG(s)- 1433 1434 Only SR 3.10.2.2 Bases Reactor Mode Switch Interlock Testing NUREG(s)- 1433 1434 Only SR 3.10.3.2 Single Control Rod Withdrawal - Hot Shutdown NUREG(s)- 1433 1434 Only SR 3.10.3.2 Bases Single Control Rod Withdrawal - Hot Shutdown NUREG(s)- 1433 1434 Only SR 3.10.3.3 Single Control Rod Withdrawal - Hot Shutdown NUREG(s)- 1433 1434 Only SR 3.10.3.3 Bases Single Control Rod Withdrawal - Hot Shutdown NUREG(s)- 1433 1434 Only SR 3.10.4.2 Single Cotnrol Rod Withdrawal - Cold Shutdown NUREG(s)- 1433 1434 Only SR 3.10.4.2 Bases Single Cotnrol Rod Withdrawal - Cold Shutdown NUREG(s)- 1433 1434 Only SR 3.10.4.3 Single Cotnrol Rod Withdrawal - Cold Shutdown NUREG(s)- 1433 1434 Only SR 3.10.4.3 Bases Single Cotnrol Rod Withdrawal - Cold Shutdown NUREG(s)- 1433 1434 Only SR 3.10.4.4 Single Cotnrol Rod Withdrawal - Cold Shutdown NUREG(s)- 1433 1434 Only SR 3.10.4.4 Bases Single Cotnrol Rod Withdrawal - Cold Shutdown NUREG(s)- 1433 1434 Only SR 3.10.5.1 Single CRD Removal - Refueling NUREG(s)- 1433 1434 Only SR 3.10.5.1 Bases Single CRD Removal - Refueling NUREG(s)- 1433 1434 Only SR 3.10.5.2 Single CRD Removal - Refueling NUREG(s)- 1433 1434 Only SR 3.10.5.2 Bases Single CRD Removal - Refueling NUREG(s)- 1433 1434 Only SR 3.10.5.3 Single CRD Removal - Refueling NUREG(s)- 1433 1434 Only SR 3.10.5.3 Bases Single CRD Removal - Refueling NUREG(s)- 1433 1434 Only SR 3.10.5.5 Single CRD Removal - Refueling NUREG(s)- 1433 1434 Only SR 3.10.5.5 Bases Single CRD Removal - Refueling NUREG(s)- 1433 1434 Only SR 3.10.6.1 Multiple Control Rod Withdrawal - Refueling NUREG(s)- 1433 1434 Only SR 3.10.6.1 Bases Multiple Control Rod Withdrawal - Refueling NUREG(s)- 1433 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.10.6.2 Multiple Control Rod Withdrawal - Refueling NUREG(s)- 1433 1434 Only SR 3.10.6.2 Bases Multiple Control Rod Withdrawal - Refueling NUREG(s)- 1433 1434 Only SR 3.10.6.3 Multiple Control Rod Withdrawal - Refueling NUREG(s)- 1433 1434 Only SR 3.10.6.3 Bases Multiple Control Rod Withdrawal - Refueling NUREG(s)- 1433 1434 Only SR 3.10.8.4 SDM Test - Refueling NUREG(s)- 1433 1434 Only SR 3.10.8.6 SDM Test - Refueling NUREG(s)- 1433 1434 Only SR 3.10.8.6 Bases SDM Test - Refueling NUREG(s)- 1433 1434 Only SR 3.10.9.1 Recirculation Loops - Testing NUREG(s)- 1433 1434 Only SR 3.10.9.1 Bases Recirculation Loops - Testing NUREG(s)- 1433 1434 Only SR 3.10.9.2 Recirculation Loops - Testing NUREG(s)- 1433 1434 Only SR 3.10.9.2 Bases Recirculation Loops - Testing NUREG(s)- 1433 1434 Only SR 3.10.10.1 Training Startups NUREG(s)- 1433 1434 Only SR 3.10.10.1 Bases Training Startups NUREG(s)- 1433 1434 Only SR 3.10.10.2 Training Startups NUREG(s)- 1433 1434 Only SR 3.10.10.2 Bases Training Startups NUREG(s)- 1433 1434 Only 5.5.15 Surveillance Frequency Control Program NUREG(s)- 1433 1434 Only Change
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| == Description:==
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| New Program SR 3.3.2.2.1 Feedwater and Main Turbine High Water Level Trip NUREG(s)- 1433 Only Instrumentation SR 3.3.2.2.1 Bases Feedwater and Main Turbine High Water Level Trip NUREG(s)- 1433 Only Instrumentation SR 3.3.2.2.2 Feedwater and Main Turbine High Water Level Trip NUREG(s)- 1433 Only Instrumentation SR 3.3.2.2.2 Bases Feedwater and Main Turbine High Water Level Trip NUREG(s)- 1433 Only Instrumentation SR 3.3.2.2.3 Feedwater and Main Turbine High Water Level Trip NUREG(s)- 1433 Only Instrumentation SR 3.3.2.2.3 Bases Feedwater and Main Turbine High Water Level Trip NUREG(s)- 1433 Only Instrumentation SR 3.3.2.2.4 Feedwater and Main Turbine High Water Level Trip NUREG(s)- 1433 Only Instrumentation 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.2.2.4 Bases Feedwater and Main Turbine High Water Level Trip NUREG(s)- 1433 Only Instrumentation SR 3.3.5.2.6 RCIC Instrumentation NUREG(s)- 1433 Only SR 3.3.5.2.6 Bases RCIC Instrumentation NUREG(s)- 1433 Only SR 3.3.6.1.8 Primary Containment Isolation Instrumentation NUREG(s)- 1433 Only SR 3.3.6.1.8 Bases Primary Containment Isolation Instrumentation NUREG(s)- 1433 Only SR 3.3.6.2.7 Secondary Containment Isolation Instrumentation NUREG(s)- 1433 Only SR 3.3.6.2.7 Bases Secondary Containment Isolation Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.1 LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.1 Bases LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.2 LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.2 Bases LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.3 LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.3 Bases LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.4 LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.4 Bases LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.5 LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.5 Bases LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.6 LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.6 Bases LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.7 LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.6.3.7 Bases LLS Instrumentation NUREG(s)- 1433 Only SR 3.3.7.1.1 [MCREC} System Instrumentation NUREG(s)- 1433 Only SR 3.3.7.1.1 Bases [MCREC} System Instrumentation NUREG(s)- 1433 Only SR 3.3.7.1.2 [MCREC} System Instrumentation NUREG(s)- 1433 Only SR 3.3.7.1.2 Bases [MCREC} System Instrumentation NUREG(s)- 1433 Only SR 3.3.7.1.3 [MCREC} System Instrumentation NUREG(s)- 1433 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.7.1.3 Bases [MCREC} System Instrumentation NUREG(s)- 1433 Only SR 3.3.7.1.4 [MCREC} System Instrumentation NUREG(s)- 1433 Only SR 3.3.7.1.4 Bases [MCREC} System Instrumentation NUREG(s)- 1433 Only SR 3.3.7.1.5 [MCREC} System Instrumentation NUREG(s)- 1433 Only SR 3.3.7.1.5 Bases [MCREC} System Instrumentation NUREG(s)- 1433 Only SR 3.4.2.1 Jet Pumps NUREG(s)- 1433 Only SR 3.4.2.1 Bases Jet Pumps NUREG(s)- 1433 Only SR 3.4.3.1 S/RVs NUREG(s)- 1433 Only SR 3.4.3.1 Bases S/RVs NUREG(s)- 1433 Only SR 3.4.3.2 S/RVs NUREG(s)- 1433 Only SR 3.4.3.2 Bases S/RVs NUREG(s)- 1433 Only SR 3.4.4.1 RCS Operational Leakage NUREG(s)- 1433 Only SR 3.4.4.1 Bases RCS Operational Leakage NUREG(s)- 1433 Only SR 3.4.5.1 RCS PIV Leakage NUREG(s)- 1433 Only SR 3.4.5.1 Bases RCS PIV Leakage NUREG(s)- 1433 Only SR 3.4.6.1 RCS Leakae Detection Instrumentation NUREG(s)- 1433 Only SR 3.4.6.1 Bases RCS Leakae Detection Instrumentation NUREG(s)- 1433 Only SR 3.4.6.2 RCS Leakae Detection Instrumentation NUREG(s)- 1433 Only SR 3.4.6.2 Bases RCS Leakae Detection Instrumentation NUREG(s)- 1433 Only SR 3.4.6.3 RCS Leakae Detection Instrumentation NUREG(s)- 1433 Only SR 3.4.6.3 Bases RCS Leakae Detection Instrumentation NUREG(s)- 1433 Only SR 3.4.7.1 RCS Specific Activity NUREG(s)- 1433 Only SR 3.4.7.1 Bases RCS Specific Activity NUREG(s)- 1433 Only SR 3.4.8.1 RHR Shutdown Cooling System - Hot Shutdown NUREG(s)- 1433 Only SR 3.4.8.1 Bases RHR Shutdown Cooling System - Hot Shutdown NUREG(s)- 1433 Only SR 3.4.9.1 RHR Shutdown Cooling System - Cold Shutdown NUREG(s)- 1433 Only SR 3.4.9.1 Bases RHR Shutdown Cooling System - Cold Shutdown NUREG(s)- 1433 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.4.10.1 RCS P/T Limits NUREG(s)- 1433 Only SR 3.4.10.1 Bases RCS P/T Limits NUREG(s)- 1433 Only SR 3.4.10.7 RCS P/T Limits NUREG(s)- 1433 Only SR 3.4.10.7 Bases RCS P/T Limits NUREG(s)- 1433 Only SR 3.4.10.8 RCS P/T Limits NUREG(s)- 1433 Only SR 3.4.10.8 Bases RCS P/T Limits NUREG(s)- 1433 Only SR 3.4.10.9 RCS P/T Limits NUREG(s)- 1433 Only SR 3.4.10.9 Bases RCS P/T Limits NUREG(s)- 1433 Only SR 3.4.11.1 Reactor Steam Dome Pressure NUREG(s)- 1433 Only SR 3.4.11.1 Bases Reactor Steam Dome Pressure NUREG(s)- 1433 Only SR 3.5.1.5 ECCS - Operating NUREG(s)- 1433 Only SR 3.5.1.8 ECCS - Operating NUREG(s)- 1433 Only SR 3.5.1.8 Bases ECCS - Operating NUREG(s)- 1433 Only SR 3.5.1.9 ECCS - Operating NUREG(s)- 1433 Only SR 3.5.1.9 Bases ECCS - Operating NUREG(s)- 1433 Only SR 3.5.1.10 ECCS - Operating NUREG(s)- 1433 Only SR 3.5.1.10 Bases ECCS - Operating NUREG(s)- 1433 Only SR 3.5.1.11 ECCS - Operating NUREG(s)- 1433 Only SR 3.5.1.11 Bases ECCS - Operating NUREG(s)- 1433 Only SR 3.5.1.12 ECCS - Operating NUREG(s)- 1433 Only SR 3.5.1.12 Bases ECCS - Operating NUREG(s)- 1433 Only SR 3.6.1.1.2 Primary Containment NUREG(s)- 1433 Only SR 3.6.1.1.2 Bases Primary Containment NUREG(s)- 1433 Only SR 3.6.1.3.9 PCIVs NUREG(s)- 1433 Only SR 3.6.1.3.11 PCIVs NUREG(s)- 1433 Only SR 3.6.1.3.15 PCIVs NUREG(s)- 1433 Only SR 3.6.1.4.1 Drywell Pressure NUREG(s)- 1433 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.1.4.1 Bases Drywell Pressure NUREG(s)- 1433 Only SR 3.6.1.5.1 Drywell Air Temperature NUREG(s)- 1433 Only SR 3.6.1.5.1 Bases Drywell Air Temperature NUREG(s)- 1433 Only SR 3.6.1.7.1 Reactor Building-to-Supression Chamber Vacuum Breakers NUREG(s)- 1433 Only SR 3.6.1.7.1 Bases Reactor Building-to-Supression Chamber Vacuum Breakers NUREG(s)- 1433 Only SR 3.6.1.7.2 Reactor Building-to-Supression Chamber Vacuum Breakers NUREG(s)- 1433 Only SR 3.6.1.7.2 Bases Reactor Building-to-Supression Chamber Vacuum Breakers NUREG(s)- 1433 Only SR 3.6.1.7.3 Reactor Building-to-Supression Chamber Vacuum Breakers NUREG(s)- 1433 Only SR 3.6.1.7.3 Bases Reactor Building-to-Supression Chamber Vacuum Breakers NUREG(s)- 1433 Only SR 3.6.1.8.1 Supression Chamber-to-Drywell Vacuum Breakers NUREG(s)- 1433 Only SR 3.6.1.8.1 Bases Supression Chamber-to-Drywell Vacuum Breakers NUREG(s)- 1433 Only SR 3.6.1.8.2 Supression Chamber-to-Drywell Vacuum Breakers NUREG(s)- 1433 Only SR 3.6.1.8.2 Bases Supression Chamber-to-Drywell Vacuum Breakers NUREG(s)- 1433 Only SR 3.6.1.8.3 Supression Chamber-to-Drywell Vacuum Breakers NUREG(s)- 1433 Only SR 3.6.1.8.3 Bases Supression Chamber-to-Drywell Vacuum Breakers NUREG(s)- 1433 Only SR 3.6.2.4.1 RHR Suppression Pool Spray NUREG(s)- 1433 Only SR 3.6.2.4.1 Bases RHR Suppression Pool Spray NUREG(s)- 1433 Only SR 3.6.2.4.2 RHR Suppression Pool Spray NUREG(s)- 1433 Only SR 3.6.2.4.2 Bases RHR Suppression Pool Spray NUREG(s)- 1433 Only SR 3.6.2.5.1 Drywell-to-Suppression Chamber Differential Pressure NUREG(s)- 1433 Only SR 3.6.2.5.1 Bases Drywell-to-Suppression Chamber Differential Pressure NUREG(s)- 1433 Only SR 3.6.3.1.1 Drywell Cooling System Fans NUREG(s)- 1433 Only SR 3.6.3.1.1 Bases Drywell Cooling System Fans NUREG(s)- 1433 Only SR 3.6.3.1.2 Drywell Cooling System Fans NUREG(s)- 1433 Only SR 3.6.3.1.2 Bases Drywell Cooling System Fans NUREG(s)- 1433 Only SR 3.6.3.2.1 Primary Containment Oxygen Concentration NUREG(s)- 1433 Only SR 3.6.3.2.1 Bases Primary Containment Oxygen Concentration NUREG(s)- 1433 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.3.3.1 CAD System NUREG(s)- 1433 Only SR 3.6.3.3.1 Bases CAD System NUREG(s)- 1433 Only SR 3.6.3.3.2 CAD System NUREG(s)- 1433 Only SR 3.6.3.3.2 Bases CAD System NUREG(s)- 1433 Only SR 3.7.1.1 RHRSW System NUREG(s)- 1433 Only SR 3.7.1.1 Bases RHRSW System NUREG(s)- 1433 Only SR 3.7.2.1 [PSW] System and [UHS} NUREG(s)- 1433 Only SR 3.7.2.1 Bases [PSW] System and [UHS} NUREG(s)- 1433 Only SR 3.7.2.2 [PSW] System and [UHS} NUREG(s)- 1433 Only SR 3.7.2.2 Bases [PSW] System and [UHS} NUREG(s)- 1433 Only SR 3.7.2.3 [PSW] System and [UHS} NUREG(s)- 1433 Only SR 3.7.2.3 Bases [PSW] System and [UHS} NUREG(s)- 1433 Only SR 3.7.2.4 [PSW] System and [UHS} NUREG(s)- 1433 Only SR 3.7.2.4 Bases [PSW] System and [UHS} NUREG(s)- 1433 Only SR 3.7.2.5 [PSW] System and [UHS} NUREG(s)- 1433 Only SR 3.7.2.5 Bases [PSW] System and [UHS} NUREG(s)- 1433 Only SR 3.7.2.6 [PSW] System and [UHS} NUREG(s)- 1433 Only SR 3.7.2.6 Bases [PSW] System and [UHS} NUREG(s)- 1433 Only SR 3.7.3.1 DB[1B] SSW System NUREG(s)- 1433 Only SR 3.7.3.1 Bases DB[1B] SSW System NUREG(s)- 1433 Only SR 3.7.3.2 DB[1B] SSW System NUREG(s)- 1433 Only SR 3.7.3.2 Bases DB[1B] SSW System NUREG(s)- 1433 Only SR 3.7.4.1 [MCREC] System NUREG(s)- 1433 Only SR 3.7.4.1 Bases [MCREC] System NUREG(s)- 1433 Only SR 3.7.4.3 [MCREC] System NUREG(s)- 1433 Only SR 3.7.4.3 Bases [MCREC] System NUREG(s)- 1433 Only SR 3.7.4.4 [MCREC] System NUREG(s)- 1433 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.7.4.4 Bases [MCREC] System NUREG(s)- 1433 Only SR 3.7.5.1 [Control Room AC] System NUREG(s)- 1433 Only SR 3.7.5.1 Bases [Control Room AC] System NUREG(s)- 1433 Only SR 3.7.6.1 Main Condenser Offgas System NUREG(s)- 1433 Only SR 3.7.6.1 Bases Main Condenser Offgas System NUREG(s)- 1433 Only SR 3.7.7.1 Main Turbine Bypass System NUREG(s)- 1433 Only SR 3.7.7.1 Bases Main Turbine Bypass System NUREG(s)- 1433 Only SR 3.7.7.2 Main Turbine Bypass System NUREG(s)- 1433 Only SR 3.7.7.2 Bases Main Turbine Bypass System NUREG(s)- 1433 Only SR 3.7.7.3 Main Turbine Bypass System NUREG(s)- 1433 Only SR 3.7.7.3 Bases Main Turbine Bypass System NUREG(s)- 1433 Only SR 3.7.8.1 Spent Fuel Storage Pool Water Level NUREG(s)- 1433 Only SR 3.7.8.1 Bases Spent Fuel Storage Pool Water Level NUREG(s)- 1433 Only SR 3.3.2.1.8 Control Rod Block Instrumentation NUREG(s)- 1434 Only SR 3.3.2.1.8 Bases Control Rod Block Instrumentation NUREG(s)- 1434 Only SR 3.3.6.3.1 RHR Containment Spray System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.3.1 Bases RHR Containment Spray System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.3.2 RHR Containment Spray System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.3.2 Bases RHR Containment Spray System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.3.3 RHR Containment Spray System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.3.3 Bases RHR Containment Spray System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.3.4 RHR Containment Spray System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.3.4 Bases RHR Containment Spray System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.3.5 RHR Containment Spray System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.3.5 Bases RHR Containment Spray System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.3.6 RHR Containment Spray System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.3.6 Bases RHR Containment Spray System Instrumentation NUREG(s)- 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.6.4.1 SPMU System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.4.1 Bases SPMU System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.4.2 SPMU System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.4.2 Bases SPMU System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.4.3 SPMU System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.4.3 Bases SPMU System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.4.4 SPMU System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.4.4 Bases SPMU System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.4.5 SPMU System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.4.5 Bases SPMU System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.4.6 SPMU System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.4.6 Bases SPMU System Instrumentation NUREG(s)- 1434 Only SR 3.3.6.5.1 Relief and LLS Instrumentation NUREG(s)- 1434 Only SR 3.3.6.5.1 Bases Relief and LLS Instrumentation NUREG(s)- 1434 Only SR 3.3.6.5.2 Relief and LLS Instrumentation NUREG(s)- 1434 Only SR 3.3.6.5.2 Bases Relief and LLS Instrumentation NUREG(s)- 1434 Only SR 3.3.6.5.3 Relief and LLS Instrumentation NUREG(s)- 1434 Only SR 3.3.6.5.3 Bases Relief and LLS Instrumentation NUREG(s)- 1434 Only SR 3.3.6.5.4 Relief and LLS Instrumentation NUREG(s)- 1434 Only SR 3.3.6.5.4 Bases Relief and LLS Instrumentation NUREG(s)- 1434 Only SR 3.3.7.1 [CRFA] Instrumentation NUREG(s)- 1434 Only SR 3.3.7.1 Bases [CRFA] Instrumentation NUREG(s)- 1434 Only SR 3.3.7.2 [CRFA] Instrumentation NUREG(s)- 1434 Only SR 3.3.7.2 Bases [CRFA] Instrumentation NUREG(s)- 1434 Only SR 3.3.7.3 [CRFA] Instrumentation NUREG(s)- 1434 Only SR 3.3.7.3 Bases [CRFA] Instrumentation NUREG(s)- 1434 Only SR 3.3.7.4 [CRFA] Instrumentation NUREG(s)- 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.3.7.4 Bases [CRFA] Instrumentation NUREG(s)- 1434 Only SR 3.3.7.5 [CRFA] Instrumentation NUREG(s)- 1434 Only SR 3.3.7.5 Bases [CRFA] Instrumentation NUREG(s)- 1434 Only SR 3.4.2.1 FCVs NUREG(s)- 1434 Only SR 3.4.2.1 Bases FCVs NUREG(s)- 1434 Only SR 3.4.2.2 FCVs NUREG(s)- 1434 Only SR 3.4.2.2 Bases FCVs NUREG(s)- 1434 Only SR 3.4.3.1 Jet Pumps NUREG(s)- 1434 Only SR 3.4.3.1 Bases Jet Pumps NUREG(s)- 1434 Only SR 3.4.4.1 S/RVs NUREG(s)- 1434 Only SR 3.4.4.1 Bases S/RVs NUREG(s)- 1434 Only SR 3.4.4.2 S/RVs NUREG(s)- 1434 Only SR 3.4.4.2 Bases S/RVs NUREG(s)- 1434 Only SR 3.4.4.3 S/RVs NUREG(s)- 1434 Only SR 3.4.4.3 Bases S/RVs NUREG(s)- 1434 Only SR 3.4.5.1 RCS Operational Leakage NUREG(s)- 1434 Only SR 3.4.5.1 Bases RCS Operational Leakage NUREG(s)- 1434 Only SR 3.4.6.1 RCS PIV Leakage NUREG(s)- 1434 Only SR 3.4.6.1 Bases RCS PIV Leakage NUREG(s)- 1434 Only SR 3.4.7.1 RCS Leakae Detection Instrumentation NUREG(s)- 1434 Only SR 3.4.7.1 Bases RCS Leakae Detection Instrumentation NUREG(s)- 1434 Only SR 3.4.7.2 RCS Leakae Detection Instrumentation NUREG(s)- 1434 Only SR 3.4.7.2 Bases RCS Leakae Detection Instrumentation NUREG(s)- 1434 Only SR 3.4.7.3 RCS Leakae Detection Instrumentation NUREG(s)- 1434 Only SR 3.4.7.3 Bases RCS Leakae Detection Instrumentation NUREG(s)- 1434 Only SR 3.4.8.1 RCS Specific Activity NUREG(s)- 1434 Only SR 3.4.8.1 Bases RCS Specific Activity NUREG(s)- 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.4.9.1 RHR Shutdown Cooling System - Hot Shutdown NUREG(s)- 1434 Only SR 3.4.9.1 Bases RHR Shutdown Cooling System - Hot Shutdown NUREG(s)- 1434 Only SR 3.4.10.1 RHR Shutdown Cooling System - Cold Shutdown NUREG(s)- 1434 Only SR 3.4.10.1 Bases RHR Shutdown Cooling System - Cold Shutdown NUREG(s)- 1434 Only SR 3.4.11.1 RCS P/T Limits NUREG(s)- 1434 Only SR 3.4.11.1 Bases RCS P/T Limits NUREG(s)- 1434 Only SR 3.4.11.7 RCS P/T Limits NUREG(s)- 1434 Only SR 3.4.11.7 Bases RCS P/T Limits NUREG(s)- 1434 Only SR 3.4.11.8 RCS P/T Limits NUREG(s)- 1434 Only SR 3.4.11.8 Bases RCS P/T Limits NUREG(s)- 1434 Only SR 3.4.11.9 RCS P/T Limits NUREG(s)- 1434 Only SR 3.4.11.9 Bases RCS P/T Limits NUREG(s)- 1434 Only SR 3.4.12.1 Reactor Steam Dome Pressure NUREG(s)- 1434 Only SR 3.4.12.1 Bases Reactor Steam Dome Pressure NUREG(s)- 1434 Only SR 3.5.1.6 ECCS - Operating NUREG(s)- 1434 Only SR 3.5.1.6 Bases ECCS - Operating NUREG(s)- 1434 Only SR 3.6.1.2.3 Primary Containment Air Locks NUREG(s)- 1434 Only SR 3.6.1.2.3 Bases Primary Containment Air Locks NUREG(s)- 1434 Only SR 3.6.1.2.4 Primary Containment Air Locks NUREG(s)- 1434 Only SR 3.6.1.2.4 Bases Primary Containment Air Locks NUREG(s)- 1434 Only SR 3.6.1.3.12 PCIVs NUREG(s)- 1434 Only SR 3.6.1.4.1 Primary Containment Pressure NUREG(s)- 1434 Only SR 3.6.1.4.1 Bases Primary Containment Pressure NUREG(s)- 1434 Only SR 3.6.1.5.1 Primary Containment Air Temperature NUREG(s)- 1434 Only SR 3.6.1.5.1 Bases Primary Containment Air Temperature NUREG(s)- 1434 Only SR 3.6.1.7.1 RHR Containment Spray System NUREG(s)- 1434 Only SR 3.6.1.7.1 Bases RHR Containment Spray System NUREG(s)- 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.1.7.2 RHR Containment Spray System NUREG(s)- 1434 Only SR 3.6.1.7.2 Bases RHR Containment Spray System NUREG(s)- 1434 Only SR 3.6.1.7.3 RHR Containment Spray System NUREG(s)- 1434 Only SR 3.6.1.7.3 Bases RHR Containment Spray System NUREG(s)- 1434 Only SR 3.6.1.7.4 RHR Containment Spray System NUREG(s)- 1434 Only SR 3.6.1.7.4 Bases RHR Containment Spray System NUREG(s)- 1434 Only SR 3.6.1.8.1 PVLCS NUREG(s)- 1434 Only SR 3.6.1.8.1 Bases PVLCS NUREG(s)- 1434 Only SR 3.6.1.8.2 PVLCS NUREG(s)- 1434 Only SR 3.6.1.8.2 Bases PVLCS NUREG(s)- 1434 Only SR 3.6.2.4.1 SPMU System NUREG(s)- 1434 Only SR 3.6.2.4.1 Bases SPMU System NUREG(s)- 1434 Only SR 3.6.2.4.2 SPMU System NUREG(s)- 1434 Only SR 3.6.2.4.2 Bases SPMU System NUREG(s)- 1434 Only SR 3.6.2.4.3 SPMU System NUREG(s)- 1434 Only SR 3.6.2.4.3 Bases SPMU System NUREG(s)- 1434 Only SR 3.6.2.4.4 SPMU System NUREG(s)- 1434 Only SR 3.6.2.4.4 Bases SPMU System NUREG(s)- 1434 Only SR 3.6.2.4.5 SPMU System NUREG(s)- 1434 Only SR 3.6.2.4.5 Bases SPMU System NUREG(s)- 1434 Only SR 3.6.3.1.1 Primary Containment and Drywell Hydrogen Ignitors NUREG(s)- 1434 Only SR 3.6.3.1.1 Bases Primary Containment and Drywell Hydrogen Ignitors NUREG(s)- 1434 Only SR 3.6.3.1.2 Primary Containment and Drywell Hydrogen Ignitors NUREG(s)- 1434 Only SR 3.6.3.1.2 Bases Primary Containment and Drywell Hydrogen Ignitors NUREG(s)- 1434 Only SR 3.6.3.1.3 Primary Containment and Drywell Hydrogen Ignitors NUREG(s)- 1434 Only SR 3.6.3.1.3 Bases Primary Containment and Drywell Hydrogen Ignitors NUREG(s)- 1434 Only SR 3.6.3.1.4 Primary Containment and Drywell Hydrogen Ignitors NUREG(s)- 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| | |
| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.3.1.4 Bases Primary Containment and Drywell Hydrogen Ignitors NUREG(s)- 1434 Only SR 3.6.3.2.1 Drywell Purge System NUREG(s)- 1434 Only SR 3.6.3.2.1 Bases Drywell Purge System NUREG(s)- 1434 Only SR 3.6.3.2.2 Drywell Purge System NUREG(s)- 1434 Only SR 3.6.3.2.2 Bases Drywell Purge System NUREG(s)- 1434 Only SR 3.6.5.1.1 Drywell NUREG(s)- 1434 Only SR 3.6.5.1.1 Bases Drywell NUREG(s)- 1434 Only SR 3.6.5.1.2 Drywell NUREG(s)- 1434 Only SR 3.6.5.1.2 Bases Drywell NUREG(s)- 1434 Only SR 3.6.5.2.1 Drywell Air Lock NUREG(s)- 1434 Only SR 3.6.5.2.1 Bases Drywell Air Lock NUREG(s)- 1434 Only SR 3.6.5.2.2 Drywell Air Lock NUREG(s)- 1434 Only SR 3.6.5.2.2 Bases Drywell Air Lock NUREG(s)- 1434 Only SR 3.6.5.2.3 Drywell Air Lock NUREG(s)- 1434 Only SR 3.6.5.2.3 Bases Drywell Air Lock NUREG(s)- 1434 Only SR 3.6.5.2.4 Drywell Air Lock NUREG(s)- 1434 Only SR 3.6.5.2.4 Bases Drywell Air Lock NUREG(s)- 1434 Only SR 3.6.5.2.5 Drywell Air Lock NUREG(s)- 1434 Only SR 3.6.5.2.5 Bases Drywell Air Lock NUREG(s)- 1434 Only SR 3.6.5.3.1 Drywell Isolation Valves NUREG(s)- 1434 Only SR 3.6.5.3.1 Bases Drywell Isolation Valves NUREG(s)- 1434 Only SR 3.6.5.3.2 Drywell Isolation Valves NUREG(s)- 1434 Only SR 3.6.5.3.2 Bases Drywell Isolation Valves NUREG(s)- 1434 Only SR 3.6.5.3.4 Drywell Isolation Valves NUREG(s)- 1434 Only SR 3.6.5.3.4 Bases Drywell Isolation Valves NUREG(s)- 1434 Only SR 3.6.5.3.5 Drywell Isolation Valves NUREG(s)- 1434 Only SR 3.6.5.3.5 Bases Drywell Isolation Valves NUREG(s)- 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| | |
| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.6.5.3.6 Drywell Isolation Valves NUREG(s)- 1434 Only SR 3.6.5.3.6 Bases Drywell Isolation Valves NUREG(s)- 1434 Only SR 3.6.5.4.1 Drywell Pressure NUREG(s)- 1434 Only SR 3.6.5.4.1 Bases Drywell Pressure NUREG(s)- 1434 Only SR 3.6.5.5.1 Drywell Air Temperature NUREG(s)- 1434 Only SR 3.6.5.5.1 Bases Drywell Air Temperature NUREG(s)- 1434 Only SR 3.6.5.6.1 Drywell Vacuum Relief System NUREG(s)- 1434 Only SR 3.6.5.6.1 Bases Drywell Vacuum Relief System NUREG(s)- 1434 Only SR 3.6.5.6.2 Drywell Vacuum Relief System NUREG(s)- 1434 Only SR 3.6.5.6.2 Bases Drywell Vacuum Relief System NUREG(s)- 1434 Only SR 3.6.5.6.3 Drywell Vacuum Relief System NUREG(s)- 1434 Only SR 3.6.5.6.3 Bases Drywell Vacuum Relief System NUREG(s)- 1434 Only SR 3.7.1.1 [SSW] System and [UHS] NUREG(s)- 1434 Only SR 3.7.1.1 Bases [SSW] System and [UHS] NUREG(s)- 1434 Only SR 3.7.1.2 [SSW] System and [UHS] NUREG(s)- 1434 Only SR 3.7.1.2 Bases [SSW] System and [UHS] NUREG(s)- 1434 Only SR 3.7.1.3 [SSW] System and [UHS] NUREG(s)- 1434 Only SR 3.7.1.3 Bases [SSW] System and [UHS] NUREG(s)- 1434 Only SR 3.7.1.4 [SSW] System and [UHS] NUREG(s)- 1434 Only SR 3.7.1.4 Bases [SSW] System and [UHS] NUREG(s)- 1434 Only SR 3.7.1.5 [SSW] System and [UHS] NUREG(s)- 1434 Only SR 3.7.1.5 Bases [SSW] System and [UHS] NUREG(s)- 1434 Only SR 3.7.1.6 [SSW] System and [UHS] NUREG(s)- 1434 Only SR 3.7.1.6 Bases [SSW] System and [UHS] NUREG(s)- 1434 Only SR 3.7.2.1 HPCS SWS NUREG(s)- 1434 Only SR 3.7.2.1 Bases HPCS SWS NUREG(s)- 1434 Only SR 3.7.2.2 HPCS SWS NUREG(s)- 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| | |
| BWROG-88, Rev. 0 TSTF-425, Rev. 3 SR 3.7.2.2 Bases HPCS SWS NUREG(s)- 1434 Only SR 3.7.2.3 HPCS SWS NUREG(s)- 1434 Only SR 3.7.2.3 Bases HPCS SWS NUREG(s)- 1434 Only SR 3.7.3.1 [Control Room Fresh Air (CRFA)] System NUREG(s)- 1434 Only SR 3.7.3.1 Bases [Control Room Fresh Air (CRFA)] System NUREG(s)- 1434 Only SR 3.7.3.3 [Control Room Fresh Air (CRFA)] System NUREG(s)- 1434 Only SR 3.7.3.3 Bases [Control Room Fresh Air (CRFA)] System NUREG(s)- 1434 Only SR 3.7.3.4 [Control Room Fresh Air (CRFA)] System NUREG(s)- 1434 Only SR 3.7.3.4 Bases [Control Room Fresh Air (CRFA)] System NUREG(s)- 1434 Only SR 3.7.4.1 [Control Room AC] System NUREG(s)- 1434 Only SR 3.7.4.1 Bases [Control Room AC] System NUREG(s)- 1434 Only SR 3.7.5.1 Main Condenser Offgas System NUREG(s)- 1434 Only SR 3.7.5.1 Bases Main Condenser Offgas System NUREG(s)- 1434 Only SR 3.7.6.1 Main Turbine Bypass System NUREG(s)- 1434 Only SR 3.7.6.1 Bases Main Turbine Bypass System NUREG(s)- 1434 Only SR 3.7.6.2 Main Turbine Bypass System NUREG(s)- 1434 Only SR 3.7.6.2 Bases Main Turbine Bypass System NUREG(s)- 1434 Only SR 3.7.6.3 Main Turbine Bypass System NUREG(s)- 1434 Only SR 3.7.6.3 Bases Main Turbine Bypass System NUREG(s)- 1434 Only SR 3.7.7.1 Fuel Pool Water Level NUREG(s)- 1434 Only SR 3.7.7.1 Bases Fuel Pool Water Level NUREG(s)- 1434 Only SR 3.8.1.10 Bases AC Sources - Operating NUREG(s)- 1434 Only SR 3.10.8.4 Bases SDM Test - Refueling NUREG(s)- 1434 Only 18-Mar-09 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.
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| TSTF-425, Rev. 3 INSERT 1 OR In accordance with the Surveillance Frequency Control Program ]
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| INSERT 2 OR The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
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| --------------------------------------------- REVIEWERS NOTE ---------------------------------------
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| Plants controlling Surveillance Frequencies under a Surveillance Frequency Control Program should utilize the appropriate Frequency description, given above, and the appropriate choice of Frequency in the Surveillance Requirement.
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| ------------------------------------------------------------------------------------------------------------------ ]
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| | |
| TSTF-425, Rev. 3 INSERT 3 5.5.15 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.
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| : a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.
| |
| : b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.
| |
| : c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.
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| INSERT 4 5.5.18 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.
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| : a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.
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| : b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.
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| : c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.
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| TSTF-425, Rev. 3 Definitions Definitions 1.1 1.1 1.1 1.1 Definitions Definitions SHUTDOWN SHUTDOWN MARGIN MARGIN (SDM)
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| (SDM) SDM SDM shall shall bebe the the instantaneous instantaneous amount amount of of reactivity reactivity by by which which the reactor the reactor is is subcritical subcritical or or would would be be subcritical subcritical from from its its present condition present condition assuming:
| |
| assuming:
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| a.
| |
| : a. All full All full length length CONTROL CONTROL RODS RODS (safety (safety and and regulating) regulating) are fully are fully inserted inserted except except forfor the the single single CONTROL CONTROL ROD ROD of highest of highest reactivity reactivity worth, worth, which which is is assumed assumed to to be be fully fully withdrawn. However, withdrawn. However, with with allall CONTROL CONTROL RODS RODS verified verified fully inserted fully inserted by by two two independent independent means, means, itit is is not not necessary to necessary to account account for for aa stuck stuck CONTROL CONTROL ROD ROD in in the the SDM calculation.
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| SDM calculation. With With anyany CONTROL CONTROL ROD ROD not not capable capable of being of being fully fully inserted, inserted, thethe reactivity reactivity worth worth of of these these CONTROL RODS CONTROL RODS mustmust be be accounted accounted for for in in the the determination of determination of SDM, SDM, b.
| |
| : b. In MODES In MODES 1 1 and and 2,2, the the fuel fuel and and moderator moderator temperatures temperatures are changed are changed to to the the [nominal
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| [nominal zero zero power power design design level],
| |
| level],
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| and and c.
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| : c. There is There is nono change change in in APSR APSR position.
| |
| position.
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| [STAGGERED TEST
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| [STAGGERED TEST BASIS BASIS A A STAGGERED STAGGERED TEST TEST BASIS BASIS shallshall consist consist of of the the testing testing of of one one of of the the systems, systems, subsystems, subsystems, channels, channels, oror other other designated designated components components during during thethe interval interval specified specified by by the the Surveillance Frequency, so that all systems, Surveillance Frequency, so that all systems, subsystems, subsystems, channels, channels, or or other other designated designated components components are are tested tested during during n Surveillance Frequency Surveillance Frequency intervals, intervals, wherewhere n isis the the total total number number of of systems, systems, subsystems, subsystems, channels, channels, or or other other designated designated components components in the associated in the function.]
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| associated function.]
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| THERMAL THERMAL POWER POWER THERMAL POWER THERMAL POWER shall shall be be the the total total reactor reactor core core heatheat transfer rate transfer rate toto the the reactor reactor coolant.
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| coolant.
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| BWOG STS BWOG STS 1.1-6 1.1-6 Rev. 3.1,12/01/05 Rev. 3.1,12/01/05
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| TSTF-425, Rev. 3 SDM SDM 3.1.1 3.1.1 3.1 REACTIVITY 3.1 REACTIVITY CONTROL CONTROL SYSTEMS SYSTEMS 3.1.1 3.1.1 SHUTDOWN MARGIN SHUTDOWN MARGIN (SDM)
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| (SDM)
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| L C 0 3.1.1 LCO 3.1.1 The SDM shall The 80M shall be be within within the the limits limits specified specified inin the the COLR.
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| COLR.
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| APPLICABILITY:
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| APPLICABILITY: MODES 3, MODES 3, 4, 4, and 5.
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| and 5.
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| ACTIONS CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. not within SDM not A. SDM within limits.
| |
| limits. A .l A.1 Initiate boration Initiate boration toto restore restore 15 minutes 15 minutes SDM to SDM within limits.
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| to within limits.
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| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS - - - -
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| SURVEILLANCE SURVEILLANCE I FREQUENCY SR 3.1.1.1 SR 3.1.1.1 Verify SOM Verify is within SDM is within the the limits limits specified specified in the in the {f4 hours ~--~
| |
| COLR.
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| COLR.
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| IV\,Ser+ ~
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| BWOG STS BWOG STS 3.1.1-1 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
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| | |
| TSTF-425, Rev. 3 Reactivity Balance Reactivity Balance 3.1.2 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.1.2.1 SR 3.1.2.1 NOTES.............................
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| -----------------------------NOTES-----------------------------
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| I.
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| : 1. The The predicted predicted reactivity reactivity values may values may be be adjusted adjusted (normalized) to (normalized) to correspond correspond to to the the measured measured core reactivity core reactivity priorprior toto exceeding exceeding a a fuel fuel burnup burnup of 60 of 60 effective effective full full power power days days (EFPD)
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| (EFPD) afterafter each fuel
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| - each fuel loading.
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| loading.
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| 2.
| |
| : 2. This Surveillance This Surveillance is is not not required required to to be be performed prior performed prior to to entry entry intointo MODE MODE 2. 2.
| |
| Verify measured Verify measured core core reactivity reactivity balance balance is is within within Prior to Prior entering to entering
| |
| + 1% Ak/k
| |
| +/- 1% ~k/k of of predicted predicted values.
| |
| values. MODE 11 after MODE after each fuel each fuel loading loading AND NOTE--------
| |
| --------NOTE--------
| |
| Only required Only required after 60 after EFPD 60 EFPD G1 EFPD 31 EFPD thereafter thereafter 7
| |
| ~--...
| |
| BWOG STS BWOG STS 3.1.2-2 Rev. 3.0, Rev. 03/31/04 3.0, 03/31/04
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| | |
| TSTF-425, Rev. 3 CONTROL ROD CONTROL ROD Group Group Alignment Limits Alignment Limits 3.1.4 3.1.4 ACTIONS (continued)
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| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME D. One D. One oror more more rods rods D.l.l 0.1.1 Verify SDM Verify SDM is is within within the the 1 hour 1 hour inoperable.
| |
| inoperable. limits specified limits specified in in the the COLR.
| |
| COLR.
| |
| OR OR D.1.2 0.1.2 Initiate boration Initiate boration to to restore restore Ihour 1 hour SDM to 80M to within within limit.
| |
| limit.
| |
| AND AND D.2 0.2 Be in Be in MODE MODE 3. 3. 6 hours 6 hours SURVEILLANCE - REQUIREMENTS SURVEILLANCE REQUIREMENTS - - - - .-
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY 3.1.4.1 SR 3.1.4.1 SR Verify individual Verify individual CONTROL CONTROL ROD ROD positions positions are are within [6.5J%
| |
| within [6.5]% of of their their group group average average height.height.
| |
| 3.1.4.2 SR 3.1.4.2 SR Verify CONTROL Verify CONTROL ROD ROD freedom freedom of of movement movement (trippability) by (trippabifity) by moving moving each each individual individual CONTROLCONTROL ROD that ROD that is is not not fully inserted r fully inserted ~ 3%3% inin anyany direction.
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| direction.
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| SR 3.1.4.3 SR 3.1.4.3 NOTE..............................
| |
| -----------------------------~-NOTE------------------------------
| |
| With rod With rod dropdrop times times determined determined with with lessless than than four four reactor coolant reactor coolant pumps pumps operating, operating, operation operation may may proceed provided proceed provided operation operation is is restricted restricted to to the the pump pump combination operating combination operating during during the the rod rod dropdrop time time determination.
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| determination.
| |
| ----------------------+------------+------------+--------------------
| |
| Verify Verify the the rodrod drop drop time time for for eacheach CONTROL CONTROL ROD, ROD, Prior to Prior to reactor reactor from the from the fully fully withdrawn withdrawn position, position, is is CO; I [ I ,661 seconds
| |
| [1.66] seconds criticality after criticality after from power from power interruption interruption at at thethe CONTROL CONTROL ROD ROD drive drive each removal each removal of of breakers to breakers 314 insertion to 3/4 insertion (25% (25% withdrawnwithdrawn position) position) the reactor the reactor vessel vessel with T with ,T
| |
| ,, avg 2 525°F.
| |
| ~ 525°F. head head BWOG STS BWOG STS 3.1.4-3 3.1.4-3 3.0, 03/31/04 Rev. 3.0.
| |
| Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Rod Insertion Safety Rod Safety Insertion Limits Limits 3.1.5 3.1.5 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| I CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME B.2 B.2 Be in Be in MODE MODE 3. 3. hours 6 hours 6
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS - - - - -
| |
| SURVEILLANCE SURVEILLANCE I I -
| |
| FREQUENCY FREQUENCY SR 3.1.5.1 Verify each Verify safety rod each safety is fully rod is fully withdrawn.
| |
| withdrawn. Ik IF-
| |
| ~ hours hours BWOG STS BWOG 3.1.5-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 APSR APSR Alignment Limits Alignment Limits 3.1.6 3.1.6 REACTIVITY CONTROL 3.1 REACTIVITY 3.1 CONTROL SYSTEMS SYSTEMS 3.1.6 3.1.6 AXIAL POWER SHAPING AXIAL POWER SHAPING ROD (APSR) Alignment ROD (APSR) Limits Alignment Limits LCO 3.1.6 L C 0 3.1.6 Each APSR Each shall be APSR shall OPERABLE and be OPERABLE and aligned aligned within 16.51% of within [6.5]% its group of its group average height.
| |
| average height.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 1 MODES Iand and 2.
| |
| 2.
| |
| ACTIONS ACTIONS - -- - - - _ I CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. One APSR A. One inoperable, APSR inoperable, A.l A.1 Petform SR Perform SR 3.2.3.1.
| |
| 3.2.3.1. 2 hours 2 hours not aligned not aligned within its within its limits, or limits, or both.
| |
| both. AND 2 hours 2 hours after after each each APSR movement APSR movement Required Action
| |
| : 0. Required B. and Action and B.l B.1 Be in Be in MODE MODE 3.3. 6 hours 6 hours associated Completion associated Completion Time notnot met.
| |
| met.
| |
| Time SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE / FREQUENCY FREQUENCY SR 3.1.6.1 SR 3.1.6.1 Verify position Verify position of each APSR of each APSR isis within within [6.5]% of the
| |
| [6.5]% of the E2hours E2 hours 'lI;."'~_~.
| |
| group average group average height.
| |
| height.
| |
| )
| |
| BWOG STS BWOGSTS 3.1.6-1 Rev. 3.0, Rev. 3.0, 03/31/04 03131104
| |
| | |
| TSTF-425, Rev. 3 Position Indicator Position Indicator Channels Channels 3.1.7 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY
| |
| =S~R~3_.1_.7~.=1 v=er~if=Y~th_e_a_b=s~o=,u~te_pO_S=it~io=n~i_nd_i_ca_t~or=C~h~a_n_ne=r~s=a_n_d_",,=U:=1_2_h_o_ur_S~d
| |
| ~
| |
| Verify the absolute position indicator channels and E2 hours the relative the relative position position indicator indicator channels channels agree agree within within
| |
| = __
| |
| the limit the limit specified specified in in the the COLR.
| |
| COLR.
| |
| (insu£D BWOG STS SWOG STS 3.1.7-4 Rev. 3.0, Rev. 03131104 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 PHYSICS TESTS PHYSICS TESTS Exceptions -
| |
| Exceptions - MODE MODE 11 3.1.8 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.1.8.1 SR 3.1.8.1 Verify THERMAL Verify THERMAL POWER POWER is::; is 585% RTP.
| |
| 85% RTP.
| |
| L--
| |
| SR 3.1.8.2 -------------------------------NOTE------------------------------
| |
| Only required to be met when THERMAL POWER is
| |
| > 20% RTP.
| |
| Perform SR Perform SR 3.2.5.1.
| |
| 3.2.5.1. ghoun (ihours 6nqert2 )
| |
| SR 3.1.8.3 Verify nuclear Verify nuclear overpower overpower trip trip setpoint is ::;
| |
| setpoint is I RTP 10% RTP 10% @hours higher than higher than the the THERMAL THERMAL POWER POWER at at which which thethe test is test is performed, performed, withwith aa maximum maximum setting setting of of RTP.
| |
| 90% RTP.
| |
| 90%
| |
| SR 3.1.8.4 Verify SDM Verify SDM is is within within the the limits limits specified specified in in the the COLR.
| |
| COLR.
| |
| BWOG STS BWOG STS Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 PHYSICS TESTS PHYSICS TESTS Exceptions -
| |
| Exceptions - MODE MODE 2 2 3.1.9 3.1.9 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME C. Nuclear C. Nuclear overpower overpower trip trip C.l C.1 Suspend PHYSICS Suspend PHYSICS TESTSTESTS 11 hour hour setpoint is setpoint is not not within within exceptions.
| |
| exceptions.
| |
| limit.
| |
| limit.
| |
| Nuclear instrumentation Nuclear instrumentation high startup high startup rate rate CONTROL ROD CONTROL ROD withdrawal inhibit withdrawal inhibit inoperable.
| |
| inoperable.
| |
| SURVEILLANCE REQUIREMENTS REQUIREMENTS -
| |
| /
| |
| SURVEILLANCE I
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.1.9.1 SR 3.1.9.1 Verify THERMAL Verify THERMAL POWERPOWER is:::;
| |
| is 5 5%
| |
| 5% RTP.
| |
| RTP.
| |
| SR 3.1.9.2 SR 3.1.9.2 Verify nuclear Verify nudear overpower overpower trip trip setpolnt setpoint is is :::; 25% RTP.
| |
| i 25% RTP. [hours Khours 8 SR 3.1.9.3 SR 3.1.9.3 Verify SDM is Verify SDM within the is within the limits limits specified specified in in the the ~. hours COLR.
| |
| COLR.
| |
| SWOG STS BWOG STS 3.1.9-2 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Regulating Rod Regulating Rod Insertion Insertion Limits Limits 3.2.1 3.2.1 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME C. Regulating C. Regulating rod rod groups groups C.l C.1 Initiate boration Initiate boration to to restore restore 15 minutes 15 minutes inserted in inserted in unacceptable unacceptable SDM to SDM to within within the the limit limit operational region.
| |
| operational region. specified in specified in the the COLR.
| |
| COLR.
| |
| AND C.2.1 C.2.1 Restore regulating Restore regulating rod rod 2 hours 2 hours groups to groups to within restricted within restricted operating region.
| |
| operating region.
| |
| OR C.2.2 C.2.2 Reduce THERMAL Reduce THERMAL 2 hours 2 hours POWER to POWER to I~ss less than than oror equal to equal the THERMAL to tRe THERMAL POWER allowed POWER allowed by by the the regulating rod regulating group rod group insertion limits.
| |
| insertion limits.
| |
| D. Required D. Required Action Action and and D.l 0.1 Be in Be in MODE MODE 3. 3. 6 hours 6 hours associated Completion associated Completion Time of Time Condition C of Condition C not not met.
| |
| met.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS - - -
| |
| SURVEILLANCE SURVEILLANCE I FREQUENCY FREQUENCY SR 3.2.1.1 Verify regulating rod groups are within the sequence and overlap limits as specified in the COLR.
| |
| SR 3.2.1.2 SR 3.2.1.2 Verify regulating Verify regulating rod as specified as specified in rod groups in the groups meet the COLR.
| |
| COLR.
| |
| meet thethe insertion insertion limits limits fu hours ~
| |
| CXnsert1)
| |
| SR 3.2.1.3 SR 3.2.1.3 Verify SDM is Verify 80M is within within the the limit limit specified specified in in the the COLR.
| |
| COLR. Within 4 Within 4 hours hours prior to prior to achieving achieving criticality criticality BWOG STS BWOG STS 3.2.1-2 3.2.1-2 Rev. 3.0, Rev. 03/31/04 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 APSR Insertion Limits APSR Insertion Limits 3.2.2 3.2.2 3.2 POWER 3.2 POWER DISTRIBUTION DISTRIBUTION LIMITS LIMITS 3.2.2 3.2.2 AXIAL POWER SHAPING AXIAL POWER SHAPING ROD ROD (APSR)
| |
| (APSR) InsertionInsertion Limits Limits LCO 3.2.2 L C 0 3.2.2 APSRs APSRs shall be positioned shall be positioned within within the the limits limits specified specified inin the the COLR.
| |
| COLR.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 11 and MODES 2.
| |
| and 2.
| |
| ACTIONS ACTIONS - -
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A.
| |
| A. APSRs within limits.
| |
| APSRs not within limits. A.11 A. --
| |
| ------ ------NOTE
| |
| --------------N --------------
| |
| 0 TE--------------
| |
| Only required Only required when when THERMAL POWER THERMAL POWER is is 20% RTP.
| |
| > 20%
| |
| > RTP.
| |
| -------------~ ..... _--------------------~
| |
| Perform SR Perform SR 3.2.5.1.3.2.5.1. Once per Once per 22 hours hours AND A.2 A.2 Restore APSRs Restore APSRs to to within within 24 hours 24 hours limits.
| |
| limits.
| |
| B. Required Action B. Required and Action and B.l B.1 Be in Be in MODE MODE 3. 3. hours 66 hours associated Completion associated Completion Time not Time not met.
| |
| met.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.2.2.1 Verify APSRs Verify APSRs areare within within acceptable acceptable limits limits specified specified @hours ~_~
| |
| in the in the COLR.
| |
| COLR.
| |
| BWOG STS BWOG STS 3.2.2-1 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 AXlAL AXIAL POWER POWER IMBALANCE IMBALANCE Operating Operating Limits Limits 3.2.3 3.2.3 3.2 3.2 POWER POWER DISTRIBUTION DISTRIBUTION LIMITSLIMITS 3.2.3 3.2.3 AXIAL AXIAL POWER POWER IMBALANCE IMBALANCE Operating Operating Limits Limits C 0 3.2.3 LLCO 3.2.3 AXIAL AXIAL POWER POWER IMBALANCE IMBALANCE shall shall be be maintained maintained within within the the limits limits specified specified in in the the COLR.
| |
| COLR.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODE MODE 1 1 with with THERMAL THERMAL POWER POWER> > 40%
| |
| 40% RTP.
| |
| RTP.
| |
| ACTIONS ACTIONS -
| |
| CONDITION CONDITION REQUIRED REQUIRED ACTIONACTION COMPLETION COMPLETION TIME TIME A.
| |
| A. AXlAL POWER AXIAL POWER A.l A.1 Perform SR 3.2.5.1.
| |
| Perform SR 3.2.5.1. Once Once per per 2 2 hours hours IMBALANCE not IMBALANCE not within within limits.
| |
| limits. AND A.2 A.2 Reduce AXlAL Reduce AXIAL POWER POWER 24 hours 24 hours IMBALANCE within IMBALANCE within limits.
| |
| limits.
| |
| B. Required B. Required Action Action and and B.l B.1 Reduce THERMAL Reduce THERMAL 22 hours hours associated Completion associated Completion POWER to POWER to ::0:;
| |
| 5 40% 40% RTP.
| |
| RTP.
| |
| Time not Time met.
| |
| not met.
| |
| SURVEILLANCE SURVEILLANCE -REQUIREMENTS REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY 3.2.3.1 SR 3.2.3.1 SR Verify AXIAL Verify AXIAL POWER POWER IMBALANCE IMBALANCE is is within within limits limits @hours "' __
| |
| as specified as specified in the COLR.
| |
| in the COLR.
| |
| BWOG STS BWOG STS 3.2.3~1 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 QPT QPT 3.2.4 3.2.4 ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME E. Required E. Required Action and Action and E l E.1 Reduce THERMAL Reduce THERMAL 2 hours associated Completion associated Completion POWER to:S; POWER to I [20]% RTP.
| |
| [20]% RTP.
| |
| Time for Time for Condition Condition C C or D or D not met.
| |
| not met.
| |
| F. QPT F. QPT greater greater than than the the F.1 F.1 Reduce THERMAL Reduce THERMAL 2 hours maximum limit.
| |
| maximum limit. POWER to POWER to :s; [20]% RTP.
| |
| I [20]% RTP.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.2.4.1 SR 3.2.4.1 Verify OPT Verify is within QPT is within limits limits as as specified specified inin the the COLR.
| |
| COLR.
| |
| When OPT When has QPT has been restored been restored toto less than less than or or equal equal to the to the steady steady state state limit, 11 hour limit, hour for for 12 12 consecutive consecutive hours, or hours, or until until verified verified acceptable at acceptable at 2 95% 95% RTP RTP BWOG STS BWOG STS 3.2.4-3 Rev. 3.0, Rev. 03/31/04 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RPS Instrumentation RPS Instrumentation 3.3.1 3.3.1 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME E. As E. required by As required by Required Required E.l E.1 Open all Open all CRD CRD trip trip breakers.
| |
| breakers. 6 hours 6 hours Action C.1 Action C.1 and and referenced in referenced in Table 3.3.1-1.
| |
| Table 3.3.1-1.
| |
| F. As required by As required by Required Required F.1 F.1 Reduce THERMAL Reduce THERMAL 6 hours 6 hours Action Action C.1C.1 and and POWER <
| |
| POWER 1451% RTP.
| |
| < [45]% RTP.
| |
| referenced in referenced in Table 3.3.1-1.
| |
| Table 3.3.1-1.
| |
| G. As G. required by As required by Required Required G.1 G.1 Reduce THERMAL Reduce THERMAL 66 hours hours Action C.1 Action C.1 and and POWER <
| |
| POWER 1151% RTP.
| |
| < [15]% RTP.
| |
| referenced in referenced in Table 3.3.1-1.
| |
| 3.3.1-1.
| |
| Table SURVEILLANCE REQUIREMENTS
| |
| ----.-------------------------------------------------------NOTE--------------------------------------------.--------------
| |
| Refer to Table 3.3.1-1 to determine which SRs apply to each RPS Function.
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY 3.3.1.1 SR 3.3.1.1 SR Perform CHANNEL Perform CHANNEL CHECK. CHECK. @.hours ~,
| |
| 3.3.1.2 SR 3.3.1.2 SR --------------------------- NOTES.............................
| |
| ---------------------------NOTES-----------------------------
| |
| I. Adjust
| |
| : 1. power range Adjust power range channel channel output output ifif the the absolute difference absolute difference isis > [2]% RTP.
| |
| > [2]% RTP.
| |
| 2.
| |
| : 2. Not required Not required to to be performed until be performed until [24] hours
| |
| [24] hours after THERMAL after THERMAL POWER is r 15%
| |
| POWER is::::: RTP.
| |
| 15% RTP.
| |
| Compare result Compare result ofof calorimetric calorimetric heat heat balance balance calculation to calculation to power power range range channel channel output.
| |
| output.
| |
| BWOG STS SWOG STS 3.3.1-2 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RPS Instrumentation RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.3.1.3 SR 3.3.1.3 .............................. NOTES.............................
| |
| ------------------------------NOTES-----------------------------
| |
| I . Adjust
| |
| : 1. Adjust the the powerpower range range channel channel imbalance imbalance output if output if the the absolute absolute value value of of the the imbalance imbalance error is error is ;::.:
| |
| 2 [2]% 121% RTP.
| |
| RTP.
| |
| 2.
| |
| : 2. Not required Not required to to be be performed performed until until [24]
| |
| [24] hours hours after THERMAL after THERMAL POWER POWER is;::': 15% RTP.
| |
| is 2 15% RTP.
| |
| Compare results Compare results of of out out of of core core measured measured AXIAL AXIAL 31da~
| |
| POWER IMBALANCE POWER IMBALANCE (APl (APIo) to incore o) to incore measured measured AXIAL POWER AXIAL POWER IMBALANCE IMBALANCE (API (API,)1) asas follows:
| |
| follows:
| |
| ~
| |
| (RTP/TP)(APlo (RTPITP)(APl o -- API,)
| |
| APld = imbalance error.
| |
| = imbalance error.
| |
| F 3.3.1.4 S R 3.3.1.4 SR Perform CHANNEL Perform CHANNEL FUNCTIONAL FUNCTIONAL TEST. TEST. [45] days 1[45] days on on a a
| |
| STAGGERED
| |
| '-STAGGERED TEST BASIS TESTBAS/S \
| |
| 3.3.1.5 S R 3.3.1.5 SR -----*+------------------**---- NOTE..............................
| |
| -------------------------------NOTE------------------------------
| |
| Neutron detectors Neutron detectors are are excluded excluded from from CHANNEL CHANNEL CALIBRATION.
| |
| CALIBRATION.
| |
| - months f5 W8]
| |
| e Perform CHANNEL Perform CHANNEL CALIBRATION.CALIBRATION. [I 81 months SR 3.3.1.6 SR 3.3.1.6 ............................... NOTE..............................
| |
| -------------------------------NOTE------------------------------
| |
| Neutron detectors Neutron detectors are are excluded excluded from from RPSRPS RESPONSE TIME RESPONSE TIME testing.
| |
| testing.
| |
| e Verify that Verify that RPSRPS RESPONSERESPONSE TIME TIME is is within within limits.
| |
| limits. months on
| |
| [18] months
| |
| ([18] on a a
| |
| ~TAGGERED STAGGERED TESTBASIS TEST BASIS %
| |
| BWOG STS BWOG STS 3.3.1-3 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3
| |
| - RTM RPS - RTM RPS 3.3.3 3.3.3 ACTIONS (continued)
| |
| I I ACTIONS (continued)
| |
| I CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME C. Two C. Two oror more more RTMs RTMs C.l C.1 Open all Open CRD trip all CRD trip breakers.
| |
| breakers. 6 hours 6 hours inoperable in inoperable in MODE MODE 4 or 5.
| |
| or 5. -
| |
| OR OR OR C.2 C.2 Remove power Remove power from from all all hours 66 hours CRD trip CRD trip breakers.
| |
| breakers.
| |
| Required Action Required and Action and associated Completion associated Completion Time not Time not met met in MODE 44 in MODE or 5.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.1 SR 3.3.3.1 Perform CHANNEL Perform CHANNEL FUNCTIONAL FUNCTIONAL TEST.
| |
| TEST. (i23] days
| |
| ((23] days on on aa STAGGERED STAGGERED TEST BASIS TEST BASIS 5 SWOG STS BWOG STS 3.3.3-2 Rev. 3.0, Rev. 03/31/04 3.0. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 CRD Trip CRD Trip Devices Devices 3.3.4 3.3.4 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME C. One C. One oror more more ETAETA relays relays I C.1 Transfer affected Transfer affected 1 hour 1 hour inoperable.
| |
| inoperable. CONTROL ROD CONTROL ROD group group toto power supply power supply with with OPERABLE ETA OPERABLE ETA relays.
| |
| relays.
| |
| OR C.2 C.2 Trip corresponding AC Trip corresponding AC Ihour 1 hour CRD trip CRD trip breaker.
| |
| breaker.
| |
| D. Required D. Required Action and Action and D.1 0.1 Be in Be in MODE MODE 3. 3. 6 hours 6 hours associated Completion associated Completion Time not Time not met met in in AND MODE 1,2, MODE I , 2, or 3.
| |
| or 3.
| |
| D.2.1 D.2.1 Open all Open all CRD CRD trip trip breakers.
| |
| breakers. 6 hours 6 hours OR OR D.2.2 D.2.2 Remove power Remove power from from all all 6 hours 6 hours CRD trip CRD trip breakers.
| |
| breakers.
| |
| E. Required E. Required Action and Action and E.l E.1 Open all Open all CRD CRD trip trip breakers.
| |
| breakers. 6 hours 6 hours associated Completion associated Completion Time not Time not met met in in MODE MODE 4 4 OR or 5.
| |
| or 5.
| |
| E.2 E.2 Remove power Remove power from from all all 6 hours 6 hours CRD trip CRD trip breakers.
| |
| breakers.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS - - -
| |
| I I-SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.3.4.1 SR 3.3.4.1 Perform CHANNEL Perform FUNCTIONAL TEST.
| |
| CHANNEL FUNCTIONAL TEST. 1[;3] days on a TAGGERED LSTAGGERED TESTBASIS TEST BASIS 5
| |
| ----_D .....
| |
| BWOG STS BWOG STS 3.3.4-2 3.0, 03/31/04 Rev. 3.0, Rev. 03131104
| |
| | |
| TSTF-425, Rev. 3 ESFAS Instrumentation ESFAS Instrumentation 3.3.5 3.3.5 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME B.2.1 --------------NOTE--------------
| |
| --------------NOTE--------------
| |
| Only required Only required for for RCS RCS Pressure -- Low Pressure Low setpoint.
| |
| setpoint.
| |
| Reduce RCS Reduce RCS pressure pressure 36 hours 36 hours
| |
| [1800] psig.
| |
| < [1800]
| |
| < psig.
| |
| AND AND B.2.2 B.2.2 --------------NOTE--------------
| |
| --------------NOTE--------------
| |
| Only required Only required for for ReS RCS Pressure -- Low Pressure Low Low Low setpoint.
| |
| setpoint.
| |
| Reduce RCS Reduce RCS pressure pressure 36 hours 36 hours
| |
| < [goo] psig.
| |
| < [900] psig.
| |
| AND B.2 .3 B.2.3 --------------NOTE
| |
| --------------N0 --------------
| |
| TE--.-----------
| |
| Only required Only required for for Reactor Reactor Building Pressure Building Pressure High High setpoint and setpoint and High High High High setpoint.
| |
| setpoint.
| |
| -------------+-----------------------
| |
| Be in Be in MODE MODE 5. 5. 36 hours 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.3.5.1 Perform CHANNEL Perform CHANNEL CHECK.
| |
| CHECK. @hours BWOG STS SWOG STS 3.3.5-2 3.0, 03/31/04 Rev. 3.0, Rev. 03131104
| |
| | |
| TSTF-425, Rev. 3 ESFAS Instrumentation ESFAS Instrumentation 3.3.5 3.3.5 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.3.5.2 SR ............................... NOTE..............................
| |
| -------------------------------NOTE------------------------------
| |
| When an When an ESFAS ESFAS channelchannel is is placed placed in in an an inoperable inoperable status solely status solely forfor performance performance of of this this Surveillance, Surveillance, entry into entry into associated associated Conditions Conditions and and Required Required Actions Actions may may be be delayed delayed for for upup toto 88 hours, hours, provided provided the remaining the remaining two two channels channels of of ESFAS ESFAS instrumentation are instrumentation are OPERABLE OPERABLE or or tripped.
| |
| tripped.
| |
| Perform CHANNEL Perform CHANNEL FUNCTIONALFUNCTIONAL TEST. TEST. §31 days L
| |
| days SR 3.3.5.3 SR 3.3.5.3 Perform CHANNEL Perform CHANNEL CALIBRATION.
| |
| CALIBRATION.
| |
| SR 3.3.5.4 SR 3.3.5.4 Verify ESFAS Verify ESFAS RESPONSE RESPONSE TIME TIME within within limits.
| |
| limits.
| |
| 1[18] months on
| |
| [18]months on aa STAGGERED a-sTAGGERED
| |
| ~~~~_ _~=~~ __a._T_E_ST_BA....lS~~
| |
| BWOG STS SWOG STS 3.3.5-3 Rev. 3.0, Rev. 03131104 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 ESFAS Manual ESFAS Initiation Manual Initiation 3.3.6 3.3.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.3.6.1 Perform CHANNEL Perform CHANNEL FUNCTIONAL FUNCTIONAL TEST.
| |
| TEST lk]
| |
| §] rnonthsq months BWOG STS SWOG STS 3.3.6-2 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 ESFAS Automatic ESFAS Automatic Actuation Logic Actuation Logic 3.3.7 3.3.7 3.3 INSTRUMENTATION 3.3 INSTRUMENTATION 3.3.7 3.3.7 Engineered Safety Engineered Safety Feature Feature Actuation System (ESFAS)
| |
| Actuation System (ESFAS) Automatic Automatic Actuation Logic Actuation Logic LC0 3.3.7 LCO 3.3.7 All the ESFAS All the ESFAS automatic automatic actuation actuation logic logic matrices matrices shall shall be be OPERABLE.
| |
| OPERABLE.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 1, MODES 2, and 1, 2, 3, and 3, MODE 44 when MODE when associated associated engineered engineered safeguardsafeguard equipment equipment is is required required to to be OPERABLE.
| |
| be OPERABLE.
| |
| ACTIONS ACTIONS NOTE--------------------------------------------------+----**--
| |
| ------------------------------------------------------------NOTE-----------------------------------------------------------
| |
| Separate Condition Separate Condition entry entry is is allowed allowed for for each each automatic automatic actuation actuation logic logic matrix.
| |
| matrix.
| |
| CONDITION CONDITION I REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A.
| |
| A. One One or or more more automatic automatic A.1 A.1 Place associated Place associated hour 1 hour 1
| |
| actuation logic actuation logic matrices matrices component(s) in component(s) in inoperable.
| |
| inoperable. engineered safeguard engineered safeguard configuration.
| |
| configuration.
| |
| OR A.2 A.2 Declare the Declare the associated associated Ihour 1 hour component(s) inoperable.
| |
| component(s) inoperable.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY 3.3.7.1 S R 3.3.7.1 SR Perform automatic Perform automatic actuation FUNCTIONAL TEST.
| |
| FUNCTIONAL TEST.
| |
| actuation logic logic CHANNEL CHANNEL Cf31 31 days days on TAGGERED
| |
| 'iTAGGERED TEST BASIS TEST on aa BASIS BWOG STS BWOG STS 3.3.7-1 3.3.7-1 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EDG LOPS EDG LOPS 3.3.8 3.3.8 REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE -
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.3.8.1 SR 3.3.8.1 Perform CHANNEL Perform CHANNEL CHECK. CHECK. Ejhours ~
| |
| SR 3.3.8.2 SR 3.3.8.2 ------------------------------NOTE
| |
| -------------------------------NOTE------------------------------
| |
| ---------d-+-m----------------
| |
| When EDG When EDG LOPSLOPS instrumentation instrumentation is is placed placed in in an an inoperable status solely for performance of this inoperable status solely for performance of this' '
| |
| Surveillance, entry Surveillance, entry into into associated associated Conditions Conditions and and Required Actions Required Actions may may be be delayed delayed as as follows: follows: (a)(a) up up to 44 hours to hours forfor the the degraded degraded voltage voltage Function, Function, and and (b) up (b) up to to 44 hours hours forfor the the loss loss of of voltage voltage Function, Function, provided the provided the two two channels channels monitoring monitoring the the Function Function for the for the bus bus are are OPERABLE OPERABLE or or tripped.
| |
| tripped.
| |
| (I. VlSe."f t -
| |
| Perform CHANNEL Perform CHANNEL FUNCTIONALFUNCTIONALTEST. TEST. ~ days days <f SR 3.3.8.3 SR 3.3.8.3 Perform CHANNEL Perform CHANNEL CALIBRATION CALIBRATION with setpoint with setpoint (r8 months 7, Allowable Value Allowable Value as as follows:
| |
| follows:
| |
| a.
| |
| : a. Degraded voltage r (( JJ and:::;
| |
| Degraded voltage;::: and I (( )) V V with with aa time time delay of delay of (( )) seconds seconds +/-k (( J] seconds seconds at V at (( )) V and and b.
| |
| : b. Loss of Loss of voltage;:::
| |
| voltage 2 (( J] and:::;
| |
| and I (( )) V V with with aa time time delay of delay of (( )) seconds seconds +/-k (( J] secondsseconds at at (( )) V.
| |
| V.
| |
| BWOG STS BWOG STS 3.3.8-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Source Range Source Range Neutron Neutron Flux Flux 3.3.9 3.3.9 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME B.3 B.3 CONTROL ROD Open CONTROL Open ROD 11 hour hour drive trip drive trip breakers.
| |
| breakers.
| |
| AND AND B.4 B.4 Verify SDM Verify SDM is within the is within the 11 hour hour limits specified limits specified in in the the COLR.
| |
| COLR. AND Once per Once 12 hours per 12 hours thereafter thereafter C. One C. One or more source or more source C.1 C.1 Initiate action Initiate action to to restore restore hour 11 hour range neutron range neutron flux flux affected channel(s) affected channel(s) to to channel(s) inoperable channel(s) inoperable OPERABLE status.
| |
| OPERABLE status.
| |
| with neutron with flux neutron flux
| |
| >> 1E-10 IE-I 0 amp amp on on the the intermediate range intermediate range neutron flux flux channels.
| |
| channels.
| |
| neutron P
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.3.9.1 SR 3.3.9.1 Perform CHANNEL Perform CHANNEL CHECK. CHECK. E2' hours t)
| |
| SR 3.3.9.2 SR 3.3.9.2 ............................... NOTE..............................
| |
| -------------------------------NOTE------------------------------
| |
| Neutron detectors Neutron detectors are excluded from are excluded from CHANNEL CHANNEL CALIBRATION.
| |
| CALIBRATION.
| |
| I Perform CHANNEL Perform CHANNEL CALIBRATION.
| |
| CALIBRATION. W 1 ~8]8months 1
| |
| months f)
| |
| BWOG STS SWOG STS 3.3.9-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 lntermediate Range Intermediate Range Neutron Neutron Flux Flux 3.3.10 3.3.10 3.3 INSTRUMENTATION 3.3 INSTRUMENTATION 3.3.10 3.3.10 lntermediate Range Intermediate Range Neutron Neutron FluxFlux L C 0 3.3.10 LCO 3.3.10 Two intermediate Two intermediate range range neutronneutron flux flux channels channels shall shall be be OPERABLE.
| |
| OPERABLE.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODE 2, MODE 2, MODES 3, MODES 3 , 4, 4 , and 5 with and 5 with any any CONTROL CONTROL ROD ROD drive (CRD) trip drive (CRD) trip breaker breaker in in the closed the closed position position and and the the CRD CRD System System capable capable ofof rod rod withdrawal.
| |
| withdrawal.
| |
| ACTIONS ACTIONS CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME One channel A. One channel inoperable.
| |
| inoperable. A.1 A.1 Reduce neutron Reduce neutron flux flux to to 2 hours 2 hours 1E-10 amp.
| |
| ~ 1E-10 5 amp.
| |
| B. Two B. Two channels channels B.1 B.1 --------------NOTE
| |
| -**_~~--------N --------------
| |
| 0 TE--------------
| |
| inoperable.
| |
| inoperable. Plant temperature Plant temperature changes changes are allowed are allowed provided provided the the temperature change temperature change is is accounted for accounted for in the in the calculated SDM.
| |
| calculated SDM.
| |
| ----------------+-+--*---------------
| |
| Suspend operations Suspend operations Immediately Immediately involving positive involving positive reactivityreactivity changes.
| |
| changes.
| |
| AND B.2 B.2 Open CRD Open CRD trip trip breakers.
| |
| breakers. 1 hour 1 hour SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE I FREQUENCY FREQUENCY SR 3.3.10.1 SR 3.3.10.1 Perform CHANNEL Perform CHANNEL CHECK. CHECK. I hours 5 BWOG STS BWOG STS 3.3.10-1 3.3.10-1 3.0, 03/31/04 Rev. 3.0, Rev. 03131104
| |
| | |
| TSTF-425, Rev. 3 Intermediate Range Intermediate Range Neutron Neutron Flux Flux 3.3.1 0 3.3.10 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.3.10.2 SR 3.3.10.2 ----------------------------"--NOTE..............................
| |
| -------------------------------NOTE------------------------------
| |
| Neutron detectors Neutron detectors areare excluded excluded from from CHANNEL CHANNEL CALIBRATION.
| |
| CALIBRATION.
| |
| Perform CHANNEL Perform CHANNEL CALIBRATION.
| |
| CALIBRATION. 1 ~l k8 months
| |
| ]months FT BWOG STS BWOG STS 3.3.10-2 Rev. 3.0, Rev. 3.0. 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EFlC System EFIC System Instrumentation Instrumentation 3.3.11 3.3.11 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TlME Three or F. Three or more more channels channels F.l F.1 Reduce once Reduce once through through 12 hours 12 hours inoperable for inoperable for steam generator steam generator pressure pressure Functions 1.c, Functions 2, 3, I .c, 2, or 4.
| |
| 3, or 4. to <
| |
| to 750 psig.
| |
| < 750 psig.
| |
| Required Action Required Action andand associated Completion associated Completion Time not Time not met met for for Functions 1.c, Functions 2, 3, 1.c, 2, 3, or or 4.
| |
| SURVEILLANCE REQUIREMENTS
| |
| **----------------------------------------------------------NOTE----.------------------------------------------------------
| |
| Refer to Refer to Table Table 3.3.11-1 3.3.11-1 to to determine determine which which SRsSRs shall shall be be performed performed forfor each each EFIC EFlC Function.
| |
| Function.
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.3.11.1 SR 3.3.11.1 Perform CHANNEL Perform CHANNEL CHECK. CHECK. Ehours~
| |
| S R 3.3.11.2 SR 3.3.11.2 Perform CHANNEL Perform CHANNEL FUNCTIONAL FUNCTIONAL TEST. TEST. daysdays SR 3.3.11.3 SR 3.3.11.3 Perform CHANNEL Perform CHANNEL CALIBRATION.
| |
| CALIBRATION.
| |
| 3.3.11.4 SR 3.3.11.4 Verify EFIC Verify EFlC RESPONSE RESPONSE TIME TIME is is within within limits.
| |
| limits. {[18] months on a "STAGGERED TEST BASIS BWOG STS BWOG STS 3.3.11-3 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EFlC Manual EFIC Manual Initiation Initiation 3.3.12 3.3.12 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME C. Required Action C. Required and Action and C.1 C.1 Be in Be in MODE 3.
| |
| MODE 3. 6 hours 6 hours associated Completion associated Completion Time not Time met.
| |
| not met. AND AND C.2 C.2 Be in MODE Be in MODE 4.
| |
| : 4. hours 12 hours 12 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.3.12.1 SR 3.3.12.1 Perform CHANNEL Perform CHANNEL FUNCTIONAL TEST.
| |
| FUNCTIONAL TEST.
| |
| SWOG STS BWOG STS 3.3.12-2 Rev. 3.0, Rev. 03131104 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EFlC EFIC Logic Logic 3.3.13 3.3.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SSR 3.3.13.1 R 3.3.13.1 Perform CHANNEL Perform FUNCTIONAL TEST.
| |
| CHANNEL FUNCTIONAL TEST. §dayS BWOGSTS BWOG STS 3.3.13-2 Rev. 3.0, Rev. 3.0,03/31/04 03l31104
| |
| | |
| TSTF-425, Rev. 3 EFIC-EFW -
| |
| EFIC-EFW - Vector Vector Valve Valve Logic Logic 3.3.14 3.3.14 INSTRUMENTATION 3.3 INSTRUMENTATION 3.3 3.3.14 3.3.14 Emergency Feedwater Emergency Feedwater Initiation Initiation and and Control (EFIC) -- Emergency Control (EFIC) Emergency Feedwater Feedwater (EFW)
| |
| (EFW)
| |
| - Vector Valve
| |
| - Vector Valve Logic Logic L C 0 3.3.14 LCO 3.3.14 Four channels Four channels ofof the valve logic vector valve the vector shall be logic shall be OPERABLE.
| |
| OPERABLE.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 1, MODES 1, 2, and 3.
| |
| 2, and 3.
| |
| ACTIONS ACTIONS CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. One A. One vector vector valve valve logic logic A.l A.1 Restore channel Restore channel toto 72 hours 72 hours channel inoperable.
| |
| channel inoperable. OPERABLE status.
| |
| OPERABLE status.
| |
| B. Required Action B. Required and Action and B.1 B.1 Be in Be in MODE MODE 3.3. hours 6 hours associated Completion Completion associated Time not Time not met.
| |
| met. AND AND 1 B.2 8.2 in MODE Be in Be MODE 4.4. hours 12 hours 12 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.3.14.1 SR 3.3.14.1 Perform a Perform CHANNEL FUNCTIONAL a CHANNEL FUNCTIONAL TEST.TEST IF days Edays 9
| |
| BWOG STS BWOG STS 3.3.14-1 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RB Purge RB Isolation-- High Purge Isolation High Radiation Radiation 3.3.15 SURVEILLANCEREQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.3.15.1 SR 3.3.15.1 PerformCHANNEL Perform CHECK.
| |
| CHANNEL CHECK.
| |
| SR 3.3.15.2 SR 3.3.15.2 Perform CHANNEL Perform CHANNEL FUNCTIONAL FUNCTIONALTEST.
| |
| TEST SR 3.3.15.3 SR 3.3.15.3 Perform CHANNEL Perform CHANNEL CALIBRATION CALIBRATION with with setpoint setpoint ~ 8] months ~..1 ,
| |
| Allowable Value Allowable Value 52 [25]
| |
| 1251mR/hr.
| |
| mR/hr.
| |
| (LnCY'>r'fJ.)
| |
| BWOG STS SWOG STS 3.3.15-2 03/31/04 3.0, 03/31/04 Rev. 3.0, Rev.
| |
| | |
| TSTF-425, Rev. 3 Control Room Isolation - High Radiation 3.3.16 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C.2 Suspend movement of Immediately
| |
| [recently] irradiated fuel assemblies.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.16.1 Perform CHANNEL CHECK. § hours SR 3.3.16.2 TE--------------------------
| |
| ------------------------------N0 TE---------------------------
| |
| When the Control Room Isolation - High Radiation instrumentation is placed in an inoperable status solely for performance of this Surveillance, entry into associated Conditions and Required Actions may be delayed for up to 3 hours.
| |
| Perform CHANNEL FUNCTIONAL TEST. @2days
| |
| @2dayS SR 3.3.16.3 Perform CHANNEL CALIBRATION with setpoint @8] months Allowable Value ~ [25] mR/hr.
| |
| BWOG STS 3.3.16-2 Rev. 3.0,,03/31/04
| |
| | |
| TSTF-425, Rev. 3 PAM Instrumentation PAM Instrumentation 3.3.17 3.3.17
| |
| -r ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME E. As E. As required required by by Required Required E.l E.1 Be in Be in MODE MODE 3. 3. 6 hours 6 hours Action D.1 Action D.1 and and referenced in referenced in AND AND Table 3.3.17-1.
| |
| Table 3.3.17-1.
| |
| E.2 E.2 Be in Be MODE 4.
| |
| in MODE 4. 12 hours 12 hours F. As F. required by As required by Required Required F.l F.1 Initiate action Initiate action in in accordance accordance Immediately Immediately Action Action D.1D.l and and with Specification with 5.6.5.
| |
| Specification 5.6.5.
| |
| referenced in referenced in Table 3.3.17-1.
| |
| Table 3.3.17-1.
| |
| SURVEILLANCE REQUIREMENTS
| |
| --------.----------.----------------------------------------NOT E-----------------------------------------------------------
| |
| These SRs apply to each PAM instrumentation Function in Table 3.3.17-1.
| |
| SURVEILLANCE SURVEILLANCE I FREQUENCY SR 3.3.17.1 SR 3.3.17.1 Perform CHANNEL Perform CHANNEL CHECK CHECK for for each each required required instrumentation channel instrumentation channel that that is is normally normally energized.
| |
| energized.
| |
| SR 3.3.17.2 -------------------------------NOTE------------------------------
| |
| Neutron detectors are excluded from CHANNEL CALIBRATION.
| |
| Perform CHANNEL Perform CHANNEL CALIBRATION.
| |
| CALIBRATION. /&Dl months-BWOG STS BWOG STS 3.3.17-2 Rev. 3.1, 12/01/05 Rev. 3.1, 12/01/05
| |
| | |
| TSTF-425, Rev. 3 Remote Shutdown Remote Shutdown System System 3.3.18 3.3.18 3.3 INSTRUMENTATION 3.3 INSTRUMENTATION 3.3.18 3.3.18 Remote Shutdown Remote Shutdown System System L C 0 3.3.18 LCO 3.3.18 Remote Shutdown The Remote The Shutdown System System Functions Functions shall shall be be OPERABLE.
| |
| OPERABLE.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 1, MODES 2, and 1, 2, and 3.3.
| |
| ACTIONS
| |
| ---.------------------------------------------.-.----------NOTE----------------------------------------------------------
| |
| Separate Condition entry is allowed for each Function.
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. One or A. One or more more required required A.1 A.1 required Function Restore required Restore Function 30 days 30 days Functions inoperable.
| |
| Functions inoperable. to OPERABLE to OPERABLE status. status.
| |
| B. Required B. Required Action Action andand B.l B.1 Be in Be in MODE MODE 3. 3. 6 hours 6 hours associated Completion associated Completion Time not Time not met.
| |
| met. AND 1 8.2 B.2 in MODE Be in Be MODE 4. 4. 1 12 hours 12 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY E. G'~I:-n"';'-2:e-(I-t-D SR 3.3.18.1 SR 3.3.18.1 (( Perform Perform CHANNEL CHANNEL CHECK CHECK for for each each required required days$)' J days instrumentation channel instrumentation channel that that is normally energized.
| |
| is normally energized.
| |
| (?%w SR 3.3.18.2 SR 3.3.18.2 Verify each Verify switch is switch each required required control is capable capable of control circuit of performing circuit and performing the and transfer transfer the intended intended 5 1 ilia} month ' )
| |
| month function.
| |
| function.
| |
| (IrlserEjj BWOG STS BWOG STS 3.3.18-1 Rev. 3.0, Rev. 03/31/04 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Remote Shutdown Remote Shutdown System System 3.3.18 3.3.18 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.3.18.3 -----------------~-------------NOTE---------------------~--------
| |
| Neutron detectors are excluded from CHANNEL CALIBRATION.
| |
| Perform CHANNEL CALIBRATION for each 08]
| |
| r"
| |
| [I81 months months required instrumentation channel.
| |
| ' I BWOG STS BWOG STS 3.3.18-2 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Pressure, RCS Pressure, Temperature, Temperature, and and Flow Flow DNB DNB Limits Limits 3.4.1 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.1.1 ------------------------------N0
| |
| +---*------------------------- NOTE ..............................
| |
| TE------------------------------
| |
| With three With three RCPsRCPs operating, operating, the the limits limits are are applied applied to to the loop the loop withwith twotwo RCPsRCPs in in operation.
| |
| operation.
| |
| Verify RCS Verify RCS loop loop pressure pressure 2:: [2061.6] psig 2 [2061.6] psig with with four RCPs four RCPs operating operating or or 2:: [2057.2] psig 2 [2057.2] psig with with three RCPs three RCPs operating.
| |
| operating.
| |
| SR 3.4.1.2 ------------------------------NOTE-----------------------------
| |
| With three With three RCPsRCPs operating, operating, the the limits limits are are applied applied to to the loop the loop withwith twotwo RCPsRCPs in in operation.
| |
| operation.
| |
| Verify RCS Verify RCS hot hot legleg temperature temperature :2-: :; [604.6rF.
| |
| [604.6I0F.
| |
| -12 hours d
| |
| SR 3.4.1.3 Verify RCS Verify RCS total RCPs operating RCPs total flow operating or flow 2::
| |
| or 2::
| |
| [139.7 E6]
| |
| 2 [139.7
| |
| [104.4 E6]
| |
| 2 [104.4 E6] Ib/hr E6JIb/hr lblhr with lblhr with with four with three four three
| |
| @ hours"J fi RCPS operating.
| |
| RCPS operating.
| |
| lIY\5e r-ti)
| |
| SR 3.4.1.4 ------------------------------NOTE------------------------------
| |
| Only required Only required to to bebe performed performed when stable thermal when stable thermal conditions are conditions are established established in in the the higher higher power power rangerange of MODE of MODE 1. 1.
| |
| Verify RCS Verify RCS total measurement.
| |
| measurement.
| |
| total flow flow rate rate isis within within limit limit by by
| |
| -[18] months r(
| |
| BWOG STS SWOG STS 3.4.1-2 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Minimum RCS Minimum Temperature Temperature for for Criticality Criticality 3.4.2 3.4.2 3.4 REACTOR 3.4 REACTOR COOLANT COOLANT SYSTEMSYSTEM (RCS) (RCS) 3.4.2 3.4.2 RCS Minimum RCS Minimum Temperature Temperature for for Criticality Criticality L C 0 3.4.2 LCO 3.4.2 Each RCS Each RCS loop loop average average temperature (T), avg ) shall temperature (T shall be;::': 525°F.
| |
| be 2 525°F.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODE 1, MODE 1, MODE 2 MODE 2 with with kk,,eff ;::.:
| |
| 2 1.0.1.O.
| |
| ACTIONS ACTIONS CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A.
| |
| A. T T
| |
| ,,, avg in in one one or or more more RCS RCS A.l A.1 Be in Be in MODE MODE 2 2 with with K Keff eff 30 minutes 30 minutes loops not loops not within within limit.
| |
| limit. 1.O.
| |
| < 1.0.
| |
| /
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.2.1 SR 3.4.2.1 RCS ,T Verify RCS Verify T
| |
| ,, avg in in each loop r 525°F.
| |
| each loop;::.: 525°F. Ehours BWOG STS SWOG STS 3.4.2-1 Rev. 3.0, Rev. 3.0, 03/31/04 03131104
| |
| | |
| TSTF-425, Rev. 3 RCS P/T Limits RCS PIT Limits 3.4.3 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.3.1 SR 3.4.3.1 -**------------------.--------NOT
| |
| --*-----------------em-------- NOTE ..............................
| |
| E----.--------------------**---
| |
| Only required Only required to to be performed during be performed during RCS RCS heatup heatup and cooldown and cooldown operations operations and RCS inservice and RCS inservice leak leak and hydrostatic and hydrostatic testing. testing.
| |
| Verify Verify RCS RCS pressure, pressure, RCS RCS temperature, temperature, and and RCSRCS Eminutes heatup and heatup and cooldown cooldown rates rates are are within within the the limits limits L----r_ _
| |
| specified in specified in the the PTLR.
| |
| PTLR.
| |
| BWOG STS SWOG STS 3.4.3-2 3.0, 03/31/04 Rev. 3.0, Rev. 03131104
| |
| | |
| TSTF-425, Rev. 3 RCS Loops -- MODES RCS Loops MODES 1Iand and 22 3.4.4 3.4.4 3.4 REACTOR 3.4 REACTOR COOLANT COOLANT SYSTEMSYSTEM (RCS)
| |
| (RCS) 3.4.4 3.4.4 RCS Loops RCS - MODES 11 and Loops - MODES and 22 L C 0 3.4.4 LCO 3.4.4 Two RCS Two RCS Loops shall be Loops shall be in in operation, with:
| |
| operation, with:
| |
| a.
| |
| : a. Four reactor Four reactor coolant coolant pumps pumps (RCPs)
| |
| (RCPs) operating operating or or b.
| |
| : b. Three RCPs Three RCPs operating operating andand THERMAL POWER restricted THERMAL POWER restricted to to
| |
| [79.9]% RTP.
| |
| [79.9}% RTP.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 1Iand MODES and 2.2.
| |
| ACTIONS ACTIONS CONDITION REQUIRED ACTION PLETION TIME COMPLETION TIME A. Requirements of A. Requirements of A .l A.1 Be in Be in MODE MODE 3. 3. 6 hours 6 hours LC0 not LCO not met.
| |
| met.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.4.1 SR 3.4.4.1 Verify required Verify required RCS RCS loops loops are are in operation.
| |
| in operation.
| |
| BWOG STS BWOG STS 3.4.4-1 3.0, 03/31/04 Rev. 3.0, Rev. 03131104
| |
| | |
| TSTF-425, Rev. 3 Loops -- MODE RCS Loops RCS MODE 3 3 3.4.5 3.4.5 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME C. Two C. Two RCS RCS loops loops C.l C.1 Suspend operations Suspend operations that that Immediately Immediately inoperable.
| |
| inoperable. would cause introduction would cause introduction of of coolant into coolant into thethe RCS RCS with with OR OR boron concentration boron concentration less less than required than required to to meetmeet SDM SDM RCS loop Required RCS Required loop notnot of LCO of 3.1.1.
| |
| LC0 3.1.1.
| |
| in operation.
| |
| in operation.
| |
| AND C.2 C.2 Initiate action Initiate action to to restore restore lmmediately Immediately one RCS one RCS loop loop to to OPERABLE status OPERABLE status and and operation.
| |
| operation.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.5.1 SR 3.4.5.1 Verify one Verify one RCS RCS looploop isis in in operation.
| |
| operation. @'
| |
| (1_2 hours hours SR 3.4.5.2 SR 3.4.5.2 ............................... NOTE
| |
| -------------------------------NOTE------------------------------
| |
| -+----------------------------
| |
| Not required Not required to to bebe periormed performed until until 24 24 hours hours after after a a
| |
| required pump required pump is is not not in in operation.
| |
| operation.
| |
| Verify correct Verify correct breaker breaker alignment alignment and and indicated indicated power available power available to to each each required required pump.pump.
| |
| BWOG STS BWOG STS 3.4.5-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Loops -- MODE RCS Loops MODE 4 4 3.4.6 3.4.6 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME Two required
| |
| : 8. Two B. required loops loops B.l B.1 Suspend operations Suspend operations that that Immediately Immediately inoperable.
| |
| inoperable. would cause would cause introduction introduction ofof coolant into coolant into the the RCS RCS with with boron concentration boron concentration less less than required than required to to meet SDM meet SDM Required loop Required loop not not in in of LCO of LC0 3.1.1."
| |
| 3.1.1.'
| |
| operation.
| |
| operation.
| |
| AND B.2 B.2 Initiate action Initiate action to to restore restore one one lmmediately Immediately loop to loop to OPERABLE OPERABLE statusstatus and operation.
| |
| and operation.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.6.1 SR 3.4.6.1 Verify required Verify required DHRDHR or or RCS RCS loop loop is is in in operation.
| |
| operation.
| |
| SR 3.4.6.2 -------------------------------NOTE------------------------------
| |
| Not required to be performed until 24 hours after a required pump is not in operation.
| |
| Verify correct Verify breaker alignment correct breaker alignment andand indicated indicated power available power available to to each each required required pump.
| |
| pump.
| |
| STS BWOG STS BWOG Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Loops RCS -
| |
| Loops - MODE MODE 5, Loops Filled 5, Loops Filled 3.4.7 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS I
| |
| P C SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.7.1 SR 3.4.7.1 Verify required Verify required DHR DHR looploop isis in operation.
| |
| in operation. § hours':(inSerti)
| |
| SR 3.4.7.2 SR 3.4.7.2 Verify required Verify required SG SG secondary secondary sideside water levels are water levels are iii hours hours 2 [50]%.
| |
| 2': [5Ol0/0.
| |
| ITn5er f.1-SR 3.4.7.3 SR 3.4.7.3 ...............................
| |
| -------------------------------NOT NOTE ..............................
| |
| E------------------------------
| |
| Not required Not required to to bebe performed performed until until 24 hours after 24 hours after a a required pump required pump is is not not inin operation.
| |
| operation.
| |
| Verify correct Verify correct breaker breaker alignment alignment and and indicated indicated power available power available to to each each required required DHR DHR pump.pump.
| |
| BWOG STS BWOG STS 3.4.7-3 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Loops -- MODE RCS Loops 5, Loops MODE 5, Loops Not Not Filled Filled 3.4.8 3.4.8 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME B. No required B. No required DHR DHR loop loop B.1 B.1 Suspend operations Suspend operations that that Immediately Immediately OPERABLE.
| |
| OPERABLE. would cause would cause introduction introduction ofof coolant into coolant into the the RCS RCS with with OR boron concentration boron concentration less less than required than required toto meet SDM meet SDM Required DHR Required DHR loop loop not not of L C 0 3.1.1.
| |
| of LCO 3.1.1.
| |
| in operation.
| |
| in operation.
| |
| AND 6.2 B.2 Initiate action Initiate action to to restore restore one one Immediately Immediately DHR loop DHR loop to to OPERABLE OPERABLE status and status and operation.
| |
| operation.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.8.1 SR 3.4.8.1 Verify required Verify required DHRDHR loop loop isis in in operation.
| |
| operation.
| |
| SR 3.4.8.2 -------------------------------NOTE------------------------------
| |
| Not required to be performed until 24 hours after a required pump is not in operation.
| |
| correct breaker Verify correct Verify breaker alignment alignment and and indicated indicated power available power available to to each each required required DHRDHR pump.
| |
| pump.
| |
| BWOG STS BWOG STS 3.4.8-2 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Pressurizer Pressurizer 3.4.9 3.4.9
| |
| -I-ACTIONS (continued)
| |
| ACTIONS (continued) 1 CONDITION CONDITION I REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME D. Required D. Required Action and Action and D.l D.1 Be in Be in MODE MODE 3. 3. 6 hours associated Completion associated Completion Time of Time of Condition Condition C not C not AND met.
| |
| met.
| |
| 0.2 0.2 Be in Be in MODE4.
| |
| MODE 4. 12 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.9.1 SR 3.4.9.1 Verify pressurizer Verify pressurizer water level < [290]
| |
| water level::;;; inches.
| |
| [290] inches. k 2 hours -reC,,d 1
| |
| )
| |
| SR 3.4.9.2 [ Verify 2::
| |
| [Verify r [126] kW of
| |
| [I261 kW of pressurizer pressurizer heaters heaters are are @ 81months]
| |
| @81 months ]
| |
| h
| |
| ~
| |
| capable of being powered from an emergency capable of being powered from an emergency power supply.
| |
| power supply.
| |
| SR 3.4.9.3 (( Verify Verify emergency heaters is emergency power is OPERABLE.
| |
| OPERABLE.
| |
| power supply supply forfor pressurizer pressurizer WBI monthsG-r'*~,C:t~t*m heaters BWOG STS BWOG STS 3.4.9-2 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 PressurizerPORV Pressurizer PORV 3.4.1 1 3.4.11 SURVEILLANCEREQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY SR 3.4.11.1 SR 3.4.11.1 ------------------------------NOTE
| |
| ------------------------------NO ----------------------
| |
| TE-------------------.---------
| |
| Not required Not requiredto to be be performed performedwithwith block block valve valve closed in closed inaccordance accordancewith with the the Required RequiredActions Actions of of this LCO.
| |
| this LCO.
| |
| Performone Perform one complete completecycle cycle of the block of the block valve.
| |
| valve.
| |
| SR 3.4.11.2 SR 3.4.11.2 Performone Perform one complete complete cycle cycle of of the the PORV.
| |
| PORV.
| |
| SR 3.4.11.3 SR 3.4.11.3 Verify PORV
| |
| ((Verify PORV and block valve and block valve are are capable capable of of being being poweredfrom powered from anan emergency emergency powerpowersource.
| |
| source.
| |
| BWOG STS SWOG STS 3.4.11-2 Rev. 3.0.
| |
| Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 LTOP System LTOP System 3.4.12 3.4.12 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME I.I. Pressurizer level Pressurizer level 1.1 1.1 Depressurize RCS Depressurize RCS and and 12 hours 12 hours
| |
| > [220)
| |
| > inches.
| |
| [220] inches. establish RCS establish RCS vent vent of of
| |
| ;:::: [0.75] square 2 [0.75) square inch.
| |
| inch.
| |
| PORV inoperable.
| |
| PORV inoperable.
| |
| LTOP System LTOP System inoperable for inoperable for any any reason other reason other than than Condition A Condition through A through Condition H.
| |
| Condition H.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.12.1 SR 3.4.12.1 Verify a maximum of [one) makeup pump is capable of injecting into the RCS.
| |
| lli hours SR 3.4.12.2 SR 3.4.12.2 Verify HPI Verify HPI isis deactivated.
| |
| deactivated.
| |
| SR 3.4.12.3 Verify y each CFT is isolated.
| |
| _S_R_3_.4_.1_2_.3 v_e_ri_f_e_a_c_h_C_F_T_iS_i_SO_I_a_te_d_. ..........j -""""'-~
| |
| SR 3.4.12.4 SR 3.4.12.4 Verify pressurizer Verify pressurizer level level is is ::; [220] inches.
| |
| 5 [220] inches. 30 minutes 30 minutes during during heatup and RCS heatup RCS and cooldown cooldown AND
| |
| [i2 hours
| |
| [L2 hours r.-.......
| |
| -. I SR 3.4.12.5 SR 3.4.12.5 Verify PORV Verify PORV block valve is block valve is open.
| |
| open. @hours ~,....._ _-1-_
| |
| BWOG STS SWOG STS 3.4.12-3 3.4.12-3 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 LTOP System LTOP System 3.4.1 2 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)
| |
| (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.12.6 SR 3.4.12.6 Verify required Verify RCS vent 2 required RCSvent [0.75] square
| |
| ~ [0.75J square inch is inch is E2 hours
| |
| [2 hours for for open.
| |
| open. unlocked open unlocked open vent valve(s) vent valve(s) 31 days for other path(S)~~CI"+!
| |
| vent path(s) vent D
| |
| SR 3.4.12.7 SR 3.4.12.7 Perform CHANNEL Perform CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST for for PORV.
| |
| PORV. Within [12]
| |
| Within [12] hours hours after decreasing after decreasing RCS temperature RCS temperature to to ~
| |
| I 12831°F
| |
| [283]OF AND 12-1 4
| |
| days thereafter~
| |
| 31 days thereafter .J. 1""
| |
| (Inse~_~
| |
| SR 3.4.12.8 SR 3.4.12.8 Perform CHANNEL Perform CHANNEL CALIBRATION CALIBRATION for for PORV.
| |
| PORV. [t8]months,~ .... ~
| |
| ~e(1
| |
| =~~~~~~----------------_ ....._---~--=
| |
| BWOG STS BWOG STS 3.4.12-4 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Operational RCS LEAKAGE Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS - - -
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.13.1 ------------------------------N 0 TES-----------------------------
| |
| : 1. Not required to be performed until 12 hours after establishment of steady state operation.
| |
| : 2. Not
| |
| : 2. Not applicable applicable to primary to to primary to secondary secondary
| |
| -- LEAKAGE.
| |
| LEAKAGE.
| |
| Verify RCS Verify RCS operational operational LEAKAGE LEAKAGE is within limits is within by limits by performance of performance of RCS RCS water water inventory inventory balance.
| |
| balance.
| |
| SR 3.4.13.2 ------------------------------NOTE----------------------------_.
| |
| Not required to be performed until 12 hours after establishment of steady state operation.
| |
| Verify primary to secondary LEAKAGE is -7 2 hours 4
| |
| ::::: 150 gallons per day through anyone SG.
| |
| SWOG STS BWOG STS 3.4.13-2 Rev. 3.1,12/01/05 Rev. 3.1, 12/01/05
| |
| | |
| TSTF-425, Rev. 3 RCS PIV RCS PIV Leakage Leakage 3.4.14 3.4.14 SURVEILLANCE SURVEILLANCE REQUIREMENTS REQUIREMENTS - -
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.14.1 ------------------------------NOTE S----------------------------
| |
| : 1. Not required to be performed in MODES 3 and 4.
| |
| 2.
| |
| : 2. Not required Not required to to be be performed performed on on the the RCS PlVs RCS PIVs located in located in the DHR flow the DHR flow path path when when in in the the DHR DHR mode of mode of operation.
| |
| operation.
| |
| : 3. RCS PlVs actuated RCS PIVs actuated during during the the performance performance of of this Surveillance this Surveillance are are not not required required toto be be tested tested more than more than once a repetitive once ifif a repetitive testing testing loop loop cannot be cannot be avoided.
| |
| avoided.
| |
| Verify leakage Verify leakage from from each each RCS PIV is RCS PIV is equivalent equivalent toto In accordance In accordan 5 0.5
| |
| :s; 0.5 gpm gpm per per nominal nominal inchinch of of valve valve size size up up to to a a with the Inservice with the Inservice maximum of maximum 5 gpm of 5 gpm at at an an RCS RCS pressure pressure Testing Program Testing Program
| |
| [2215] psia
| |
| ;::.2: [2215] psia and and :s; I [2255] psia.
| |
| [2255] psia. orIT18]mO~
| |
| -AND AND ~
| |
| Prior to Prior to entering entering MODE 2 MODE 2 whenever the whenever the unit unit has been has been in in MODE 55 for MODE for 77 days days or or more, more, ifif leakage testing leakage testing has not has not been been performed in performed in the the previous 9 previous 9 months months
| |
| (( Within Within 24 24 hours hours following valve following valve actuation due actuation due toto automatic or automatic or manual action manual action or or flow through flow through thethe valve ]
| |
| valve]
| |
| BWOG STS BWOG STS 3.4.14-3 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS PIV RCS PIV Leakage Leakage 3.4.14 3.4.14 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.14.2 ------------------------------NOTE------------------------------
| |
| [ Not required to be met when the DHR System autoclosure interlock is disabled in accordance with LCO 3.4.12.
| |
| Verify DHR Verify the valves the DHR System valves from System autoclosure from being autoclosure interlock being opened opened with interlock prevents with a a simulated prevents simulated or or
| |
| [18] 9 months ]
| |
| [ I 81 months]
| |
| actual RCS actual RCS pressure pressure signal signal ;::0:
| |
| 2 [425][425] psig.
| |
| psig. ']:11$C,t 1-SR 3.4.14.3 SR 3.4.14.3 -------------------------------N0
| |
| --------d-dd-e-------d*------*- NOTE ..............................
| |
| TE------------------------------
| |
| (( Not Not required required to to bebe met met when when the DHR System the DHR System autoclosure interlock autoclosure interlock isis disabled disabled in in accordance accordance with with 3.4.12.
| |
| L C 0 3.4.12.
| |
| ?
| |
| LCO Verify DHR Verify DHR SystemSystem autoclosure autoclosure interlock interlock causes causes the the [ I 81 months]
| |
| [18] months ]
| |
| valves to valves to close close automatically automatically with with a a simulated simulated or or actual RCS actual RCS pressure pressure signal signal ;::0:
| |
| 2 [600][600] psig.
| |
| psig.
| |
| BWOG STS SWOG 3.4.14-4 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Leakage RCS Leakage Detection Detection Instrumentation Instrumentation 3.4.1 5 3.4.15 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME B.1.2 --------------NOTE--------------
| |
| ~~-~-~--~~--~~NO TE -~~~-~-~--~~--
| |
| Not required Not required until until 12 12 hours hours after establishment after establishment of of steady state steady state operation.
| |
| operation.
| |
| Perform SR Perform SR 3.4.13.1.
| |
| 3.4.1 3.1. per 24 Once per Once 24 hours hours AND B.2 Restore required Restore required 30 days 30 days containment atmosphere containment atmosphere radioactivity monitor radioactivity monitor to to OPERABLE status.
| |
| OPERABLE status.
| |
| C. Required C. Required Action and Action and C.1 C.1 Be in Be in MODE MODE 3. 3. 6 hours 6 hours associated Completion associated Completion Time not Time not met.
| |
| met. AND C.2 C.2 Be in Be in MODE MODE 5. 5. 36 hours 36 hours D. Both D. Both required required monitors monitors D.l D.1 Enter LCO Enter L C 0 3.0.3.
| |
| 3.0.3. Immediately Immediately inoperable.
| |
| inoperable.
| |
| I SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.15.1 3.4.15.1 Perform CHANNEL CHANNEL CHECK CHECK of of required required containment containment 12 hours SR Perform atmosphere radioactivity atmosphere radioactivity monitor.
| |
| monitor. C SR 3.4.15.2 SR 3.4.15.2 Perform CHANNEL Perform CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST of of required required containment atmosphere containment atmosphere radioactivity radioactivity monitor.
| |
| monitor.
| |
| ---~-~._-_. - -"__. _
| |
| BWOG STS BWOG STS 3.4.15-2 Rev. 3.0, Rev. 3.0, 03/31104 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Leakage RCS Leakage Detection Detection Instrumentation Instrumentation 3.4.15 3.4.15 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.15.3 SR 3.4.15.3 Perform CHANNEL Perform CHANNEL CALI containment sump containment CALIBRATION BRATJON of monitor.
| |
| sump monitor.
| |
| of required required k8]months fi SR 3.4.15.4 SR 3.4.15.4 Perform CHANNEL Perform CHANNEL CALIBRATION CALIBRATION of of required required containment atmosphere containment atmosphere radioactivity radioactivity monitor.
| |
| monitor. '
| |
| BWOG STS SWOG STS 3.4.15-3 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Specific RCS Specific Activity Activity 3.4.16 3.4.16 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME C. Gross C. Gross specific specific activity activity of of C.l C.1 Be in Be in MODE MODE 3 3 with with 6 hours 6 hours the coolant not within the coolant not within Tavg T avg < 500°F.
| |
| c 500°F.
| |
| limit.
| |
| limit.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.16.1 SR 3.4.16.1 Verify reactor Verify reactor coolant coolant gross gross specific specific activity activity 7 days 61
| |
| ::; IOO/E llCi/gm.
| |
| I 100/E pCi/gm.
| |
| SR 3.4.16.2 SR 3.4.16.2 -------------------------------NOTE
| |
| -------------------------------NOTE w _
| |
| Only required Only required to to be be performed performed in in MODE MODE 1. 1.
| |
| Verify reactor Verify reactor coolant coolant DOSEDOSE EQUIVALENT EQUIVALENT 1-131 1-131 specific activity::;
| |
| specific activity I 1.0 I..lCi/gm.
| |
| 1.0 pCi1gm.
| |
| Between 2 Between 2 and and 6 hours 6 hours after after THERMAL THERMAL POWER change POWER change 15% RTP of 2'2: 15%
| |
| of RTP within a within a11 hour hour period period SR 3.4.16.3 SR 3.4.16.3 ............................... NOTE..............................
| |
| -------------------------------NOTE------------------------------
| |
| Not required Not required to to bebe performed performed until until 3131 days days after after aa minimum of minimum of 22 EFPD EFPD and and 20 20 days days of of MODE MODE 1 1 operation have operation have elapsed elapsed since since thethe reactor reactor was was last last subcritical for subcritical 48 hours.
| |
| for 2'2: 48 hours.
| |
| ~j Determine E. E.
| |
| i_
| |
| Determine ~ days -e:: ~
| |
| rI.n.l1Prf1, o....:.J.. oI~~
| |
| BWOG STS BWOG STS 3.4.16-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 CFTs CFTs 3.5.1 3.5.1 3.5 EMERGENCY 3.5 EMERGENCY CORE CORE COOLING COOLING SYSTEMS SYSTEMS (ECCS) (ECCS) 3.5.1 3.5.1 Core Flood Core Flood Tanks Tanks (CFTs)
| |
| (CFTs)
| |
| L C 0 3.5.1 LCO 3.5.1 Two CFTs Two CFTs shall be OPERABLE.
| |
| shall be OPERABLE.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 1 MODES 1 and 2, and 2, MODE 3 MODE 3 with with Reactor Reactor Coolant Coolant System System (RCS)
| |
| (RCS) pressure>
| |
| pressure > [750]
| |
| [750] psig.
| |
| psig.
| |
| ACTIONS ACTIONS CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. One A. One CFT CFT inoperable inoperable due due A A.1 Restore boron Restore boron 72 hours 72 hours to boron to boron concentration concentration concentration to concentration to within within not within not within limits.
| |
| limits. limits.
| |
| limits.
| |
| _._~_.~.,,~---
| |
| B. One B. CFT inoperable One CFT inoperable for for 6.1 8.1 Restore CFT Restore CFT to to 1 hour 1 hour reasons other reasons other than than OPERABLE status.
| |
| OPERABLE status.
| |
| A.
| |
| Condition A.
| |
| Condition C. Required C. Required Action and Action and C.l C.1 Be in Be in MODE MODE 3. 3. 6 hours 6 hours associated Completion associated Completion Time of Time Condition A of Condition or B A or B AND not met.
| |
| not met.
| |
| C.2 C.2 Reduce RCS Reduce RCS pressure pressure to to [ I21 hours
| |
| [12] hours
| |
| [750] psig.
| |
| $5 [750] psig.
| |
| D. Two D. Two CFTs CFTs inoperable.
| |
| inoperable. D.1 D.1 Enter LCO Enter L C 0 3.0.3.3.0.3. Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY 3.5.1.1 SR 3.5.1.1 Verify each Verify each eFT CFT isolation isolation valve valve is is fully fully open.
| |
| open.
| |
| BWOG STS BWOG STS 3.5.1-1 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 CFTs CFTs 3.5.1 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.5.1.2 SR 3.5.1.2 Verify borated Verify borated water water volume volume inin each each CFT CFT is is
| |
| ~
| |
| 2 [7555 gallons,
| |
| [7555 gallons, (( )) ft and 18005 ft and::; gallons, (( )) ft].
| |
| 8005 gallons, ft].
| |
| SR 3.5.1.3 SR 3.5.1.3 Verify nitrogen Verify nitrogen cover cover pressure pressure in in each each CFT CFT is is 6hours C,
| |
| ~ [575] psig 1 [575] psig and::;
| |
| and 5 [625]
| |
| [625] psig.
| |
| psig.
| |
| SR 3.5.1.4 SR 3.5.1.4 Verify boron Verify boron concentration concentration in in each each CFT CFT isis &1 days~
| |
| [2270] ppm ppm and::;
| |
| and 5 [3500]
| |
| [3500] ppm.
| |
| ppm.
| |
| 2'1: [2270]
| |
| AND ci.I'\Su+.i)
| |
| --------NOTE
| |
| --------N --------
| |
| 0 TE--------
| |
| Only required Only required to to be performed be performed for for affected CFT affected CFT Once within Once within 66 hours hours after after each each solution volume solution volume increase of increase of
| |
| [80 gallons]
| |
| 2'2: [80 gallons] that that is not is not the the result result of of addition from addition from the the borated water borated water storage tank storage tank 3 1 days 6 d
| |
| SR 3.5.1.5 SR 3.5.1.5 Verify power Verify power is valve operator valve is removed removed from operator when when RCS from each each eFT RCS pressure CFT isolation pressure isis 2 isolation
| |
| [2000] psig.
| |
| ~ [2000] psig.
| |
| § days !::l i~
| |
| BWOG STS SWOG STS 3.5.1-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 ECCS -- Operating ECGS Operating 3.5.2 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.5.2.1 SR 3.5.2.1 [ Verify the
| |
| [Verify with power with the following power to following valves to the the valve valves are valve operator are in in the the listed operator removed.
| |
| removed.
| |
| listed position position @hour~
| |
| Valve Number Valve
| |
| (( ]I Number Position Position
| |
| (( }1 Function Function
| |
| (( }1 (Xnserti)
| |
| [L ]1 (( ]1 (( ]1
| |
| (( }I (( ]I (( ]I SR 3.5.2.2 SR 3.5.2.2 Verify each Verify each ECCS automatic valve automatic ECCS manual, valve in manual, power in the the flow power operated, flow path, path, that operated, and that isis not and not locked, locked, §d~
| |
| sealed, or sealed, or otherwise correct position.
| |
| correct otherwise secured position.
| |
| secured in in position, position, is is in in the the I:nSJ',t ~
| |
| 3.5.2.3 SR 3.5.2.3 SR Verify ECCS
| |
| (( Verify ECCS piping piping isis full full of of water.
| |
| water §dayS~' IYiser ._
| |
| SR 3.5.2.4 SR 3.5.2.4 Verify each Verify each EGGS ECCS pump's pump's developed developed head head at at the the accordance In accordance In test flow point is greater than or equal to the test flow point is greater than or equal to the with the with Inservice the Inservice required developed required developed head.head. Testing Program Testing Program
| |
| .c SR 3.5.2.5 SR 3.5.2.5 Verify each Verify each ECCS ECCS automatic automatic valve valve inin the the flow flow path path months ~.
| |
| Q2[I8}81months 4, that is that is not not locked, locked, sealed, sealed, or or otherwise otherwise secured secured in in ___ -2.~
| |
| position, actuates position, actuates to to the the correct correct position position on on anan (j.n 5e ( -t 1.
| |
| actual or actual or simulated simulated actuation actuation signal.
| |
| signal.
| |
| " .. -~-,--
| |
| SR 3.5.2.6 SR 3.5.2.6 Verify each Verify ECCS pump each ECCS pump starts starts automatically automatically on on anan months ~
| |
| [I81 months
| |
| }l18J +-,
| |
| actual or actual or simulated simulated actuation actuation signal.
| |
| signal.
| |
| (I-n5e rt j.)
| |
| months~
| |
| SR 3.5.2.7 SR 3.5.2.7 (( Verify Verify the HPI stop HPI the correct correct settings stop check check valves:
| |
| settings of valves:
| |
| of stops stops for for the the following following
| |
| -[I 81months
| |
| [!Tal ]
| |
| a.
| |
| : a. [MUV-21,
| |
| [MUV-2], I.n5f~"( ..1-b.
| |
| : b. [MUV-61, and
| |
| [MUV-6], and ;~_., ...... ,,',..,......._-"'""--"'.,.~
| |
| C.
| |
| : c. [MUV-101.
| |
| [MUV-10].
| |
| BWOG STS BWOG STS 3.5.2-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 ECCS -- Operating ECCS Operating 3.5.2 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)
| |
| (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.5.2.8 [ Verify the
| |
| [Verify the flow flow controllers controllers for for the the following following LPI LPI throttle valves throttle valves operate operate properly:
| |
| properly:
| |
| a.
| |
| : a. [DHV-1101and
| |
| [DHV-110] and b.
| |
| : b. [DHV-1111.
| |
| [DHV-111J.
| |
| SR 3.5.2.9 Verify, by Verify, visual inspection, by visual inspection, each each ECCS ECCS train train containment sump containment suction inlet sump suction inlet is is not not restricted restricted by by debris and debris and suction suction inlet inlet trash trash racks racks and and screens screens show no show no evidence evidence of structural distress of structural distress or or abnormal abnormal corrosion.
| |
| corrosion.
| |
| BWOG STS SWOG STS 3.5.2-3 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 BWST BWST 3.5.4 3.5.4
| |
| -SURVEILLANCE SURVEILLANCE REQUIREMENTS REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.5.4.1 -----------------------------N0 NOTE ..............................
| |
| TE-----------.------------------
| |
| Only required Only required to to be be performed performed when ambient air when ambient air temperature is temperature < [40}OF is < [40]"F or > [1 or > [lOO]"F.
| |
| OO}OF.
| |
| Verify BWST Verify BWST borated borated water water temperature temperature is is 2: [40IoF 2 [40]OF 124 hours A and 5 [I and ~ OOJ°F.
| |
| [100]OF.
| |
| SR 3.5.4.2 Verify BWST Verify BWST borated borated water water volume volume is is ~ays
| |
| [415,200 gallons]
| |
| 2 [415,200 2: gallons] (( )) ft. and ~
| |
| ft. and I [449,000 gallons]
| |
| [449,000 gallons]
| |
| (( ]I ft.
| |
| ft.
| |
| SR 3.5.4.3 Verify BWST Verify BWST boron boron concentration concentration is is 2 [2270}
| |
| [2270] ppm ppm 7 davs A and I~ [2450}
| |
| and [2450] ppm.
| |
| ppm.
| |
| BWOG STS BWOG STS 3.5.4-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Containment Air Containment Locks Air Locks 3.6.2 3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS - - - -
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.6.2.1 SR 3.6.2.1 ------------------------------NOTES NOTES------~----------------------
| |
| I. An
| |
| : 1. inoperable air An inoperable air lock lock door door does does not not invalidate invalidate the previous successful performance the previous successful performance of of the the overall air overall air lock lock leakage leakage test.
| |
| test.
| |
| 2.
| |
| : 2. Results shall Results shall bebe evaluated evaluated against against acceptance acceptance criteria applicable criteria applicable to SR 3.6.1.1.
| |
| to SR 3.6.1.I.
| |
| Perform required Perform required air air lock lock leakage leakage rate rate testing testing in in In accordance In accordance accordance with accordance with thethe Containment Containment Leakage Leakage Rate Rate with the with the Testing Program.
| |
| Testing Program. Containment Containment Leakage Rate Leakage Rate Testing Program Testing Program 4
| |
| SR 3.6.2.2 SR 3.6.2.2 Verify only Verify only oneone door door in in the the air air lock lock cancan be be opened opened at at 24 months 6 a time.
| |
| a time.
| |
| SWOG STS BWOG STS 3.6.2-4 Rev. 3.0, Rev. 3.0,03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 [ Verify each [48] inch purge valve is sealed closed § days]
| |
| except for one purge valve in a penetration flow path while in Condition D of the LCO.
| |
| SR 3.6.3.2 Verify each [8] inch purge valve is closed except when the [8] inch purge valves are open for
| |
| §dayS ~
| |
| pressure control, ALARA or air quality considerations for personnel entry, or for (i;Ser'1})
| |
| (i;Ser'ID Surveillances that require the valves to be open.
| |
| SR 3.6.3.3 -------------------------------N 0 T E------------------------------
| |
| Valves and blind flanges in high radiation areas may be verified by use of administrative means.
| |
| Verify each containment isolation manual valve and blind flange that is located outside containment and E d(i2as, I"Y-> 5e--*.. . T--.1~*-
| |
| not locked, sealed, or otherwise secured and is
| |
| * I
| |
| * t required to be closed during accident conditions is closed, except for containment isolation valves that ---
| |
| are open under administrative controls.
| |
| SR 3.6.3.4 ------------------------------N0 TE-----------------------------
| |
| Valves and blind flanges in high radiation areas may be verified by use of administrative means.
| |
| Verify each containment isolation manual valve and Prior to entering blind flange that is located inside containment and MODE 4 from not locked, sealed, or otherwise secured and MODE 5 if not required to be closed during accident conditions is performed within closed, except for containment isolation valves that the previous are open under administrative controls. 92 days SR 3.6.3.5 Verify the isolation time of each automatic power [In accordance operated containment isolation valve is within limits. with the Inservice Testing Program or[§2 day~~*.
| |
| day~~ - _~
| |
| SWOG STS 3.6.3-6 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Containment Isolation Containment Isolation Valves Valves 3.6.3 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)(continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.6.3.6 SR 3.6.3.6 Perform leakage Perform leakage rate rate testing testing for for containment containment purge purge valves with valves with resilient resilient seals.
| |
| seals.
| |
| Within 92 Within days 92 days after opening after opening the the valve valve SR 3.6.3.7 SR 3.6.3.7 Verify each Verify each automatic automatic containment containment isolation isolation valve valve [jl8] months that is that is not not locked, locked, sealed, sealed, or or otherwise otherwise secured secured in in %
| |
| position, actuates position, actuates toto the the isolation isolation position position on an on an actual or actual or simulated simulated actuation actuation signal.
| |
| signal.
| |
| SR 3.6.3.8 Verify each
| |
| (( Verify each (( J] inch inch containment containment purge purge valve valve is is blocked to blocked to restrict restrict the the valve valve from from opening>
| |
| opening r [50]%.
| |
| [50]%.
| |
| BWOG STS BWOG STS 3.6.3-7 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Containment Pressure Containment Pressure 3.6.4 3.6.4 3.6 CONTAINMENT 3.6 CONTAINMENT SYSTEMSSYSTEMS 3.6.4 3.6.4 Containment Pressure Containment Pressure LC0 3.6.4 LCO 3.6.4 Containment pressure Containment pressure shall be 2 shall be [-2.01 psig
| |
| ~ [-2.0] psig and and s psig.
| |
| [+3.0]psig.
| |
| 5 [+3.0]
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 1, MODES 2, 3, 1, 2, 3, and and 4.
| |
| ACTIONS ACTIONS - -
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. Containment pressure A. Containment pressure A.l A.1 Restore containment Restore containment 1 hour 1 hour not within not within limits.
| |
| limits. pressure to pressure to within within limits.
| |
| limits.
| |
| B. Required B. Required Action and Action and B.l B.1 Be in Be in MODE MODE 3.3. 6 hours 6 hours associated Completion associated Completion Time not Time not met.
| |
| met. AND AND 8.2 B.2 Be in Be in MODE MODE 5.5. 36 hours 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.6.4.1 SR 3.6.4.1 Verify containment Verify containment pressure is within pressure is within limits.
| |
| limits. @hours BWOG STS BWOG STS 3.6.4-1 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Containment Air Containment Temperature Air Temperature 3.6.5 3.6.5 3.6 CONTAINMENT 3.6 CONTAINMENT SYSTEMSSYSTEMS 3.6.5 3.6.5 Containment Air Containment Temperature Air Temperature 3.6.5 LC0 3.6.5 LCO Containment average Containment average air air temperature temperature shall be 5 [130]OF.
| |
| shall be:-:::; [130IoF.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 1, MODES 2, 3, 1, 2, 3, and 4.
| |
| and 4.
| |
| ACTIONS ACTIONS CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. Containment average A. Containment average airair A.
| |
| A.11 Restore containment Restore containment 8 hours 8 hours temperature not temperature not within within average air average air temperature temperature to to limit.
| |
| limit. within limit.
| |
| within limit.
| |
| B. Required B. Required Action and Action and B.l B.1 Be in Be in MODE MODE 3. 3. 6 hours 6 hours associated Completion associated Completion Time not Time not met.
| |
| met. AND B.2 B.2 Be in Be in MODE MODE 5. 5. 36 hours 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS --
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY 3.6.5.1 SR 3.6.5.1 SR Verify containment Verify containment average average air air temperature temperature is is within within limit.
| |
| limit.
| |
| BWOG STS BWOG STS 3.6.5-1 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Containment Spray Containment Spray and and Cooling Cooling Systems Systems 3.6.6 3.6.6 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME E. Two E. Two [required]
| |
| [required] E.l E.1 Restore one Restore one [required]
| |
| [required] 72 hours 72 hours containment cooling containment cooling containment cooling containment cooling train train to to trains inoperable.
| |
| trains inoperable. OPERABLE status.
| |
| OPERABLE status.
| |
| F. Required F. Required Action and Action and F.1 F.1 Be in Be in MODE MODE 3. 3. 6 hours 6 hours associated Completion associated Completion Time of Time of Condition Condition C C or D or D AND AND not met.
| |
| not met.
| |
| F.2 F.2 Be in Be in MODE MODE 5. 5. 36 hours 36 hours G. Two G. Two containment containment spray spray G.l G.1 Enter LCO Enter L C 0 3.0.3.
| |
| 3.0.3. Immediately Immediately trains inoperable.
| |
| trains inoperable.
| |
| OR Any combination Any combination of of three three or more or more trains trains inoperable.
| |
| inoperable.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.6.6.1 SR 3.6.6.1 Verify each Verify each containment containment spray spray manual, manual, power power operated, and operated, and automatic automatic valve valve in in the the flow flow path path that that not locked, is not is locked, sealed, sealed, or or otherwise otherwise secured secured inin position is position is in in the the correct correct position.
| |
| position.
| |
| I_
| |
| IL SR 3.6.6.2 SR Operate each Operate each [required]
| |
| [required] containment containment cooling train cooling train 1/31days*
| |
| fan unit fan for r unit for 15 minutes.
| |
| ~ 15 minutes. @ O S C ~ 2)
| |
| BWOG STS SWOG STS 3.6.6-2 Rev. 3.1,12/01/05 Rev. 3.1,12/01/05
| |
| | |
| TSTF-425, Rev. 3 Containment Spray Containment Spray and and Cooling Cooling Systems Systems 3.6.6 3.6.6 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.6.6.3 SR 3.6.6.3 Verify each Verify each [required]
| |
| [required] containment containment cooling cooling train train ~1 days days cooling water cooling water flow flow rate rate is is 2 [I7801 gpm.
| |
| ~ [1780] gpm.
| |
| 3.6.6.4 SR 3.6.6.4 SR Verify each Verify each containment containment sprayspray pump's pump's developed developed In accordance In accordance head at head at the the flow flow test test point point is is greater greater than than or or equal equal to to with the Inservice with the Inservice the required the required developed developed head.
| |
| head. Testing Program Testing Program 3.6.6.5 SR 3.6.6.5 SR Verify each Verify each automatic automatic containment containment sprayspray valve valve in in @.8] months the flow the flow path path that that is is not not locked, locked, sealed, sealed, oror otherwise otherwise secured in secured in position, position, actuates actuates to to the the correct correct position position on an on an actual actual or or simulated simulated actuation actuation signal.
| |
| signal.
| |
| 3.6.6.6 SR 3.6.6.6 SR Verify each Verify each containment containment sprayspray pump pump starts starts automatically on automatically on an an actual actual oror simulated simulated actuation actuation signal.
| |
| signal.
| |
| SR 3.6.6.7 SR 3.6.6.7 Verify each Verify each [required]
| |
| [required] containment containment cooling cooling train train ~8] months starts automatically starts automatically on on an an actual actual oror simulated simulated actuation signal.
| |
| actuation signal.
| |
| SR 3.6.6.8 SR 3.6.6.8 Verify each Verify each spray spray nozzle nozzle isis unobstructed.
| |
| unobstructed. (( At first refueling]
| |
| At first refueling 3 AND G9 years BWOG STS SWOG STS 3.6.6-3 3.1, 12/01/05 Rev. 3.1,12/01/05 Rev.
| |
| | |
| TSTF-425, Rev. 3 Spray Additive Spray System Additive System 3.6.7 3.6.7 3.6 CONTAINMENT 3.6 CONTAINMENT SYSTEMS SYSTEMS 3.6.7 3.6.7 Spray Additive Spray System Additive System L C 0 3.6.7 LCO 3.6.7 The Spray The Spray Additive Additive SystemSystem shall shall be be OPERABLE.
| |
| OPERABLE.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 1, MODES 1, 2, 3, and 2, 3, 4.
| |
| and 4.
| |
| ACTIONS ACTIONS CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. Spray Additive A. Spray System Additive System A .l A.1 Restore Spray Restore Spray Additive Additive 72 hours 72 hours inoperable.
| |
| inoperable. System to System to OPERABLE OPERABLE status.
| |
| status.
| |
| B. Required B. Required Action Action and and B.1 B.1 Be in Be MODE 3.
| |
| in MODE 3. 6 hours 6 hours associated Completion associated Completion Time not Time not met.
| |
| met. AND B.2 B.2 Be in Be MODE 5.
| |
| in MODE 5. hours 84 hours 84 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.6.7.1 SR 3.6.7.1 Verify Verify eacheach spray and automatic and spray additive automatic valve additive manual, valve in in the manual, power the flow flow path power operated, path that operated, that is is not not 6 days GdayS n locked, sealed, locked, sealed, oror otherwise otherwise secured secured in position is in position is in in (InSer'r .1 the correct the correct position.
| |
| position.
| |
| SR 3.6.7.2 SR 3.6.7.2 Verify spray Verify spray additive additive tank tank solution solution volume volume is is 2
| |
| :::>: [12,970] gal
| |
| [12,970] gal and:::;
| |
| and 5 [13,920]
| |
| [13,920] gal.gal.
| |
| SR 3.6.7.3 SR 3.6.7.3 Verify spray Verify spray additive additive tank tank [NaOH]
| |
| [NaOH] solution solution h 4 days h§4days ~
| |
| concentration is concentration is :::>: [60,000 ppm]
| |
| 2 [60,000 ppm] and:::;
| |
| and 5 [65,000
| |
| [65,000 ppm].
| |
| ppm].
| |
| - (InSer-tD BWOG STS SWOG STS 3.6.7-1 3.6.7-1 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Spray Additive Spray System Additive System 3.6.7 3.6.7 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SU RVEI LLANCE I FREQUENCY FREQUENCY SR 3.6.7.4 SR 3.6.7.4 Verify each Verify each spray flow path spray additive path actuates additive automatic actuates to automatic valve the correct to the correct position in the valve in on an position on the an E8J months flow actual or actual or simulated simulated actuation actuation signal.
| |
| signal. In_3 eJ!- 1:.
| |
| ---.""- J SR 3.6.7.5 SR 3.6.7.5 Verify Spray Additive Verify Spray System flow Additive System flow [rate]
| |
| [rate] from from each each Eyears f'years solution's flow solution's flow path.
| |
| path. ~-,,-,
| |
| BWOG STS SWOG STS 3.6.7-2 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 MSIVs 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.7.2.1 SR 3.7.2.1 -------------------------------NOTE ..............................
| |
| --------~----------------------NOTE------------------------------
| |
| Only required Only required to to be be performed performed in in MODES MODES 11 and and 2. 2.
| |
| Verify isolation Verify isolation time time ofof each each MSIV MSlV is is ::;;
| |
| 5 [6][6] seconds.
| |
| seconds. In accordance In accordance with the IInservice with the nservice Testing Program Testing Program SR 3.7.2.2 --------~----------------------NOTE ----------------------~-------
| |
| Only required to be performed in MODES 1 and 2.
| |
| L-Verify each Verify each MSIV MSlV actuates actuates toto the the isolation isolation position position [I81 months ES]months ~
| |
| 6 actual or an actual or simulated simulated actuation actuation signal.
| |
| signal.
| |
| on an lt~..Y"I-1~.-&-_r-r*:~-1-"")
| |
| BWOG STS SWOG STS 3.7.2-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3
| |
| [MFSVs, MFCVs,
| |
| [MFSVs, MFCVs, and and Associated SFCVs]
| |
| Associated SFCVs]
| |
| 3.7.3 3.7.3 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME D. Two D. Two valves valves in in the same the same D.l D.1 Isolate affected Isolate affected flow flow path. path. 88 hours hours flow path flow path inoperable inoperable for for one or one or more flow paths.
| |
| more flow paths.
| |
| Required Action E. Required E. Action and and E.1 E.1 Be in Be in MODE MODE 3. 3. 66 hours hours Completion associated Completion associated Time not Time not met.
| |
| met. [AND
| |
| [AND E.2 E.2 Be in Be in MODE MODE 4. 4. 12 hours]
| |
| 12 hours ]
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS - --
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.7.3.1 SR 3.7.3.1 ------------------------~~-----N
| |
| ------------------------dd----- NOTE --------------------------~-~-
| |
| 0 TE----------------------------+-
| |
| Only required Only required to to be be performed performed in in MODES MODES 1Iand 2.
| |
| and 2.
| |
| Verify the Verify the isolation isolation time of each time of [MFSV], [MFCV],
| |
| each [MFSV}, [MFCV], In accordance In accordance and [SFCV]
| |
| and [SFCV] is [7] seconds.
| |
| is $I [7] seconds. with Inservice with the Inservice Testing Program Testing Program SR 3.7.3.2 SR 3.7.3.2 NOTE..............................
| |
| -------------------------~-----NOTE------------------------------
| |
| ------------------------+------
| |
| Only required Only required to to be performed in be performed in MODES MODES 11 and 2.
| |
| and 2.
| |
| +
| |
| Verify each Verify each [MFSV],
| |
| [MFSV], [MFCV],
| |
| [MFCV], and and [SFCV]
| |
| [SFCV] actuates actuates months ~
| |
| D2[18]8] months fi isolation position to the isolation to position on on an an actual actual or or simulated simulated ......
| |
| actuation signal.
| |
| actuation signal. IllSer-t .1 BWOG STS BWOG STS 3.7.3-2 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 AVVs AVVs 3.7.4 3.7.4 PLANT SYSTEMS 3.7 PLANT 3.7 SYSTEMS 3.7.4 3.7.4 Atmospheric Vent Valves Atmospheric Vent Valves (AVVs)
| |
| (AVVs)
| |
| L C 0 3.7.4 LCO 3.7.4 pTwo] A
| |
| [Two) AWsW s [lines
| |
| [lines per per steam steam generator) generator] shall shall be be OPERABLE.
| |
| OPERABLE.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 1, I , 2, and 3, 2, and 3, MODE 4 MODE 4 when when steam steam generator is relied generator is relied upon upon for for heat heat removal.
| |
| removal.
| |
| ACTIONS ACTIONS CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. One A. One required required AAW W [line)
| |
| [line] A.l A.1 Restore required Restore required AVV [line]
| |
| AVV [line) [7 days]
| |
| [7days) inoperable.
| |
| inoperable. to OPERABLE to OPERABLE status.
| |
| status.
| |
| Two or B. (( Two B. or more more required required B.l B.1 Restore all Restore all but but one one AAWW 24 hours]
| |
| 24 hours ]
| |
| AVV [lines] inoperable.
| |
| AVV [lines) inoperable. [line] to
| |
| [line) to OPERABLE OPERABLE status.
| |
| status.
| |
| Required Action C. Required C. and Action and C.1 C.1 Be in Be MODE 3.
| |
| in MODE 3. 6 hours 6 hours associated Completion associated Completion Time not Time not met.
| |
| met. AND C.2 C.2 Be in Be in MODE MODE 4 4 without without hours
| |
| [24] hours
| |
| [24]
| |
| reliance upon reliance upon steam steam generator for generator for heat heat removal.
| |
| removal.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 3.7.4.1 SR 3.7.4.1 SR Verify one Verify one complete complete cycle cycle of each AVV.
| |
| of each AVV. fi!.8] months In5el' BWOG STS SWOG STS 3.7.4-1 Rev. 3.0. 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 A Ws AWs 3.7.4 3.7.4 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY 3.7.4.2 SR 3.7.4.2 [ Verify one
| |
| [Verify one complete complete cycle cycle of each A of each AWW block block valve.
| |
| valve.
| |
| BWOG STS BWOG STS 3.7.4-2 Rev. 3.0, Rev. 3.0. 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EFW System EFW System 3.7.5 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.7.5.1 SR 3.7.5.1 Verify each Verify each EFW EFW manual, manual, powerpower operated, operated, and and days automatic valve automatic steam supply steam pumps, that pumps, valve in supply flow that is in each each water paths to flow paths is not not locked, water flow to the the steam locked, sealed, path and flow path steam turbine sealed, or and in or otherwise otherwise in both both driven turbine driven 5 secured in secured in position, position, is is in in the the correct correct position.
| |
| position.
| |
| SR 3.7.5.2 SR 3.7.5.2 -------------------------------NOTE
| |
| -------------------------------N0 ..............................
| |
| T E------------------------------
| |
| Not required Not required to to be be performed performed for for the the turbine turbine driven driven EFW pumps, EFW pumps, until [24] hours until [24] hours after after reaching reaching
| |
| [800] psig
| |
| [800] psig in in the the steam steam generators.
| |
| generators.
| |
| Verify the Verify the developed developed head head of of each each EFW EFW pump pump at at the the In accordance In accordance flow test flow test point point isis greater greater thanthan or or equal equal to to the the with the with Inservice the Inservice required developed required developed head. head. Testing Program Testing Program SR 3.7.5.3 SR 3.7.5.3 .............................. NOTES.............................
| |
| ------------------------------NOTES-----------------------------
| |
| I . Not
| |
| : 1. Not required required to to be be performed performed until [24] hours until [24] hours after reaching after reaching [800] [800] psig psig in in the the steam steam generators.
| |
| generators.
| |
| 2.
| |
| : 2. Not required Not required to to be be met met in MODE 4.
| |
| in MODE 4.
| |
| Verify each Verify sealed, or sealed, each EFW EFW automatic or otherwise automatic valve otherwise securedsecured in valve thatthat is in position, is not not locked, position, actuates locked, actuates to to fii-
| |
| [ I 8]
| |
| 81 months months ~
| |
| 5) the correct the correct position position on on anan actual actual or or simulated simulated actuation signal.
| |
| actuation signal.
| |
| 3.7.5.4 SR 3.7.5.4 SR .............................. NOTES.............................
| |
| ------------------------------NOTES-----------------------------
| |
| I . Not
| |
| : 1. Not required required to to be be performed performed until [24] hours until [24] hours after reaching after reaching [800] [800] psig psig in in the the steam steam generators.
| |
| generators.
| |
| : 2. Not required to be met in MODE 4.
| |
| each EFW Verify each Verify EFW pump pump starts starts automatically automatically on on anan 1181 months %?,-
| |
| actual or actual or simulated simulated actuation actuation signal.
| |
| signal.
| |
| BWOG STS SWaG STS 3.7.5-3 3.7.5-3 Rev. 3.1, Rev. 3.1, 12/01/05 12/01105
| |
| | |
| TSTF-425, Rev. 3 EFW System EFW System 3.7.5 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)
| |
| (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.7.5.5 SR 3.7.5.5 Verify proper Verify proper alignment alignment of the required of the required EFW EFW flow flow Prior to Prior to entering entering paths by paths by verifying verifying [valve alignment/flow] from
| |
| [valve alignment/flow1 from the the MODE 2 MODE 2 condensate storage condensate storage tank tank to to each each steam steam generator.
| |
| generator whenever plant whenever plant has been has been inin MODE 5, MODE 5, MODE 6, MODE 6, or or defueled for defueled a for a cumulative period cumulative period of> 30 days of > 30 days SR 3.7.5.6 SR 3.7.5.6 (( Perform Perform a EFW pump EFW a CHANNEL CHANNEL FUNCTIONAL pump suction FUNCTIONAL TEST suction pressure pressure interlocks.
| |
| TEST for interlocks.
| |
| for the the [I1 dayS~
| |
| (Tnce.rt1 )
| |
| 3.7.5.7 SR 3.7.5.7 (( Perform Perform a CHANNEL CALIBRATION a CHANNEL CALIBRATION for for the the EFW EFW pump suction pump suction pressure pressure interlocks.
| |
| interlocks.
| |
| BWOG STS BWOG STS 3.1, 12/01/05 Rev. 3.1,12/01/05 Rev.
| |
| | |
| TSTF-425, Rev. 3 CST CST 3.7.6 3.7.6 3.7 PLANT 3.7 SYSTEMS PLANT SYSTEMS 3.7.6 3.7.6 Condensate Storage Condensate Storage Tank (CST)
| |
| Tank (CST)
| |
| LCO 3.7.6 L C 0 3.7.6 The [two]
| |
| The [two] CST(s)
| |
| CST(s) shall shall be be OPERABLE.
| |
| OPERABLE.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 1, MODES 2, and 1, 2, and 3, 3, MODE 4 MODE 4 when when steam steam generator generator isis relied relied upon upon for for heat heat removal.
| |
| removal.
| |
| ACTIONS ACTIONS CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. The [two]
| |
| A. The [two] CST(s)
| |
| CST(s) A .l A.1 Verify by Verify by administrative administrative 4 hours 4 hours inoperable.
| |
| inoperable. means OPERABILITY means OPERABILITY of of backup water backup water supply.
| |
| supply. AND Once per Once 12 hours per 12 hours thereafter thereafter AND A.2 A.2 Restore CST(s)
| |
| Restore CST(s) to to 7 days 7 days status.
| |
| OPERABLE status.
| |
| OPERABLE B. Required B. Required Action and Action and B.l B.1 Be in Be in MODE MODE 3. 3. 6 hours 6 hours associated Completion associated Completion Time not Time not met.
| |
| met. AND B.2 B.2 Be in Be in MODE MODE 4 4 without without [24] hours
| |
| [241 hours reliance on reliance on steam steam generator for generator for heat heat removal.
| |
| removal.
| |
| /
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.7.6.1 SR 3.7.6.1 Verify CST Verify CST level level is is 2'2: [250,000]
| |
| [250,000] gal.
| |
| gal. @ hours
| |
| @ hours +
| |
| BWOG STS BWOGSTS 3.7.6-1 3.7.6-1 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 CCW System CCW System 3.7.7 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE I FREQUENCY FREQUENCY SR 3.7.7.1 SR 3.7.7.d -------------------------------NOTE
| |
| -------------------------------NOT ..............................
| |
| E------------------------------
| |
| Isolation of Isolation of CCW CCW flow flow toto individual individual components components does not does not render render CCWCCW System System inoperable.
| |
| inoperable.
| |
| Verify each Verify each CCW automatic valve CCW manual, valve in manual, power in the the flow power operated, flow path operated, and path servicing servicing safety and safety E days ~
| |
| ~
| |
| automatic related equipment, related equipment, that that is is not not locked, locked, sealed, sealed, or or otherwise secured otherwise secured in in position, position, is is in in the the correct correct position.
| |
| position.
| |
| SR 3.7.7.2 Verify each Verify CCW automatic each CCW automatic valve valve in in the the flow flow path path that is that is not not locked, locked, sealed, sealed, or or otherwise otherwise secured secured in in position, actuates position, actuates to to the the correct correct position position on on an an actual or actual or simulated simulated actuation signal.
| |
| actuation signal.
| |
| 3.7.7.3 S R 3.7.7.3 SR Verify each Verify each CCW CCW pumppump starts starts automatically automatically on on an an actual or simulated actuation signal.
| |
| actual or simulated actuation signal.
| |
| BWOG STS SWOG STS 3.7.7-2 Rev. 3.0.
| |
| Rev. 3.0. 03/31/04 03131104
| |
| | |
| TSTF-425, Rev. 3 SWS SWS 3.7.8 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY
| |
| . SR 3.7.8.1 -------------------------------NOTE------------------------------
| |
| Isolation of SWS flow to individual components does not render the SWS inoperable.
| |
| 'r-each SWS Verify each SWS manual, manual, power power operated, operated, and and
| |
| ~1 daY:,_.-,.-~_
| |
| Verify automatic valve automatic valve inin the the flow flow path path servicing servicing safety safety related equipment, related equipment, that that is is not not locked, locked, sealed, sealed, or or otherwise secured otherwise position.
| |
| position.
| |
| secured in in position, position, is is in in the the correct correct
| |
| ~ertD r--
| |
| SR 3.7.8.2 SR 3.7.8.2 Verify each Verify SWS automatic each SWS automatic valve valve inin the flow path the flow path [ I 81 months;
| |
| [18J months 6 that is is not not locked, locked, sealed, sealed, or or otherwise otherwise secured secured inin that position, actuates position, actual or actual actuates to or simulated to the the correct simulated actuation correct position position on actuation signal.
| |
| signal.
| |
| an on an L- ein r@
| |
| r-3.7.8.3 SR 3.7.8.3 Verify each Verify each SWS SWS pumppump starts starts automatically automatically onon an an [18] months
| |
| [18} months "1 C,
| |
| actual or actual or simulated simulated actuation actuation signal.
| |
| signal. I-..
| |
| arl~rt1.)
| |
| BWOG STS BWOG STS 3.7.8-2 Rev. 3.0, Rev. 3.0, 03/31/04 03l31104
| |
| | |
| TSTF-425, Rev. 3 UHS UHS 3.7.9 3.7.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE I FREQUENCY FREQUENCY 3.7.9.1 SR 3.7.9.1 SR [Verify water level of UHS is;::. [562] ft [mean sea ~4 hours]
| |
| level].
| |
| level].
| |
| SR 3.7.9.2 SR 3.7.9.2 Verify average
| |
| (( Verify average water water temperature temperature of UHS is of UHS is 5
| |
| S; [9Ol0F.
| |
| [90]OF.
| |
| SR 3.7.9.3 SR 3.7.9.3 [Operate each cooling
| |
| [ Operate each cooling tower tower fan fan for> [15] minutes.
| |
| for > [15] minutes. \2,1 days]
| |
| BWOG STS BWOG STS 3.7.9-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 CREVS CREVS 3.7.10 3.7.10 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME D. (( Required D. Required Action Action andand D.1 --------------N 0 TE---------------
| |
| associated Completion associated Completion Place in emergency mode if Time of Time of Condition Condition A not A not automatic transfer to met during met during movement movement of of emergency mode
| |
| [recently] irradiated
| |
| [recently] irradiated fuelfuel inoperable.
| |
| assemblies.
| |
| assemblies. -------------------------------------
| |
| Place OPERABLE Place OPERABLE CREVS CREVS Immediately Immediately train in train in emergency emergency mode. mode.
| |
| OR D.2 D.2 Suspend movement Suspend movement of of lmmediately ]
| |
| Immediately]
| |
| [recently] irradiated
| |
| [recently] irradiated fuel fuel assemblies.
| |
| assemblies.
| |
| E. [Two E. [ Two CREVS CREVS trains trains E.1 E.1 Suspend movement Suspend movement of of lmmediately ]
| |
| Immediately]
| |
| inoperable during inoperable during [recently] irradiated
| |
| [recently] irradiated fuel fuel movement of movement of [recently]
| |
| [recently] assemblies.
| |
| assemblies.
| |
| irradiated fuel irradiated fuel assemblies.
| |
| assemblies.
| |
| F. Two F. Two CREVS CREVS trains trains F.l F.1 Enter L C 0 3.0.3.
| |
| Enter LCO 3.0.3. lmmediately Immediately inoperable during inoperable during MODE 1, MODE 1,2, or 4 for 3, or 2, 3, for reasons other reasons other than than Condition B.
| |
| Condition B.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE I FREQUENCY FREQUENCY SR 3.7.10.1 SR 3.7.10.1 Operate each Operate hours with hours each CREVS with the CREVS train the heaters for P train for heaters operating 10 continuous
| |
| [~ 10 operating or continuous or (for (for system system 6 days without heaters) without I 5 minutes].
| |
| heaters) 2'2: 15 minutes].
| |
| BWOG STS BWOG STS 3.7.10-2 3.7.10-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 CREVS CREVS 3.7.1 0 3.7.10 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.7.10.2 SR 3.7.10.2 Perform required Perform required CREVS CREVS filter filter testing testing in in accordance accordance In accordance In accordance with the with the [Ventilation
| |
| [Ventilation Filter Filter Testing Testing Program Program (VFTP)).(VFTP)]. with the with [VFTP]
| |
| the [VFTP)
| |
| SR 3.7.10.3 SR 3.7.10.3 Verify [each Verify [each CREVS CREVS train train actuates) actuates] [or [or the the control control b181 months f{18] months room isolates) room isolates] on on anan actual actual or or simulated simulated actuation actuation Fi signal.
| |
| signal.
| |
| SR 3.7.10.4 SR 3.7.10.4 Verify one Verify one CREVS CREVS traintrain can can maintain maintain aa positive positive @
| |
| 1[18] months on 81 months on aa
| |
| <"I, pressure of::::>:
| |
| pressure of 2 [0.125)
| |
| [0.125] inches inches water water gauge gauge relativerelative to to TAGGERED
| |
| !.STAGGERED the adjacent the adjacent [area]
| |
| [area] during during the [pressurization] mode the [pressurization) mode TEST BASIS -E TESTBASIS of operation of at aa flow operation at flow rate rate of:":::
| |
| of I [3300] cfm.
| |
| [3300) cfm.
| |
| SR 3.7.10.5 SR 3.7.10.5 Verify the
| |
| (( Verify the system system makeup makeup flow flow raterate is [270] and is :2: >: [270] and
| |
| :I [330] cfm
| |
| ": : [330) cfm when when supplying supplying thethe the the control control room room with outside with outside air.
| |
| air.
| |
| BWOG BWOG STS STS 3.7.10-3 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 CREATCS CREATCS 3.7.1 1 3.7.11 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME E. Two E. Two CREATCS CREATCS trains trains E.l E.1 Enter LCO Enter L C 0 3.0.3.
| |
| 3.0.3. Immediately Immediately inoperable during inoperable during MODE 1, MODE 1, 2, 2, 3, or 4.
| |
| 3, or4.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE I FREQUENCY FREQUENCY SR 3.7.11.1 SR 3.7.11.1 Ver~fyeach Verify each CREATCS train has CREATCS train the capability has the capability to to remove the remove the assumed assumed heat heat load.
| |
| load.
| |
| BWOG STS SWOG STS 3.7.11-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EVS EVS 3.7.12 3.7.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.7.12.1 SR 3.7.12.1 Operate each Operate each EVS EVS train train for for [2':
| |
| [2 10 10 continuous continuous hours hours ~1 days with the with the heaters heaters operating operating or or (for (for systems systems without without I 5 minutes].
| |
| heaters) 2'2: 15 heaters) minutes].
| |
| T nscr'-t1-SR 3.7.12.2 SR 3.7.12.2 Perform required Perform required EVS EVS filter filter testing testing in in accordance accordance In accordance In accordance with the with the [Ventilation ventilation FilterFilter Testing Testing Program Program (VFTP)].
| |
| (VFTP)]. with the [VFTP]
| |
| with the [VFTP]
| |
| 4 SR 3.7.12.3 SR 3.7.12.3 Verify each Verify each EVSEVS train train actuates actuates on on an an actual actual or or [I81 months .E-.l, simulated actuation simulated actuation signal.
| |
| signal.
| |
| 4 3.7.12.4 SR 3.7.12.4 SR Verify one Verify one EVS EVS train train cancan maintain maintain a a pressure pressure $;
| |
| I(( )) [ I 81 months r[18] months on on aa inches water inches water gauge gauge relative relative toto atmospheric atmospheric pressure STAGGERED pressure LSTAGGERED during the during the [post
| |
| [post accident]
| |
| accident] mode mode of of operation operation at at a a TEST BASIS .fr TEST BASIS flow rate flow rate of:e::;
| |
| of 2 [3000]
| |
| [3000] cfm.
| |
| cfm.
| |
| SR 3.7.12.5 SR 3.7.12.5 (( Verify Verify each each EVS EVS filter filter cooling cooling bypass bypass damper damper cancan be opened.
| |
| be opened.
| |
| BWOG STS SWOG STS 3.7.12-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 FSPVS FSPVS 3.7.1 3 3.7.13 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME C. (( Required C. Required Action Action andand C.l C.1 Be in Be MODE 3.
| |
| in MODE 3. 66 hours hours associated Completion associated Completion Time of Time of Condition Condition A A oror BB AND not met in MODE 1,2,3, not met in MODE 1, 2, 3, or 4.
| |
| or4. C.2 C.2 Be in Be in MODE MODE 5. 5. 36 hours]
| |
| 36 hours ]
| |
| OR Two FSPVs Two FSPVs trains trains inoperable in inoperable in MODE MODE 1, 1, 3, or 2, 3, 2, or 4 for for reasons reasons other than other than Condition Condition B. B.
| |
| D. Required D. Required Action Action andand D.l D.1 Place OPERABLE Place OPERABLE FSPVS FSPVS Immediately Immediately associated Completion associated Completion train in train in operation.
| |
| operation.
| |
| Time of Time of Condition Condition A A not not met during met during movement movement of of OR
| |
| [recently] irradiated fuel
| |
| [recently] irradiated fuel assemblies in assemblies in the the fuel fuel D.2 D.2 Suspend movement Suspend movement of of lmmediately Immediately building.
| |
| building. [recently1irradiated
| |
| [recently] irradiated fuel fuel assemblies in assemblies in the the fuel fuel building.
| |
| building.
| |
| E. Two E. Two FSPVS FSPVS trains trains E.l E.1 Suspend movement Suspend movement of of lmmediately Immediately inoperable during inoperable during [recently] irradiated
| |
| [recently} irradiated fuel fuel movement of movement of [recently]
| |
| [recently] assemblies in assemblies in the the fuel fuel irradiated fuel irradiated fuel building.
| |
| building.
| |
| assemblies in assemblies in the the fuel fuel building.
| |
| building.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.7.13.1 SR 3.7.13.1 (( Operate Operate each each FSPVS FSPVS train train for for [~
| |
| [2 10 10 continuous continuous ~ days hours with hours with the the heaters heaters operating operating or or (for (for systems systems without heaters) without heaters) ~2 15 minutes].
| |
| 15 minutes}.
| |
| BWOG STS SWOG STS Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 FSPVS FSPVS 3.7.13 3.7.13 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.7.13.2 SR 3.7.13.2 (( Perform Perform required required FSPVS FSPVS filterfilter testing testing in in In accordance In accordance accordance with accordance with the the [Ventilation
| |
| [Ventilation Filter Filter Testing Testing with the with the [VFTP]
| |
| WFTP] J]
| |
| Program (VFTP)).
| |
| Program (VFTP)].
| |
| SR 3.7.13.3 SR 3.7.13.3 I Verify Verify each each FSPVS FSPVS train train actuates actuates on on an an actual actual or or simulated actuation simulated actuation signal.
| |
| signal.
| |
| SR 3.7.13.4 SR 3.7.13.4 Verify one Verify one FSPVS FSPVS train train cancan maintain maintain a a pressure pressure 1[18] months on a
| |
| $5 (( )) inches water inches water gauge gauge with with respect respect to to ~T'AGGERED TAGGERED atmospheric pressure atmospheric pressure during during thethe [post
| |
| [post accident]
| |
| accident] TEST BASIS6 TEST BASIS mode of operation at a flow rate mode of operation at a flow I rate::; [3000]
| |
| [3000] cfm.
| |
| cfm.
| |
| SR 3.7.13.5 SR 3.7.13.5 [ Verify each
| |
| [Verify each FSPVS FSPVS filter filter bypass bypass damper damper cancan be be opened.
| |
| opened.
| |
| BWOG STS BWOG STS 3.7.13-3 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Fuel Storage Fuel Storage Pool Pool Water Water Level Level 3.7.14 3.7.14 3.7 PLANT 3.7 PLANT SYSTEMS SYSTEMS 3.7.14 3.7.14 Fuel Storage Fuel Storage Pool Pool Water Water Level Level L C 0 3.7.14 LCO 3.7.14 The fuel The fuel storage storage pool pool water water level level shall shall be 23 ftft over be 22 23 over the the top top of of irradiated irradiated fuel assemblies fuel assemblies seated seated inin the storage racks.
| |
| the storage racks.
| |
| APPLICABILITY:
| |
| APPLICABILITY: During movement During movement of of irradiated irradiated fuel fuel assemblies assemblies in in fuel fuel storage storage pool.
| |
| pool.
| |
| ACTIONS ACTIONS CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. Fuel A. Fuel storage storage pool pool water water A. 1 A.1 --------------NOTE---------------
| |
| --------------NOTE---------------
| |
| level not within limit.
| |
| level not within limit. L C 0 3.0.3 LCO 3.0.3 isis not not applicable.
| |
| applicable.
| |
| ---------------------.+------------
| |
| Suspend movement Suspend movement of of Immediately Immediately irradiated fuel irradiated assemblies in fuel assemblies in fuel storage fuel storage pool.
| |
| pool.
| |
| 1 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR SR 3.7.14.1 3.7.14.1 Verify Verify the above the fuel above the fuel storage the top storage pool top of pool water of irradiated water level irradiated fuel level is fuel assemblies 2 23 is 2 23 ft assemblies seated ft seated in in f days the the storage storage racks.
| |
| racks.
| |
| BWOG BWOG STSSTS 3.7.14-1 Rev.
| |
| Rev. 3.0, 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3
| |
| [Spent Fuel
| |
| [Spent Fuel Pool Pool Boron Boron Concentration]
| |
| Concentration]
| |
| 3.7.15 3.7.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS P SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.7.15.1 3.7.15.1 Verify the the spent fuel pool spent fuel pool boron boron concentration is concentration is days ~--
| |
| SR Verify within limit.
| |
| within limit.
| |
| [idays 7
| |
| BWOG STS BWOG STS 3.7.15-2 3.0, 03/31/04 Rev. 3.0.
| |
| Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Secondary Specific Secondary Specific Activity Activity 3.7.1 7 3.7.17 3.7 PLANT 3.7 PLANT SYSTEMS SYSTEMS 3.7.1 7 3.7.17 Secondary Specific Secondary Specific Activity Activity LCO 3.7.17 The specific The specific activity activity of of the the secondary secondary coolant coolant shall shall be [0.10]
| |
| be $I [0.1 pCi/gm 0] ~Cilgm DOSE EQUIVALENT DOSE EQUIVALENT 1-131.1-131.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 1, MODES 1,2, 3, and 2, 3, and 4.
| |
| 4.
| |
| ACTIONS ACTIONS CONDITION CONDITION REQUIRED ACTiON REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. Specific activity A. Specific activity not not A.l A.1 Be in Be in MODE MODE 3. 6 hours 6 hours limit.
| |
| within limit.
| |
| within AND AND A.2 A.2 Be in MODE Be in MODE 5.
| |
| : 5. 36 hours 36 hours SURVEILLANCE SURVEILLANCE REQUIREMENTS REQUIREMENTS SURVEILLANCE SURVEILLANCE / FREQUENCY FREQUENCY SR 3.7.17.1 SR 3.7.17.1 Verify the specific activity of the secondary coolant [!31] days ( -
| |
| is $i [0.1 is [0.10]
| |
| 0] pCi/gm DOSE EQUIVALENT
| |
| ~Ci/gm DOSE EQUIVALENT 1-131.
| |
| 1-131.
| |
| IYl Se... +:t BWOG STS BWOG STS 3.7.17-1 Rev. 3.0, Rev. 03/31/04 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Steam Generator Steam Generator Level Level 3.7.18 3.7.18 3.7 PLANT 3.7 PLANT SYSTEMS SYSTEMS 3.7.1 8 3.7.18 Steam Generator Steam Generator Level Level L C 0 3.7.18 LCO 3.7.18 Water level Water level of of each each steam steam generator generator shall shall be be less less than than or or equal to the equal to the maximum water maximum water level level shown shown inin Figure Figure 3.7.18-1.
| |
| 3.7.18-1.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODES 11 and MODES and 2.
| |
| : 2. .
| |
| ACTIONS ACTIONS CONDITION CONDITION I REQUIRED ACTION REQUIRED ACTION I COMPLETION COMPLETION TIME TIME A. Water A. Water level level in in one one or or A.l A.1 Restore steam Restore steam generator generator 15 minutes 15 minutes more steam more steam generators generators level to level to within within limit.
| |
| limit.
| |
| greater than greater than maximum maximum water level water level in in 3.7.1 8-1.
| |
| Figure 3.7.18~1.
| |
| Figure B. Required B. Required Action Action and and B.l B.1 Be in Be in MODE MODE 3. 3. 66 hours hours associated Completion associated Completion Time of Time of Condition Condition A A not not met.
| |
| met.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 SR 3.7.18.1 Verify steam Verify steam generator generator water water level level to be within to be within limits.
| |
| limits.
| |
| BWOG STS BWOG STS 3.7.18-1 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 AC Sources -- Operating AC Sources Operating 3.8.1 3.8.1 I
| |
| ACTIONS ACTIONS (continued)(continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME
| |
| -----REV1
| |
| ~~~~-REVIEWER'SEWER'S NOTE-----
| |
| NOTE----- F.1 F.1 Restore [required]
| |
| Restore [required] [I21 hours]
| |
| [12] hours ]
| |
| (( This This Condition Condition may may be be [automatic load
| |
| [automatic foad sequencer]
| |
| sequencer]
| |
| deleted if deleted if the the unit unit design design is is to OPERABLE status.
| |
| such that such that any any sequencer sequencer failure mode failure mode will will only only affect affect the ability the ability of of the the associated associated DG to DG to power power its its respective respective safety loads safety loads following following a a loss loss of offsite power independent of offsite power independent of, or of, or coincident coincident with, with, a a Design Basis Design Basis Event.
| |
| Event.
| |
| F. One F. One [required]
| |
| [required]
| |
| [automatic load
| |
| [automatic load sequencer] inoperable.
| |
| sequencer] inoperable
| |
| .~~~-_.
| |
| G. Required Action G. Required Action and and G.l G.1 Be in Be MODE 3.
| |
| in MODE 3. 12 hours 12 hours Associated Completion Associated Completion Time of Time of Condition Condition A, A, B,B, AND C, D.
| |
| C. D, E.E, or [F] not or [F) not met.
| |
| met.
| |
| G.2 in MODE Be in Be MODE 5. 5. 36 hours 36 hours H. Three H. Three or or more more [required]
| |
| [required] H.l H.1 Enter LCO Enter L C 0 3.0.3.
| |
| 3.0.3. Immediately Immediately AC sources AC sources inoperable.
| |
| inoperable.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.1.1 SR 3.8.1.1 Verify correct breaker Verify correct power availability power breaker alignment availability for alignment and for each and indicated each [required]
| |
| indicated offsite circuit.
| |
| [required] offsite circuit.
| |
| c:. days r--~---I--_
| |
| BWOG STS BWOG STS 3.8.1-4 3.1, 12/01/05 Rev. 3.1,12/01/05 Rev.
| |
| | |
| TSTF-425, Rev. 3 AC Sources -- Operating AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY 3.8.1.2 SR 3.8.1.2 SR .............................. NOTES.............................
| |
| ------------------------------NOTES-----------------------------
| |
| I. All
| |
| : 1. DG starts All DG starts may may be be preceded preceded by by anan engine engine prelube period prelube period and and followed followed by by a warmup a warmup period prior period prior toto loading.
| |
| loading.
| |
| [ 2. A
| |
| [2. modified DG A modified DG startstart involving involiiing idling idling and and gradual gradual acceleration to acceleration to synchronous synchronous speed speed maymay be be used for used for this this SR SR as as recommended recommended by by the the manufacturer. When manufacturer. When modified modified start start procedures procedures are not are not used, used, the the time, time, voltage, voltage, and and frequency frequency tolerances of tolerances of SR 3.8.1.7 must SR 3.8.1.7 must bebe met.
| |
| met. ]j Verify each Verify each DG DG starts starts from from standby standby conditions conditions and and §days ~
| |
| achieves steady achieves steady statestate voltage;:::
| |
| voltage 2 [3740]
| |
| [3740] V V and and
| |
| [4580] V, I [4580]
| |
| :S
| |
| [61.2] Hz.
| |
| r [61.2]
| |
| :S and frequency::::
| |
| V, and Hz.
| |
| frequency 2 [58.8] [58.8] Hz Hz and and
| |
| ~
| |
| SR 3.8.1.3 SR 3.8.1.3 .............................. NOTES
| |
| ------------------------------NOTES----------------------------
| |
| DG loadings may I . DG loadings may include gradual
| |
| : 1. include gradual loading loading asas recommended by recommended by the the manufacturer.
| |
| manufacturer.
| |
| 2.
| |
| : 2. Momentary transients Momentary transients outsideoutside the the load load range range do do not invalidate not invalidate this this test.
| |
| test.
| |
| 3.
| |
| : 3. This Surveillance This Surveillance shall shall be be conducted conducted on on only only one DG one DG at at a a time.
| |
| time.
| |
| : 4. This SR shall be preceded by and immediately follow, without shutdown, a successful performance of SR 3.8.1.2 or SR 3.8.1.7.
| |
| Verify each Verify each DG DG is is synchronized synchronized and and loaded loaded andand [i1 days ~
| |
| ~
| |
| operates for::::
| |
| operates for 2 60 60 minutes minutes at at a a load::::
| |
| load 2 [4500]
| |
| [4500] kWkW and and
| |
| [5000] kW.
| |
| 2 [5000]
| |
| :S kW.
| |
| SR 3.8.1.4 SR 3.8.1.4 Verify each Verify each day day tank tank [and[and engine engine mounted mounted tank]
| |
| tank] G1dayS~_
| |
| 31 davs 6 contains 2 contains 12201 gal
| |
| ~ [220] gal of of fuel fuel oil.
| |
| oil.
| |
| ~l1)
| |
| SWOG STS BWOG STS 3.8.1-5 Rev. 3.1, Rev. 12/01/05 3.1, 12/01/05
| |
| | |
| TSTF-425, Rev. 3 AC Sources -- Operating AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.1.5 SR 3.8.1.5 Check for Check for and and removeremove accumulated accumulated water water from from each each [31] days day tank day tank [and [and engine engine mounted mounted tank]. tank].
| |
| SR 3.8.1.6 SR 3.8.1.6 Verify the Verify the fuelfuel oil
| |
| [automatically] transfer
| |
| [automatically]
| |
| oil transfer transfer system transfer fuel system operates fuel oil oil from operates to storage tank[s]
| |
| from storage to tank[s]
| |
| -[92] days +-,
| |
| to the to the day day tank tank [and [and engineengine mounted mounted tank]. tank].
| |
| SR 3.8.1.7 -------------------------------NOTE------------------------------
| |
| All DG starts may be preceded by an engine prelube period.
| |
| Verify each Verify achieves:
| |
| achieves:
| |
| each DG DG startsstarts from from standbystandby condition condition and and G84
| |
| -184 days days 6
| |
| a.
| |
| : a. In :0::;
| |
| In [ l o ] seconds, 5 [10] seconds, voltage voltage 2'2: [3740] [3740] V V and and IYlSert1.
| |
| frequency 2'2: [58.8]
| |
| frequency [58.8] Hz Hz and and b.
| |
| : b. Steady state Steady state voltagevoltage 2'2: [3740] [3740] V V and and :0::; I45801V, 5 [4580] V, and frequency and frequency 2'2: [58.8] [58.8] Hz Hz and and :0::; [61.2) Hz.
| |
| 2 [61.2} Hz.
| |
| 3.8.1.8 SR 3.8.1.8 -------------------------------NOTE
| |
| ------------------------------~NOTE------------------------------ ..............................
| |
| (( This This Surveillance Surveillance shall shall not not normally normally be be performed performed in MODE in MODE 11 or or 2. However, this
| |
| : 2. However, this Surveillance Surveillance may may be be performed to performed to reestablish reestablish OPERABILITY OPERABILITY provided provided an an assessment determines assessment determines the the safety safety of of the the plant plant is is maintained or maintained or enhanced.
| |
| enhanced. Credit Credit may may be be taken taken for for unplanned events unplanned events that that satisfy satisfy this this SR.
| |
| SR.
| |
| ----------------------------------------------+--+-------------------
| |
| Verify [automatic Verify sources from sources
| |
| [automatic [and]
| |
| from the
| |
| [and] manual]
| |
| the normal manual] transfer normal offsite offsite circuit transfer of circuit toto each of AC each power l[1S] months AC power t.'
| |
| months R j.
| |
| alternate [reqUired]
| |
| alternate [required] offsite offsite circuit.
| |
| circuit. ,.Ihser l1
| |
| " ,"" *._, __ . __ ".-_~. _ _____.L _
| |
| BWOG STS BWOG STS 3.8.1-6 Rev. 3.1, Rev. 3.1, 12/01/05 12/01/05
| |
| | |
| TSTF-425, Rev. 3 AC Sources -- Operating AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.1.9 SR 3.8.1.9 NOTES.............................
| |
| ------------------------------NOTES-----------------------------
| |
| [ I . This
| |
| [1. This Surveillance Surveillance shall shall not not normally normally be be performed in performed MODE 11 or in MODE or 2.2. However, However, this this Surveillance may Surveillance may be be performed performed to to reestablish reestablish OPERABILITY provided OPERABILITY provided an an assessment assessment determines the determines the safety safety of of the the plant plant is is maintained maintained or enhanced.
| |
| or enhanced. Credit Credit may may be be taken taken for for unplanned events unplanned events that that satisfy satisfy this SR.
| |
| this SR.
| |
| 2.
| |
| : 2. If performed If performed with with the the DG DG synchronized synchronized with with offsite power, offsite power, itit shall shall be be performed performed at at aa power power factor I~ [0.9].
| |
| factor 10.91. However, However, if if grid grid conditions conditions do do not not permit, the permit, the power power factor factor limit limit is is not not required required to to be met.
| |
| be met. Under Under this this condition condition the the power power factor factor shall be shall maintained as be maintained close to as close to the limit as the limit as practicable. ))
| |
| practicable.
| |
| Verify each Verify each DGDG rejects rejects a a load load greater greater thanthan or or equal equal to its to its associated associated singlesingle largest largest post-accident post-accident load, load, and:
| |
| and:
| |
| a.
| |
| : a. Following load Following load rejection, rejection, the the frequency frequency is is 5
| |
| S; [63] Hz,
| |
| [63] Hz, b.
| |
| : b. Within [3]
| |
| Within [3] seconds seconds following following loadload rejection, rejection, thethe voltage is voltage is r [3740] V
| |
| ~ [3740] V and and S; [4580] V, 5 [4580] V, and and c.
| |
| : c. Within [3]
| |
| Within [3] seconds seconds following following loadload rejection, rejection, thethe frequency is frequency is 2:: [58.8] Hz 2 [58.8] and s< [61.2}
| |
| Hz and [6l.2] Hz.
| |
| Hz.
| |
| BWOG STS BWOG STS 3.8.1-7 Rev. 3.1,12/01/05 Rev. 3.1, 12/01/05
| |
| | |
| TSTF-425, Rev. 3 AC Sources -- Operating AC Sources Operating 3.8.1 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY 3.8.1.10 SR 3.8.1.10 SR NOTES T --------------
| |
| -----------------------------NOTES----------------------_**-*_-
| |
| S EO N-----------------------------
| |
| S EO N
| |
| T ---..
| |
| S EO N
| |
| T
| |
| [1. This Surveillance
| |
| [I. This Surveillance shall shall not not normally normally be be performed in performed in MODE MODE 1 1 oror 2. 2. However, However, this this Surveillance may Surveillance may be be performed performed to to reestablish reestablish OPERABILITY provided OPERABILITY provided an an assessment assessment determines the determines the safety safety of of thethe plantplant is is maintained maintained or enhanced.
| |
| or enhanced. Credit Credit may may be be taken taken for for unplanned events unplanned events that that satisfy satisfy this this SR. SR.
| |
| 2.
| |
| : 2. If performed If performed with with the the DG DG synchronized synchronized with with offsite power, offsite power, itit shall shall be be performed performed at at a a power power factor [0.9]. However, factor ~ [0.9]. However, if grid conditions do 2 if grid conditions do not not permit, the permit, the power power factor factor limit limit is is notnot required required to to be met.
| |
| be met. Under Under this this condition condition the the powerpower factor factor shall be shall be maintained maintained as as close close to to thethe limit limit as as practicable. ))
| |
| practicable.
| |
| Verify each Verify each DG DG doesdoes not not trip,trip, and and voltage voltage is is ~ 8] months .5:;2--
| |
| maintained ~ [5000] V V during during and and following following a a load load Civ\~t.D maintained 5 [5000J rejection of rejection [4500] kW of 22 [4500] and < [5000]
| |
| kW and:"::: [5000] kW. kW.
| |
| BWOG STS BWOG STS 3.8.1-8 3.1, 12/01/05 Rev. 3.1,12/01/05 Rev.
| |
| | |
| TSTF-425, Rev. 3 AC Sources -- Operating AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.1.11 ------------------------------N0 TES-----------------------------
| |
| : 1. All DG starts may be preceded by an engine prelube period.
| |
| 2.
| |
| : 2. This Surveillance This Surveillance shall shall not not normally normally be be performed in performed in MODE MODE 1, 2, 3, 1, 2, 3, or 4. However, or 4. However, portions of portions of the the Surveillance Surveillance may may be be performed performed to reestablish to reestablish OPERABILITY OPERABILITY provided provided an an assessment determines assessment determines thethe safety safety ofof the the plant plant is maintained is maintained or or enhanced.
| |
| enhanced. CreditCredit may may bebe taken for taken for unplanned unplanned events events that that satisfy satisfy this SR.
| |
| this SR.
| |
| Verify on Verify on an an actual actual or or simulated simulated lossloss of of offsite offsite power power ~8] months signal:
| |
| signal:
| |
| a.
| |
| : a. De-energization of De-energization of emergency emergency buses,buses, Insert1-b.
| |
| : b. Load shedding Load shedding from from emergency emergency buses,buses, andand c.
| |
| : c. DG auto-starts DG auto-starts from from standby standby condition condition and:
| |
| and:
| |
| 1.
| |
| : 1. Energizes permanently Energizes permanently connected connected loads loads in:":: [lo] seconds, in I (101 seconds, 2.
| |
| : 2. Energizes auto-connected Energizes auto-connected shutdown shutdown loadload through [automatic through [automatic loadload sequencer],
| |
| sequencer],
| |
| 3.
| |
| : 3. Maintains steady-state Maintains steady-state voltage voltage 2 [3740] V
| |
| ~ [3740] V and S; and [4580] V, I[4580] V, 4.
| |
| : 4. Maintains steady-state Maintains steady-state frequency frequency
| |
| ::::: [58.8] Hz 2 [58.8] Hz and:"::
| |
| and 5 [61.2]
| |
| [61.2] Hz, Hz, and and 5.
| |
| : 5. Supplies permanently Supplies permanently connected connected and and auto-connected shutdown auto-connected shutdown loadsloads for for 25 5 minutes.
| |
| minutes.
| |
| BWOG STS BWOGSTS 3.8.1-9 Rev. 3.1, Rev. 3.1, 12/01/05 12/01/05
| |
| | |
| TSTF-425, Rev. 3 AC Sources -- Operating AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.1.12 SR 3.8.1.12 NOTES
| |
| ------------------------------NOTES-----------------------------
| |
| : 1. All
| |
| : 1. All DGDG starts starts may may be be preceded preceded by by an an engine engine prelube period.
| |
| prelube period.
| |
| 2.
| |
| : 2. This Surveillance This Surveillance shall shall not not normally normally be be performed in performed MODE 11 or in MODE or 2.2. However, However, portions portions of the of the Surveillance Surveillance may may be be performed performed to to reestablish OPERABILITY reestablish OPERABILITY provided provided an an assessment determines assessment determines the the safety safety of of the the plant plant is maintained is maintained or or enhanced.
| |
| enhanced. Credit Credit may may be be taken for taken for unplanned unplanned events events that that satisfy satisfy this this SR.
| |
| SR.
| |
| ---------------------------------------+-----------------------------
| |
| Verify on Verify on an an actual actual or or simulated simulated [Engineered[Engineered Safety Safety
| |
| {E8] monthsfl.----~.'.
| |
| Feature (ESF)]
| |
| Feature from standby from (ESF)] actuation standby condition actuation signal condition and: and:
| |
| signal each each DG DG auto-starts auto-starts
| |
| ~~;y a.
| |
| : a. In $
| |
| In [12] seconds 5 [12] seconds after after auto-start auto-start and and during during tests, achieves tests, achieves voltage voltage 2': [3740] V 2 [3740J V and and frequency 2'2: [58.8]
| |
| frequency [58.8] Hz, Hz, b.
| |
| : b. Achieves Achieves steady steady state state voltage voltage 2'2: [3740]
| |
| [3740] VV and5 [4580J and$ [4580] V V and and frequency frequency 2'2: [58.8J Hz and
| |
| [58.8] Hz and
| |
| [61.2] Hz,
| |
| $5 [61.2J Hz, c.
| |
| : c. Operates for Operates for 2'2: 55 minutes, minutes, d.
| |
| : d. Permanently connected Permanently connected loads loads remainremain energized energized from the from offsite power the offsite power system, system, and and e.
| |
| : e. Emergency loads Emergency loads are are energized energized [or [or auto-auto-connected through connected through the the automatic automatic load load sequencer] from sequencer] from the offsite power the offsite power system.
| |
| system.
| |
| BWOG STS BWOG STS 3.8.1-10 Rev. 3.1,12/01/05 Rev. 3.1, 12/01/05
| |
| | |
| TSTF-425, Rev. 3 AC Sources -- Operating AC Sources Operating 3.8.1 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.1.13 SR 3.8.1.13 ............................... NOTE..............................
| |
| -------------------------------NOTE------------------------------
| |
| This Surveillance
| |
| (( This Surveillance shall shall not not normally normally bebe performed performed MODE 11 or in MODE in or 2.
| |
| : 2. However, However, thisthis Surveillance Surveillance may may be be performed to performed to reestablish reestablish OPERABILITY OPERABILITY providedprovided an an assessment determines assessment determines the the safety safety of of the the plant plant is is maintained or maintained or enhanced.
| |
| enhanced. Credit Credit may may be be taken taken for for unplanned events unplanned events thatthat satisfy satisfy this this SR.
| |
| SR. 11 Verify each Verify each DG'sDG's noncritical noncritical automatic automatic trips trips are are bypassed on bypassed on [actual
| |
| [actual or or simulated simulated loss loss of of voltage voltage signal on signal on the the emergency emergency bus concurrent with bus concurrent with an an actual or actual or simulated simulated ESF SF actuation actuation signal].
| |
| signal].
| |
| BWOG STS BWOG STS 3.8.1-11 Rev. 3.1, Rev. 12/01/05 3.1,12/01/05
| |
| | |
| TSTF-425, Rev. 3 AC -
| |
| Sources - Operating AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY 3.8.1.14 SR 3.8.1.14 NOTES.............................
| |
| ------------------------------NOTES-----------------------------
| |
| ----------+-------------**--*-
| |
| I. Momentary
| |
| : 1. Momentary transients transients outside outside the the load load and and power factor power factor ranges ranges do do not not invalidate invalidate this this test.
| |
| test.
| |
| 2.
| |
| : 2. This Surveillance This Surveillance shall shall not not normally normally be be performed in performed MODE 1Ior in MODE or 2. 2. However, However, this this Surveillance may Surveillance may be be performed performed to to reestablish reestablish OPERABILITY provided OPERABILITY provided an an assessment assessment determines the determines the safetysafety of of the the plant plant is is maintained maintained or enhanced.
| |
| or enhanced. Credit Credit may may be be taken taken for for unplanned events unplanned events that that satisfy satisfy thisthis SR.
| |
| SR.
| |
| 3.
| |
| : 3. If performed If performed with with DC DC synchronized synchronized with with offsite offsite power, itit shall power, shall be be performed performed at at a a power power factor factor 5 [0.9].
| |
| [0.9].However, However, ifif grid grid conditions conditions do do not not permit, the permit, the powerpower factor factor limit limit is is not not required required to to be met.
| |
| be met. Under Under this this condition condition the the power power factor factor shall be shall be maintained maintained as as close close to to the the limit limit as as practicable.
| |
| practicable.
| |
| ----------------------+----------------------------------------------
| |
| /
| |
| Verify each Verify each DG DG operates operates for for 2 24 hours:
| |
| 2 24 hours: [I81 months a.
| |
| : a. For r [2]
| |
| For:2: hours loaded
| |
| [2] hours loaded :2: 2 [5250]
| |
| [5250]kW kW andand I
| |
| :::; [6000]
| |
| [6000]kW kW and and b.
| |
| : b. For the For the remaining remaining hours hours of of the the test test loaded loaded
| |
| :2:
| |
| 2 [4500]
| |
| [4500]kW kW and:::;
| |
| and I [5000]
| |
| [5000]kW. kW.
| |
| SWOG STS BWOG STS 3.8.1-12 Rev. 3.1,12/01/05 Rev. 3.1,12/01/05
| |
| | |
| TSTF-425, Rev. 3 AC Sources -- Operating AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.1.15 SR 3.8.1.15 NOTES
| |
| -~---------~---------~--------NOTES-~--------------------------
| |
| -----------dF-----------------
| |
| 1.
| |
| : 1. This Surveillance This Surveillance shall shall be be performed performed within within 55 minutes minutes of of shutting shutting down down the the DG DG after after the DG the DG has operated::::>:
| |
| has operated 2 [2] [2] hours hours loaded::::>:
| |
| loaded 2 [4500] [4500] kW kW and 5 [5000]
| |
| and [5000] kW. kW.
| |
| Momentary transients Momentary transients outside outside of of loadload range range dodo not invalidate not invalidate this this test.
| |
| test.
| |
| : 2. All DG starts may be preceded by an engine prelube period.
| |
| Verify each Verify each DG DG starts starts and and achieves:
| |
| achieves:
| |
| a.
| |
| : a. In 5 [10]
| |
| In:::; [lo] seconds, seconds, voltage::::>:
| |
| voltage 2 [3740] [3740] Vand V and frequency 2 [58.8]
| |
| frequency::::>: [58.8] Hz Hz and and b.
| |
| : b. Steady state Steady state voltage::::>:
| |
| voltage 2 [3740] [3740] V V and and 5 I [4580] V,
| |
| [4580] V, and frequency::::>:
| |
| and frequency 2 [58.8] [58.8] Hz Hz and and :-::; [61.2] Hz.
| |
| 5 [61.2] Hz.
| |
| SR 3.8.1.16 SR 3.8.1 .I6 ------------~------------------ NOTE
| |
| ------------+--------------+--- NOTE--------------~------------~--
| |
| ---------------------------+--
| |
| This Surveillance This Surveillance shall shall notnot normally normally be be performed performed in in MODE 1, MODE 1, 2, 2, 3, 3, oror 4. However, this
| |
| : 4. However, this Surveillance Surveillance may may be performed be performed to to reestablish reestablish OPERABILITY OPERABILITY provided provided an assessment an assessment determines determines the the safety safety of of thethe plant plant is is maintained or maintained or enhanced.
| |
| enhanced. Credit Credit may may be be taken taken for for unplanned events unplanned events that that satisfy satisfy this this SR. SR.
| |
| -----------------------------+----------------------------*----------
| |
| Verify each Verify each DG: DG: 6 8 1 months &
| |
| a.
| |
| : a. Synchronizes with Synchronizes with offsite offsite power power source source while while loaded with loaded with emergency emergency loads loads upon upon a a simulated simulated restoration of restoration offsite power, of offsite power, b.
| |
| : b. Transfers loads Transfers loads to to offsite offsite power power source, source, and and c.
| |
| : c. Returns to Returns to ready-to-Ioad ready-to-load operation. operation.
| |
| BWOG STS BWOG STS 3.8.1-13 Rev. 3.1, Rev. 3.1, 12/01/05 12/01/05
| |
| | |
| TSTF-425, Rev. 3 AC AC Sources -
| |
| Sources Operating w Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.1.17 SR 3.8.1.17 ...............................
| |
| -------------------------------NOTE ..............................
| |
| NOTE-------------------~----------
| |
| (( This This Surveillance Surveillance shall shall not not normally normally be be performed performed MODE 1, in MODE in I, 2, or 2, 3. However, or 3. However, portionsportions of of the the Surveillance may Surveillance may be be performed performed to to reestablish reestablish OPERABlLlTY provided OPERABILITY provided an an assessment assessment determines determines the safety the safety of of the the plant plant isis maintained maintained or or enhanced.
| |
| enhanced.
| |
| Credit may Credit may be be taken taken forfor unplanned unplanned events events that that satisfy this satisfy this SR.
| |
| SR.
| |
| -------------------------*------------------------+*-----------------
| |
| Verify, with Verify, with a connected to a DG DG operating to its operating in its bus, bus, an an actual in test actual or test mode mode and or simulated simulated ESF and ESF
| |
| §]month~._
| |
| ~~i,.D connected actuation signal actuation signal overrides overrides the the test test mode mode by: by:
| |
| a.
| |
| : a. Returning DG Returning DG to to ready-to-Ioad ready-to-load operation operation and and
| |
| [ b. Automatically
| |
| [b. energizing the Automatically energizing the emergency emergency load load from offsite from power. ))
| |
| offsite power.
| |
| SR 3.8.1.18 SR 3.8.1.18 ------------------------------NOTE------------------------------
| |
| ------------+-----------------
| |
| (( This This Surveillance Surveillance shall shall not not normally normally be performed be performed in MODE in MODE 1, 1, 2, 3, or 2, 3, However, this or 4. However, this Surveillance Surveillance may be may be performed performed to to reestablish reestablish OPERABILITY OPERABILITY provided an provided an assessment assessment determines determines the the safety safety of of the plant the plant is is maintained maintained or or enhanced.
| |
| enhanced. Credit Credit may may bebe taken for taken for unplanned unplanned events events thatthat satisfy satisfy this this SR. SR. ))
| |
| Verify interval Verify interval between between each each sequenced sequenced load load block block ~18) months ~ .
| |
| is within within +/- [lo% of k [10% of design design interval]
| |
| interval] for for each each is emergency [and emergency [and shutdown]
| |
| shutdown] load load sequencer.
| |
| sequencer. nseYfJ)
| |
| BWOG STS BWOG STS 3.8.1-14 3.1, 12/01/05 Rev. 3.1,12/01/05 Rev.
| |
| | |
| TSTF-425, Rev. 3 AC Sources -- Operating AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.1.19 SR 3.8.1.19 --+-+dd----+em--------------- NOTES-----------------------------
| |
| -----------------------------NOTES-----------------------------
| |
| : 1. All
| |
| : 1. All DG starts starts may may bebe preceded preceded by by an an engine engine prelube period.
| |
| prelube period.
| |
| 2.
| |
| : 2. This This Surveillance Surveillance shall shall not not normally normally be be performed in performed in MODE MODE 1. 1,2, 3, or 2, 3. or 4. However, However, portions of portions of the the Surveillance Surveillance may may bebe performed performed to reestablish to reestablish OPERABILITY OPERABILITY provided provided an an assessment determines assessment determines the the safety safety of of the the plant plant is maintained is maintained or or enhanced.
| |
| enhanced. CreditCredit may may be be taken for taken for unplanned unplanned events events that that satisfy satisfy this SR.
| |
| this SR.
| |
| /
| |
| Verify on Verify signal in signal on an an actual in conjunction actual or conjunction with or simulated simulated loss an actual with an loss of actual or of offsite offsite power or simulated simulated power [!;
| |
| [18] months ?..,,£._
| |
| 8] months f?, _,.....
| |
| ESF actuation ESF actuation signal: signal:
| |
| ~5erill a.
| |
| : a. De-energization of De-energization of emergency emergency buses.buses, b.
| |
| : b. Load shedding Load shedding from from emergency emergency buses,buses, c.
| |
| : c. DG auto-starts DG auto-starts from from standby standby condition condition and:
| |
| and:
| |
| : 1. Energizes permanently Energizes permanently connected connected loads loads in 5 in ~ [10] seconds,
| |
| [lo]seconds, 2.
| |
| : 2. Energizes auto-connected Energizes auto-connected emergency emergency loads through loads through [load
| |
| [load sequencer),
| |
| sequencer],
| |
| : 3. Achieves steady-state voltage;::.:
| |
| Achieves steady-state voltage 2 [3740]
| |
| [3740]V V and s and [4580] V,
| |
| ~ [4580] V, 4.
| |
| : 4. Achieves steady-state frequency Achieves steady-state frequency
| |
| ;::.: 158.81 Hz 2 [58.8) Hz and and ~s [61.2] Hz, and
| |
| [61.2] Hz, and 5.
| |
| : 5. Supplies permanently Supplies permanently connected connected and and auto-connected emergency auto-connected emergency loadsloads forfor 2 [5] minutes.
| |
| [5] minutes.
| |
| BWOG STS BWOG STS 3.8.1-15 Rev. 3.1,12/01/05 Rev. 3.1, 12/01/05
| |
| | |
| TSTF-425, Rev. 3 AC Sources -- Operating AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.1.20 -------------------------------NOTE------------------------------
| |
| All DG starts may be preceded by an engine prelube period.
| |
| Verify, when started simultaneously from standby [0 years ~._ _
| |
| condition, each DG achieves, in ::;; [10] seconds, voltage 2:: [3740] V and::;; [4580] V, and frequency a:n5eJI) 2:: [58.8] Hz and $ [61.2] Hz.
| |
| BWOG STS SWOG STS 3.8.1-16 3.1, 12/01/05 Rev. 3.1,12/01/05 Rev.
| |
| | |
| TSTF-425, Rev. 3 Diesel Fuel Diesel Fuel Oil, Oil, Lube Lube Oil, Oil, and and Starting Starting Air Air 3.8.3 3.8.3 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME Required Action F. Required F. Action and and F.11 Declare associated Declare associated DGDG Immediately Immediately associated Completion associated Completion inoperable.
| |
| inoperable.
| |
| Time not Time not met met.
| |
| One or One or more more DGs DGs with with fuel oil, diesel fuel diesel oil, lube lube oil, oil, or or starting air starting air subsystem subsystem not within not within limits limits forfor reasons other reasons other than than Condition A, Condition A, S,B, C, C, 0, D, E.
| |
| or E.
| |
| or SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.3.1 SR 3.8.3.1 Verify each Verify 2
| |
| ::0::
| |
| each fuel
| |
| [33,000] gal
| |
| [33,000]
| |
| fuel oil gal of oil storage of fuel.
| |
| storage tank fuel.
| |
| tank contains contains r31 i , days
| |
| @.1 days et.\3~
| |
| - - . -- --. - - - - - - - +
| |
| SR 3.8.3.2 SR 3.8.3.2 Verify lube Verify lube oil oil inventory inventory is is ::0:: [500] gal.
| |
| 2 [500] gal. )11 days ~I'~
| |
| ( \",.~~
| |
| SR 3.8.3.3 SR 3.8.3.3 Verify fuel oil Verify oil properties properties of of new new and and stored stored fuel fuel oil In accordance In accordance are tested are tested in in accordance accordance with, with, andand maintained maintained within within with the Diesel with the Diesel the limits the limits of, of, the the Diesel Diesel Fuel Fuel Oil Oil Testing Testing Program.
| |
| Program. Fuel Oil Fuel Oil Testing Testing Program Program SR 3.8.3.4 SR 3.8.3.4 Verify each Verify each DG DG airair start start receiver receiver pressure pressure isis r [225J
| |
| ::0:: psig.
| |
| [225] psig. 111 days (InserfJ)
| |
| SR 3.8.3.5 SR 3.8.3.5 Check for Check for and and remove remove accumulated accumulated water water from each from each [@1]dayS~~ £?'
| |
| fuel oil fuel oil storage storage tank.
| |
| tank. (1£§ e y- !; ;.L./
| |
| BWOG STS SWOG STS 3.8.3-2 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 DC Sources -- Operating DC Sources Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.4.1 SR 3.8.4.1 Verify battery Verify battery terminalterminal voltage voltage is is greater greater than than oror 7 days equal to to thethe minimum minimum established established float float voltage.
| |
| voltage.
| |
| C equal E
| |
| SR 3.8.4.2 SR 3.8.4.2 Verify each Verify each battery battery charger charger supplies supplies 2': [400] amps 2 [400] amps atat [I81 months greater than greater than or or equal equal to to the the minimum minimum established establistied float voltage float voltage for for 2'2: [8][8] hours.
| |
| hours.
| |
| Verify each Verify each battery battery charger charger can can recharge recharge the the battery battery to the to the fullyfully charged charged state state within within [24] [24] hours hours while while supplying the supplying the largest largest combinedcombined demands demands of of the the various continuous various continuous steady steady state state loads, loads, after after aa battery discharge battery discharge to to thethe bounding bounding design design basis basis event discharge event discharge state. state.
| |
| SR 3.8.4.3 SR 3.8.4.3 NOTES-----------------------------
| |
| ------------- -~------ ---------NOTES-----------------------------
| |
| -----------------+------------
| |
| : 1. The
| |
| : 1. The modified modified performance performance discharge discharge test test in in 3.8.6.6 may SR 3.8.6.6 SR may be be performed performed in in lieu lieu of of 3.8.4.3.
| |
| SR 3.8.4.3.
| |
| SR 2.
| |
| : 2. This Surveillance This Surveillance shall shall not not normally normally be be performed in performed in MODE MODE 1, 1, 2,2, 3, 3, or or 4.
| |
| : 4. However, However, portions of portions of thethe Surveillance Surveillance may may be be performed performed to reestablish to reestablish OPERABILITY OPERABILITY provided provided an an assessment determines assessment determines the the safety safety ofof the the plant plant is maintained is maintained or or enhanced.
| |
| enhanced. Credit Credit may may be be taken for taken for unplanned unplanned events events that that satisfy satisfy this SR.
| |
| this SR.
| |
| ---------------+-----------------------------------------------------
| |
| Verify battery Verify battery capacitycapacity is maintain in OPERABLE status, the required maintain in OPERABLE is adequate adequate to status, the to supply, supply, and required and
| |
| [I 81 months
| |
| [18] months ' \ )
| |
| 6 emergency loads emergency loads for for thethe design design duty duty cycle cycle when when (InSey-(D subjected to subjected to a a battery battery service service test. test.
| |
| BWOG STS BWOG STS 3.8.4-2 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Battery Parameters Battery Parameters 3.8.6 3.8.6 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME F. Required F. Required Action Action and and F.1 F.1 Declare associated Declare associated battery battery Immediately Immediately associated Completion associated Completion inoperable.
| |
| inoperable.
| |
| Time of Time of Condition Condition A,A, B, 6,
| |
| D, or C, D, C, or EE not not met.
| |
| met.
| |
| One [or One [or two] batter[y][ies two] batter[y][ies on one on one train]
| |
| train] with with one one oror more battery more battery cells cells float float voltage <
| |
| voltage < [2.07] V and
| |
| [2.07] Vand float current>
| |
| float [2] amps.
| |
| current > [2] amps.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.6.1 SR 3.8.6.1 -------------------------------NOTE..............................
| |
| -------------------------------NOTE------------------------------
| |
| Not required Not required to be met to be met when battery terminal when battery terminal voltage is voltage is less less than than the the minimum minimum established established float float voltage of voltage SR 3.8.4.1.
| |
| of SR 3.8.4.1.
| |
| Verify each Verify each battery battery float float current current is is :;:;
| |
| 5 [2] amps.
| |
| [2] amps. f!. days ~-----,._
| |
| SR 3.8.6.2 SR 3.8.6.2 Verify each Verify each battery battery pilot pilot cell cell voltage voltage is is 2'r: [2.07]
| |
| [2.07] V.
| |
| V. @.! days ,__ oL--- _
| |
| SR 3.8.6.3 SR 3.8.6.3 Verify each Verify each battery battery connected connected cell cell electrolyte electrolyte level level is is greater than greater than oror equal equal to to minimum minimum established established design limits.
| |
| design limits.
| |
| SR 3.8.6.4 SR 3.8.6.4 Verify each Verify each battery battery pilot pilot cell cell temperature temperature is is greater greater El days I?+---,
| |
| than or than or equal equal toto minimum minimum established established designdesign limits.
| |
| timits.
| |
| BWOG STS BWOG STS 3.8.6-3 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Battery Parameters 3.8.6 SURVEILLANCE FREQUENCY SR 3.8.6.5 Verify each battery connected cell voltage is
| |
| ~ [2.07] V.
| |
| ~2 days :-=-=~'-- __
| |
| SR 3.8.6.6 -------------------------------NOTE------------------------------
| |
| This Surveillance shall not be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.
| |
| Verify battery capacity is ~ [80%] of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.
| |
| 12 months when battery shows degradation, or has reached
| |
| [85]% of the expected life with capacity < 100%
| |
| of manufacturer's rating 24 months when battery has reached [85]% of the expected life with capacity
| |
| ~ 100% of manufacturer's manufactu rer's rating BWOG STS 3.8.6-4 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Inverters -- Operating Inverters Operating 3.8.7 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.7.1 SR 3.8.7.1 Verify correct inverter voltage, [frequency,) and alignment to alignment to required AC vital required AC buses.
| |
| vital buses. GdaYS~eY!J)
| |
| BWOG STS SWOG STS 3.8.7-2 Rev. 3.0, Rev. 3.0. 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Inverters - Shutdown Inverters , Shutdown 3.8.8 3.8.8 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A.2.2 A.2.2 Suspend movement Suspend movement of of Immediately Immediately
| |
| [recently] irradiated
| |
| [recently] irradiated fuel fuel assemblies.
| |
| assemblies.
| |
| A.2.3 A.2.3 Suspend operations Suspend operations Immediately Immediately involving positive involving positive reactivity reactivity additions that additions that could could result result in in loss of loss of required required SDM SDM or or boron concentration.
| |
| boron concentration.
| |
| A.2.4 A.2.4 Initiate action Initiate action to to restore restore lmmediately Immediately required inverters required inverters to to OPERABLE status.
| |
| OPERABLE status.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.8.1 SR 3.8.8.1 Verify correct inverter voltage, [frequency,] and alignments to alignments to required required AC vital buses.
| |
| AC vital buses.
| |
| BWOG STS BWOG STS 3.8.8-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Distribution Systems Distribution -
| |
| Systems ~ Operating Operating 3.8.9 3.8.9 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME D. Required D. Required Action Action andand D.l D.1 Be in Be in MODE MODE 3. 3. 6 hours 6 hours associated Completion associated Completion Time not Time not met.
| |
| met. AND D.2 D.2 Be in Be MODE 5.
| |
| in MODE 5. 36 hours 36 hours Two or E. Two or more more electrical electrical E.l E.1 L C 0 3.0.3.
| |
| Enter LCO Enter 3.0.3. Immediately Immediately power distribution power distribution subsystems inoperable subsystems inoperable that result that result in in aa loss loss of of function.
| |
| function.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE I FREQUENCY FREQUENCY SR 3.8.9.1 SR 3.8.9.1 Verify correct Verify correct breaker breaker alignments alignments and and voltage voltage to to ~days(- _
| |
| [required] AC,
| |
| [required] AC, DC, and AC DC, and distribution sUbsystems.
| |
| distribution subsystems.
| |
| vital bus AC vital bus electrical electrical power power
| |
| ~c-r-t1-;D SWOG STS BWOG STS 3.8.9-2 Rev. 3.1,12/01/05 Rev. 3.1, 12/01/05
| |
| | |
| TSTF-425, Rev. 3 Distribution Systems -- Shutdown Distribution Systems Shutdown 3.8.10 3.8.10 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A.2.4 A.2.4 Initiate actions Initiate actions to to restore restore Immediately Immediately required AC, required AC, DC, and AC DC, and AC vital bus vital bus electrical electrical power power distribution subsystems distribution subsystems to to OPERABLE status.
| |
| OPERABLE status.
| |
| A.2.5 A.2.5 Declare associated Declare associated lmmediately Immediately required decay required decay heat heat subsystem(s) removal subsystem(s) removal inoperable and inoperable and not in not in operation.
| |
| operation.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.8.10.1 SR 3.8.10.1 Verify correct Verify correct breaker breaker alignments alignments andand voltage voltage to to kdays f required AC, required and AC DC, and AC, DC, vital bus AC vital bus electrical electrical power power distribution subsystems.
| |
| distribution subsystems.
| |
| BWOG STS BWOG STS 3.8.10-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Boron Concentration Boron Concentration 3.9.1 3.9.1 3.9 REFUELING 3.9 REFUELING OPERATIONS OPERATIONS 3.9.1 3.9.1 Boron Concentration Boron Concentration LC0 3.9.1 LCO 3.9.1 Boron concentrations Boron concentrations of of the the Reactor Reactor Coolant Coolant System, System, the the refueling refueling canal, canal, and the and the refueling refueling cavity cavity shall shall be be maintained maintained within within the the limit limit specified specified in in the the COLR.
| |
| COLR.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODE 6.
| |
| MODE 6.
| |
| ----------------------------------------NOTE............................................
| |
| ---------------------------------------------NOTE--------------------------------------------
| |
| Only applicable Only applicable to to the the refueling refueling canal and refueling canal and refueling cavity cavity when when connected to connected to the the RCS.
| |
| RCS.
| |
| ACTIONS ACTIONS CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. Boron concentration A. Boron concentration not not A.1 Suspend CORE Suspend CORE Immediately Immediately within limit.
| |
| within limit. ALTERATIONS.
| |
| ALTERATIONS.
| |
| A.2 Suspend positive Suspend positive reactivity reactivity lmmediately Immediately additions.
| |
| additions.
| |
| AND A.3 Initiate action Initiate to restore action to restore Immediately Immediately concentration to boron concentration boron to within limit.
| |
| within limit.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS ~ --
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.9.1.1 SR 3.9.1.1 Verify boron concentration Verify boron concentration is is within the limit within the limit k 2 hou specified in specified in the COLR.
| |
| the COLR.
| |
| BWOG STS BWOG STS 3.9.1-1 3.9.1-1 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Nuclear Instrumentation Nuclear Instrumentation 3.9.2 3.9.2 3.9 REFUELING 3.9 OPERATIONS REFUELING OPERATIONS 3.9.2 3.9.2 Nuclear Instrumentation Nuclear Instrumentation L C 0 3.9.2 LCO 3.9.2 Two source Two source range range neutron neutron flux flux monitors monitors shall shall be be OPERABLE.
| |
| OPERABLE.
| |
| APPLICABILITY:
| |
| APPLICABILITY: MODE 6.
| |
| MODE 6.
| |
| ACTIONS ACTIONS CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. One [required]
| |
| A. One [required] source source A.l A.1 Suspend CORE Suspend CORE lmmediately Immediately range neutron range neutron flux flux ALTERATIONS.
| |
| ALTERATIONS.
| |
| monitor inoperable.
| |
| monitor inoperable.
| |
| AND AND A.2 A.2 Suspend operations Suspend operations that that lmmediately Immediately would cause would cause introduction introduction of of coolant into coolant into the the RCS RCS with with boron concentration boron concentration less less than required than required to to meet meet the the boron concentration boron concentration of of LC0 3.9.1.
| |
| LCO 3.9.1.
| |
| B. Two B. Two [required]
| |
| [required] source source B.11 Initiate action Initiate action toto restore restore one one lmmediately Immediately range neutron range neutron flux flux source range source range neutron neutron flux flux monitors inoperable.
| |
| monitors inoperable. monitor to monitor to OPERABLE OPERABLE status.
| |
| status.
| |
| AND 6.2 B.2 Perform SR Perform SR 3.9.1.1.
| |
| 3.9.1.I. Once per Once per 12 hours 12 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE I FREQUENCY FREQUENCY SR 3.9.2.1 SR 3.9.2.1 Perform CHANNEL Perform CHANNEL CHECK.
| |
| CHECK.
| |
| BWOG STS BWOG STS 3.9.2-1 3.9.2-1 Rev. 3.0. 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Nuclear Instrumentation Nuclear Instrumentation 3.9.2 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SURVEILLANCE I FREQUENCY SR 3.9.2.2 SR 3.9.2.2 ............................... NOTE..............................
| |
| -------------------------------NOTE------------------------------
| |
| Neutron detectors Neutron detectors are are excluded excluded from from CHANNEL CHANNEL CALIBRATION.
| |
| CALIBRATION.
| |
| -----*-*-+*----------------------------------------------------------
| |
| Perform CHANNEL Perform CHANNEL CALIBRATION. CALIBRATION.
| |
| STS BWOG STS SWOG 3.9.2-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Containment Penetrations Containment Penetrations 3.9.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.9.3.1 SR 3.9.3.1 Verify each Verify each required the required the required containment required status.
| |
| status.
| |
| containment penetration penetration is is in in
| |
| -7 days 3.9.3.2 SR 3.9.3.2 ------------------------------NOTE --------------------- ---------
| |
| ------------------------------NOTE------------------------------
| |
| Not required Not required toto be be met met for for containment containment purge and purge and exhaust valve(s) exhaust valve(s) in in penetrations penetrations closed closed to to comply comply with LCO with L C 0 3.9.3.c.1.
| |
| 3.9.3.c.1.
| |
| Verify each Verify each required required containment containment purge purge and and exhaust valve exhaust valve actuates actuates to to the the isolation isolation position position on on an actual an actual oror simulated simulated actuation actuation signal.
| |
| signal.
| |
| BWOG STS SWOG STS 3.9.3-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 DHR DHR andand Coolant Coolant Circulation -
| |
| Circulation - High High Water Water Level Level 3.9.4 ACTIONS ACTIONS (continued)
| |
| (continued)
| |
| CONDITION CONDITION REQUIRED REQUIRED ACTION ACTION COMPLETION TIME COMPLETION TIME A.4 A.4 Close Close equipment equipment hatch hatch and and 4 hours hours secure secure withwith [four]
| |
| [four] bolts.
| |
| bolts.
| |
| AND A.5 Close Close one one door door in in each each air air 44 hours hours lock.
| |
| lock.
| |
| A.6.1 A.6.1 Close Close eacheach penetration penetration 44 hours hours providing providing direct direct access access from from the the containment containment atmosphere atmosphere to to the the outside outside atmosphere atmosphere with with a a manual manual or or automatic automatic isolation isolation valve, valve, blind blind flange, flange, or or equivalent.
| |
| equivalent.
| |
| A.6.2 A.6.2 Verify each Verify each penetration penetration is is hours 4 hours capable of capable of being being closed closed byby an OPERABLE an OPERABLE Containment Purge Containment Purge and and Exhaust Isolation Exhaust Isolation System.
| |
| System.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.9.4.1 SR 3.9.4.1 Verify one Verify DHR loop one DHR is in loop is in operation operation and and circulating circulating % hours 6
| |
| @hour_s_oI-_ _.....
| |
| reactor coolant at a flow rate of 2 [2800] gpm.
| |
| reactor coolant at a flow rate of;::: (2800) gpm.
| |
| Ln5er-L1.
| |
| BWOG STS BWOG STS 3.9.4-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 DHR and DHR and Coolant Circulation -- Low Coolant Circulation Low Water Water Level Level 3.9.5 3.9.5 ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME B.5.2 B.5.2 Verify each Verify each penetration penetration is is 44 hours hours capable of capable being closed of being by closed by an OPERABLE an OPERABLE Containment Purge Containment Purge and and Exhaust Isolation Exhaust Isolation System.
| |
| System.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS -
| |
| SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.9.5.1 SR 3.9.5.1 Verify one Verify one DHR DHR loop loop is is in in operation.
| |
| operation. \E hoursh_-----.
| |
| 3.9.5.2 SR 3.9.5.2 SR Verify correct Verify correct breaker breaker alignment alignment and and indicated indicated power available power available to to the the required required DHR DHR pump pump that that is is not in not in operation.
| |
| operation.
| |
| BWOG STS BWOG STS 3.9.5-3 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Refueling Canal Refueling Canal Water Water Level Level 3.9.6 3.9.6 REFUELING OPERATIONS 3.9 REFUELING 3.9 OPERATIONS 3.9.6 3.9.6 Refueling Canal Refueling Water Level Canal Water Level LCO 3.9.6 Refueling canal Refueling canal water level shall water level shall be maintained r be maintained 23 ft
| |
| ~ 23 ft above above the the top top of of the reactor the reactor vessel vessel flange.
| |
| flange.
| |
| APPLICABILITY:
| |
| APPLICABILITY: During movement During movement of of irradiated irradiated fuel fuel assemblies assemblies within within containment containment.
| |
| ACTIONS ACTIONS CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A. Refueling cavity A. Refueling cavity water water A.l A.1 Suspend movement Suspend movement of of Immediately Immediately level not level not within limit.
| |
| within limit irradiated fuel irradiated fuel assemblies assemblies within containment within containment.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.9.6.1 Verify refueling canal water level is ~ 23 ft above the top of reactor vessel flange.
| |
| BWOG STS BWOG STS 3.9.6-1 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Programs and Programs and Manuals Manuals 5.5 5.5 5.5 5.5 Programs and Programs and Manuals Manuals 5.5.17 5.5.17 Batterv Monitoring Battery Monitoringandand Maintenance Maintenance Program Proqram This Program This Program provides provides for for battery battery restoration restoration and and maintenance, maintenance, based based on [the on [the recommendationsof recommendations of IEEE Standard 450-1995, IEEE Standard 450-7995, "IEEE "IEEE Recommended Recommended PracticePractice for Maintenance, for Maintenance,Testing, Testing, and and Replacement Replacementof of Vented Vented Lead-Acid Lead-Acid Batteries Batteries for for Stationary Applications,"
| |
| Stationary Applications," oror of of the the battery battery manufacturer]
| |
| manufacturer] including including the the following:
| |
| following:
| |
| a.
| |
| : a. Actions to Actions to restore restore battery battery cells cells with with float float voltage [2.13] V, voltage << [2.13] V, and and b.
| |
| : b. Actions to Actions to equalize equalize and and test test battery battery cells cells that that had had been been discovered discovered with with electrolyte level electrolyte level below below the the minimum minimum established established design design limit.
| |
| limit.
| |
| BWOG STS BWOG STS 5.5-18 Rev. 3.1,12/01/05 Rev. 3.1, 12/01/05
| |
| | |
| TSTF-425, Rev. 3 SDM SDM B 3.1.1 B 3.1.1 BASES BASES REQUIREMENTS (continued)
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE (continued) f.f. Samarium concentration, Samarium concentration, and and g.
| |
| : g. Isothermal temperature Isothermal temperature coefficient coefficient (lTC).
| |
| (ITC).
| |
| Using the Using the ITC ITC accounts accounts for for Doppler Doppler reactivity reactivity in in this this calculation calculation because because the reactor the is subcritical, reactor is subcritical, and and the the fuel fuel temperature temperature willwill be be changing changing at at the the same rate same rate as as the the RCS.
| |
| RCS.
| |
| a 2
| |
| [ -r ~ h eFrequency
| |
| [The Frequency of 24 hours of 24 hours is is based based onon the the generally generally slow slow change change in in required boron required boron concentration, concentration, and and also also allows allows sufficient sufficient time time for for the the operator to operator to collect collect the the required required data, data, which includes performing which includes performing a boron a boron concentration analysis, and complete the calculation.
| |
| concentration analysis, and complete the calculation.
| |
| 7 REFERENCES REFERENCES 1.
| |
| : 1. 10 CFR 10 CFR 50,50, Appendix Appendix A, GDC 26.
| |
| A, GDC 26. : ..,
| |
| 2.
| |
| : 2. FSAR, Chapter FSAR, Chapter [14].
| |
| [14].
| |
| I.ns erf "-
| |
| 3.
| |
| : 3. 10 CFR 100, 10 CFR 100. "Reactor Site Criteria."
| |
| "Reactor Site Criteria."
| |
| BWOG STS BWOG STS B 3.1.1-5 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Reactivity Balance Reactivity Balance B 3.1.2 B 3.1.2 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued) demonstrated, and demonstrated, and itit is is concluded concluded that that the reactor core the reactor core isis acceptable acceptable for for continued operation, continued operation, then then the the boron boron letdown letdown curve curve maymay be be renormalized, renormalized, and power and power operation operation may may continue.
| |
| continue. If If operational operational restrictions restrictions or or additional surveillance additional surveillance requirements requirements are are necessary necessary to to ensure ensure the the reactor reactor core is core is acceptable acceptable for for continued continued operation, operation, then then they they must must be be defined.
| |
| defined.
| |
| The required The required Completion Completion Time Time of of 7 7 days days is is adequate adequate for for preparing preparing operating restrictions operating restrictions or or surveillances surveillances that that may may be be required required to to allow allow continued reactor continued reactor operation.
| |
| operation.
| |
| If the If the core core reactivity reactivity cannot cannot be be restored restored to to within the 1 within the 1% limit, the
| |
| ~k/k limit,
| |
| % Aklk the unit unit must be must be brought brought to to aa MODE MODE in in which which the the LeOL C 0 does does not not apply.
| |
| apply. To To achieve this achieve this status, status, the the unit unit must must be be brought brought to to at at least least MODE MODE 3 3 within within 6 hours.
| |
| 6 hours. If If the the SDM SDM for MODE 3 for MODE 3 is is not not met, met, then then boration boration required required by by Action A.1 Required Action Required A.1 of LC0 3.1.1 of LCO 3.1.1 would would occur.occur. TheThe allowed allowed Completion Completion Time of Time 6 hours of 6 hours is is reasonable, reasonable, based based on on operating operating experience experience to to reach reach the required the required unitunit conditions conditions from from full full power power conditions conditions in in an an orderly orderly manner and manner and without challenging unit without challenging unit systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE SR 3.1.2.1 SR 3.1.2.1 REQUIREMENTS REQUIREMENTS Core reactivity Core reactivity isis verified verified byby periodic periodic comparisons comparisons of of measured measured and and predicted RCS predicted RCS boron boron concentrations.
| |
| concentrations. The The comparison comparison is is made made considering that considering that other other core core conditions conditions are are fixed fixed oror stable, stable, including including CONTROL ROD CONTROL positions, moderator ROD positions, moderator temperature, temperature, fuel fuel temperature.
| |
| temperature, fuel fuel depletion, xenon depletion, xenon concentration, concentration, and and samarium samarium concentration.
| |
| concentration. The The Surveillance is Surveillance is performed performed prior prior to to entering entering MODE MODE 11 as as an an initial initial check check on on core conditions core conditions and and design design calculations calculations at BOC. A at BOC. Note is A Note is included included in in the the SR to SR to indicate indicate that that the the normalization normalization of of predicted predicted corecore reactivity reactivity to to the the measured value measured value must must take take place place within within the the first 60 effective first 60 effective fullfull power power after each fuel loading. This allows days (EFPD) after each fuel loading. This allows sufficient time for days (EFPD) sufficient time for core core conditions to reach steady state, but prevents operation for a large conditions to reach steady state, but prevents operation for a large fraction of fraction of th~uel th fuel cyclecycle without establishing a without establishing a benchmark benchmark for for the the design design calculations. The calculations.
| |
| the initial the initial 60 slow rate slow 60 rate of k The required of core PD required subsequent PD after core reactivity subsequent Frequency after entering entering MODE reactivity changes changes due MODE 11 is due to Frequency of to fuel of 31 is acceptable, 31 EFPD, acceptable, based fuel depletion depletion and based on and the the following EFPD, following on the the presence of otherother indicators (QPT, etc.)
| |
| indicators (QPT, etc.) forfor prompt prompt indication indication of of anan anomaly.tAnother nother Note Note is is included included in in the the SRs SRs to to indicate indicate thatthat thethe performance e of of the the Surveillance Surveillance is is not not required required for for entry entry into MODE 2.
| |
| into MODE BWOG STS SWOG STS B 3.1.2-5 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 CONTROL ROD CONTROL ROD GroupGroup Alignment Alignment Limits Limits B 3.1.4 B 3.1.4 BASES BASES SURVEILLANCE SURVEILLANCE SR 3.1.4.1 SR 3.1.4.1 REQUIREMENTS REQUIREMENTS Verification that Verification that individual individual rods rods are are aligned aligned within within [6.5J%
| |
| [6.5]% of of their their group group average height average l i m i tat height limits s e t m ho hoyrFieque&llows re ue 1I0ws thethe operator operator to to detect detect a rod a rod that that isis beginning beginning to to deviate eviate fromfrom its its expected position. E h e ' - - - -
| |
| expected position./Ihe specified Frequency specified Frequency takes takes intointo account account other other rodrod position position information information that that is continuously is available to continuously available to the the operator operator in in the the control control room, room, so so that that during actual during actual rodrod motion, motion, deviations deviations can can immediately immediately be be detected.
| |
| detected.
| |
| IViSe-r f2 SR 3.1.4.2 Verifying each Verifying each CONTROL CONTROL ROD ROD is is OPERABLE OPERABLE would would require require thatthat each each rod be rod be tripped.
| |
| tripped. However, However, in in MODES MODES 1 Iand and 2, 2, tripping tripping each each CONTROL CONTROL ROD could ROD could result result in in radial radial tilts.
| |
| tilts. Exercising Exercising each each individual individual CONTROL CONTROL ROD~@~provides 2,&idprovides increased increased confidence confidence that that allall rods rods continue continue to bePE ABLE BLE without without exceeding exceeding the the alignment alignment limit,limit, even even ifif they they are are not regularly regularly tripped.
| |
| tripped. Moving Moving each each CONTROL CONTROL ROJl,..by RO by 3% 3% will will not not cause cause not radial or radial or axial takes into axial power power tilts, into consideration tilts, or consideration other or oscillations, oscillations, to other information to occur.lJ]le information available occur.
| |
| available to b to the 92 day e 92 day Frequency the operator Frequency operator in in the the takes control room control adds to adds room and to the and SR SR 3.1.4.1, the determination determination of which is 3.1.4.1, which of OPERABILITY is performed OPERABILITY of performed more of the more frequently freauently and rods.%etween the rods. \1l3etween and 4... ser
| |
| § required performances required performances of of SR SR 3.1.4.2 (determination of 3.1.4.2 (determination of CONTROL CONTROL ROD ROD OPERABILITY by OPERABILITY by movement),
| |
| movement), ifif a CONTROL ROD(S) a CONTROL ROD(S) is is discovered discovered to to bebe immovable, but immovable, but isis determined determined to to bebe trippable, trippable, the the CONTROL CONTROL ROD(S) ROD(S) is is considered to considered to be be OPERABLE.
| |
| OPERABLE. At any time, At any time, ifif a a CONTROL CONTROL ROD(S) ROD(S) is is immovable, a immovable, a determination determination of of the the trippability trippability (OPERABILITY)
| |
| (OPERABILITY) of of the the CONTROL ROD(S)
| |
| CONTROL ROD(S) must must be be made, made, and and appropriate appropriate action action taken.
| |
| taken.
| |
| SR 3.1.4.3 Verification of Verification of rod rod drop drop timetime allows allows the the operator operator to to determine determine that that the the maximum rod maximum rod drop drop time time permitted permitted is is consistent consistent with with thethe assumed assumed rod rod drop time drop time used used in in the the safety safety analysis.
| |
| analysis. The The rodrod drop drop timetime given given in in the the safety analysis safety analysis is is 1.4 seconds to 1.4 seconds to b insertion. Using b insertion. Using the the identical identical rodrod drop drop gives a curve gives curve a value value of of [1.66] seconds to
| |
| [1.66]seconds to % insertion. The 3/s insertion. The latter latter value value is is used in used in the the Surveillance Surveillance because because the the zone zone reference reference lights lights are are located located at at insertion intervals.
| |
| 25% insertion 25% intervals. The The zone zone reference reference lightslights willwill activate activate at at %%
| |
| insertion to insertion to give give an an indication indication of of the the rod rod drop drop time time and and rodrod location.
| |
| location.
| |
| Measuring rod Measuring rod drop drop times, times, prior prior to to reactor reactor criticality criticality after after reactor reactor vessel vessel head removal head removal and and after after CONTROL CONTROL ROD ROD drivedrive system system maintenance maintenance or or modification, ensures modification, ensures that that the the reactor reactor internals internals and and CRDM CRDM will will not not BWOG STS BWOG STS B 3.1.4-9 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Safety Rod Safety Rod Insertion Insertion Limit Limit B 3.1.5 B 3.1.5 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| If more If more than than one one safety safety rod rod is is inoperable inoperable thethe unit unit must must bebe brought brought to to aa MODE where MODE where the LC0 is the LCO is not not applicable.
| |
| applicable. The The allowed allowed Completion Completion Time of Time of 6 hours 6 is reasonable, hours is reasonable, basedbased on on operating operating experience, experience, for for reaching reaching the the required MODE required MODE from from full full power power conditions conditions in an orderly in an orderly manner manner andand without challenging without challenging plantplant systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE SR 3.1.5.1 SR 3.1S.1 REQUIREMENTS REQUIREMENTS Verification that Verification that each each safety safety rod rod is is fully fully withdrawn withdrawn ensures ensures the the rods rods are are available to provide reactor shutdown available to provide reactor shutdown capability. capability.
| |
| Verification that eerification that individual individual safety safety rod rod positions positions areare fully fully withdrawn withdrawn at a at a hour Frequency L 12Z hour Frequency allows allows the the operator operator toto detect detect a a rod rod beginning beginning toto deviate from deviate from itsits expected expected position.
| |
| position. Also, Also, the the 1212 hour hour Frequency Frequency takes takes I..
| |
| into account into account other purpose of purpose other information of monitoring information available monitoring the available in status of the status of the in the the control the safety control ~.b~
| |
| safety rods.
| |
| rods. ::== ~
| |
| REFERENCES 1. 10 CFR 50, Appendix A, GDC 10 and GDC 26. . _ ~ 2
| |
| : 2. 10 CFR 50.46. C2,~";""1~~=~~"" . . . ,,~"""/
| |
| 3.
| |
| : 3. FSAR, Section FSAR, Section (( J] .
| |
| BWOG STS BWOG STS B 3.1.5-4 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 APSR APSR Alignment Limits Alignment Limits B 3.1.6 B 3.1.6 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| The plant The plant must must be be brought brought to to a a MODE MODE in in which which the L C 0 does the LCO does not not apply apply ifif the Required the Required Actions associated Completion and associated Actions and Completion Times Times cannot be met.
| |
| cannot be met.
| |
| To achieve To achieve this this status, status, the the plant plant must must bebe brought brought to at least to at least MODE MODE 3 3 within within 6 6 hours.
| |
| hours. The The Completion Completion Time Time ofof 66 hours hours ;s is reasonable, reasonable, based based on on operating experience, operating experience, for for reaching reaching MODE MODE 3 3 from from RTP RTP inin an an orderly orderly manner and manner and without withaut challenging challenging plantplant systems.
| |
| systems. In MODE 3, In MODE 3, APSR group APSR group alignment limits alignment limits are are not not required required because because the the reactor reactor isis not not generating generating THERMAL POWER THERMAL POWER and and excessive excessive local LHRs cannot local LHRs cannot occur occur from from APSR APSR misalignment.
| |
| misalignment.
| |
| SURVEILLANCE SURVEILLANCE SR 3.1.6.1 SR 3.1.6.1 REQUIREMENTS REQUIREMENTS Verification~
| |
| ~ e r i f i c a t i o n ba 12 hour a 12 hour FrequencJthat
| |
| ~ r e ~ u e n c d hindividual individual at APSR positions are APSR positions are
| |
| [6.5]% of within [6.5]%
| |
| within of the the group group average average height height limits limits allows allows the the operator operator to to detect an detect an APSR beginning to APSR beginning to deviate deviate from from itsits expected expected position.
| |
| position. InIn addition, APSR addition, position is APSR position is continuously continuously available available to to the the operator operator inin the the control room control room so so that that during during actual actual rod rod motion, motion, deviations deviations cancan immediately immediately be detected.
| |
| be detected. [ j c <F~------------------~
| |
| 7 REFERENCES REFERENCES I. 10
| |
| : 1. 10 CFR CFR 50, 50, Appendix Appendix A, GDC 10 A, GDC I 0 and and GDCGDC 26.26. r=;
| |
| ~V1~e>,,+ 1.
| |
| 2.
| |
| : 2. 10 CFR 10 50.46.
| |
| CFR 50.46.
| |
| 3.
| |
| : 3. FSAR, Section FSAR, Section (( )) ..
| |
| 4.
| |
| : 4. FSAR, Section FSAR, Section (( )) ..
| |
| BWOG STS BWOG STS B 3.1.6-4 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Position Indicator Position lndicator Channels Channels B 3.1.7 B 3.1.7 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| Continuing to Continuing to verify verify the the rod rod positions positions every every 88 hours hours is is reasonable reasonable for for ensuring that ensuring that rod rod alignment alignment and and insertion insertion are are not not changing, changing, and and provides provides the operator the operator adequate adequate time time to to correct correct any any deviation deviation that that maymay occur.
| |
| occur. The The additional Completion additional Completion Time Time of of 11 hour hour after after motion motion of of nonindicating nonindicating rods, rods, which exceeds which exceeds 15 15 inches inches in in one one direction direction since since the the last last determination determination of of the rod's the rod's position, position, ensures ensures thatthat the the rod rod with with inoperable inoperable position position indication indication will not will not be be misaligned misaligned for for aa significant significant period period of of time, time, in in the the event event the the rodrod is moved.
| |
| is moved. The The specified specified Completion Completion TimesTimes areare acceptable acceptable because because the the simultaneous occurrence simultaneous occurrence of of aa mispositioned mispositioned rod rod and and an an event event sensitive sensitive to to the rod the rod position position hashas a a small small probability.
| |
| probability.
| |
| If both If both the the absolute absolute position position indicator indicator channel channel andand relative relative position position indicator channel indicator channel are are inoperable inoperable for for one one oror more more rods, rods, or or ifif the the Required Required Actions and associated Actions and associated Completion Completion Times Times are are not not met.
| |
| met, thethe position position of of the the rod(s) is rod(s) is not not known known withwith certainty.
| |
| certainty. Therefore, Therefore, each each affected affected rod rod must must be be declared inoperable, declared inoperable, and and the the limits limits of L C 0 3.1.4 or of LCO or LCO 3.1.6 apply.
| |
| L C 0 3.1.6 apply. The The required Completion required Completion Time Time for for declaring declaring the rod(s) inoperable the rod(s) inoperable is is immediately. Therefore immediately. Therefore LCO L C 0 3.1.4 or LCO 3.1.4 or L C 0 3.1.6 3.1.6 isis entered entered immediately, immediately, and the and the reqUired required Completion Completion Times Times forfor the the appropriate appropriate Required Required Actions Actions in those in LCOs apply those LCOs apply without without delay.
| |
| delay.
| |
| SURVEILLANCE SURVEILLANCE SR 3.1.7.1 SR 3.1.7.1 REQUIREMENTS REQUIREMENTS Verification is Verification is required required that that the the Absolute Position Indicator Absolute Position lndicator channels channels and and Relative Position Relative Position Indicator lndicator channels channels agreeagree within within the the limit limit given given in in the the COLR. This COLR. This verification verification ensures ensures thatthat the the Relative Relative Position Position Indicator lndicator channels, which channels, which areare regarded regarded as as the the potentially potentially less less reliable reliable meansmeans of of position indication, position indication, remain remain OPERABLE OPERABLE and and accurate.
| |
| accurate. (Ihe E h e required required Frequency of Frequency of 12 hours is 12 hours is adequate adequate for for verifying verifying that that no no degradation degradation in in system OPERABILITY has system OPERABILITY has occurred. ~ occurred.
| |
| Ii\5 e ,{ ~ 3J BWOG STS BWOG STS B 3.1.7-6 Rev. 3.0, Rev. 3.0, 03/31/04 03131104
| |
| | |
| TSTF-425, Rev. 3 PHYSICS TESTS PHYSICS Exceptions -- MODE TESTS Exceptions MODE 11 3.1.8 B 3.1.8 BASES BASES SURVEILLANCE SURVEILLANCE SR 3.1.8.1 SR 3.1.8.1 REQUIREMENTS REQUIREMENTS 85% RTP I
| |
| Verification that Verification that THERMAL THERMAL POWER POWER is is :s; 5 85% RTP ensures ensures that that the the required additional required additional thermal therma~argin argin hashas beenbeen established established priorprior to to and and during PHYSICS during PHYSICS TESTS.
| |
| allows the allows the operator established TESTS. he operator adequa thermal adequa e margin 7 he required during required Frequency e time time to Frequency of to determine determine any PHYSICS established thermal margin during PHYSICS TESTS. ~.5~~
| |
| of once once per any degradation TESTS.
| |
| per hour degradation of hour of the the SR 3.1.8.2 Verification that Verification that Fo(Z)
| |
| F&) and and FF~TH ~are are within within theirtheir limits limits ensures ensures that that core core local linear local linear heat heat rate rate and and departure departure fromfrom nucleate nucleate boiling boiling ratio ratio will will remain remain within their within their limits, limits, while while one one oror more more of of the the LCOs LCOs that that normally normally control control these design these design limits limits are are out out of of specification.
| |
| specification. llhe E h e required required Frequency Frequency of of 22 hours hours allows allows the the operator operator adequate adequate time time forfor collecting collecting a a flux flux map map and and
| |
| ~~. for for performing performing the the hot hot channel channel factor factor verifications, verifications, based based on on operating operating
| |
| \~rtSel"- 2.,,".~~~e..erienc . If If SR 3.2.5.1 is not met, PHYSICS SR 3.2.5.1 is not met, PHYSICS TESTS are suspendedTESTS are suspended
| |
| . -.----~.... and reO ~.5 applies. This
| |
| .5 applies. This Frequency Frequency is is more more conservative conservative than than the the Completion Time Completion Time for for restoration restoration of of the the individual individual LCOs that preserve LCOs that preserve the the F&) and FQ(Z) and F limits.
| |
| : H limits.
| |
| F~
| |
| This SR This SR isis modified modified by by a a Note Note that that requires requires performance performance only only whenwhen THERMAL POWER THERMAL POWER is is greater greater than 20% RTP.
| |
| than 20% RTP. ThisThis establishes establishes a a performance requirement performance requirement that that is is consistent consistent with with the the Applicability Applicability of of 3.2.5, "Power L C 0 3.2.5, LeO "Power Peaking Peaking Factors."
| |
| Factors."
| |
| SR 3.1.8.3 Verification that Verification that the the nuclear nuclear overpower overpower trip trip setpoint setpoint is is within within thethe limit limit specified for specified for each each PHYSICS PHYSICS TEST TEST ensures ensures that that core core protection protection at at the the reduced power reduced power level level is is established established and and will remain in will remain in place place during during thethe PHYSICS TESTS.
| |
| PHYSICS ~ ~ ~ ~[ferforming
| |
| ~ . @ - fthe the o verification verification r m i n ~once once every every 88 hours hours allows allows the operator operator adequate adequate time time for for determining determining any any degradation degradation of of the the the established trip established setpoint margin trip setpoint margin before before andand during during PHYSICS PHYSICS TESTS TESTS and and for adjusting for adjusting thethe nuclear nuclear overpower overpower trip trip setpoint.
| |
| setpoint.- f--....._----,,..-_.
| |
| Q=ns~i7)
| |
| BWOG STS BWOG STS B 3.1.8-6 Rev. 3.0, Rev. 03/31/04 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 PHYSICS TESTS PHYSICS TESTS Exceptions - MODE 1 Exceptions ~ MODE 1 BB 3.1.8 3.1.8 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)
| |
| (continued)
| |
| SR 3.1.8.4 SDM is The SOM The is verified verified by by performing performing a a reactivity reactivity balance balance calculation, calculation, considering the considering the following following reactivity reactivity effects:
| |
| effects:
| |
| a.
| |
| : a. Reactor Coolant Reactor Coolant System System (RCS)
| |
| (RCS) boron boron concentration, concentration, b.
| |
| : b. CONTROL ROD position, CONTROL position, c.
| |
| : c. Doppler defect, Doppler defect, d.
| |
| : d. Fuel burnup Fuel burnup based based on on gross gross thermal thermal energy energy generation, generation, e.
| |
| : e. Samarium concentration, Samarium concentration, f.
| |
| : f. Xenon concentration, Xenon concentration, and and g.
| |
| : g. Moderator defect.
| |
| Moderator defect.
| |
| Frequency of C h e Frequency
| |
| [!he of 24 hours is 24 hours is based based on on the generally slow the generally slow change change in in required boron required boron concentration concentration and and on on the the low low probability probability of an accident of an accident occurring without occurring without the the required required SDM.
| |
| SDM. --.-
| |
| REFERENCES REFERENCES I.
| |
| : 1. CFR 50, 10 CFR 10 50, Appendix Appendix B, B, Section Xi.
| |
| Section XI.
| |
| 2.
| |
| : 2. 10 CFR 10 50.59.
| |
| CFR 50.59.
| |
| : 3. Regulatory Guide
| |
| : 3. Regulatory Guide 1.68, 1.68, Revision 2, August Revision 2, 1978.
| |
| August 1978.
| |
| : 4. ANSIIANS-19.6.1-1985, ANSI/ANS-19.6.1-1985, December December 13, 13, 1985.
| |
| 1985.
| |
| 5.
| |
| : 5. FSAR, Section FSAR, Section [13.4.8].
| |
| [ I 3.4.81.
| |
| 6.
| |
| : 6. FSAR, Section FSAR, Section [13.4.8],
| |
| [13.4.8], [Tables 13-3 and
| |
| [Tables 13-3 and 13-4, 13~4, Am. 49, Am. 49, Se~tember30, September 30, 1976].
| |
| 19761.
| |
| BWOG STS BWOG STS B 3.1.8-7 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 PHYSICS TESTS PHYSICS Exceptions -- MODE TESTS Exceptions MODE 2 2 3.1.9 B 3.1.9 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued) specification, in specification, in order order to to ensure ensure that that continuity continuity ofof reactor reactor operation operation is is within initial condition within initial condition limits.
| |
| limits. This This required required ,Completion Completion TimeTime is is consistent consistent with, with, oror more more conservative conservative than, than, those those specified specified forfor the the individual individual LCOs LCOs addressed by addressed by PHYSICS PHYSICS TESTS TESTS exceptions.
| |
| exceptions.
| |
| If the If the nuclear nuclear instrumentation instrumentation high high startup startup rate rate CONTROL CONTROL ROD ROD withdrawal inhibit withdrawal inhibit function function is is inoperable, inoperable, then hour is then 1I hour is allowed allowed for for the the operator to operator to restore restore thethe function function toto OPERABLE OPERABLE status status or or to to complete complete an an orderly suspension orderly suspension of of PHYSICS PHYSICS TESTS TESTS exceptions.
| |
| exceptions. Suspension Suspension of of PHYSICS TESTS PHYSICS TESTS exceptions exceptions requires requires restoration restoration of of each each of of the the applicable individual applicable individual LCOs LCOs to to within within specification.
| |
| specification. ThisThis required required Completion Time Completion Time isis consistent consistent with, with, oror more more conservative conservative than, than, those those specified for specified for the the individual individual LCOs LCOs addressed addressed by by PHYSICS PHYSICS TESTS TESTS exceptions.
| |
| exceptions.
| |
| The nuclear The nuclear instrumentation instrumentation high high startup startup rate rate CONTROL CONTROL ROD ROD withdrawal withdrawal inhibit function inhibit function is is not not required required when when the the reactor reactor power power level level isis above above the the operating range operating range of of the the instrumentation instrumentation channel.
| |
| channel. For For example, example, if if the the reactor power reactor power levellevel is above the is above the source source range range channel channel operating operating range,range, then only then only the the intermediate intermediate rangerange highhigh startup startup rate rate CONTROL CONTROL ROD ROD withdrawal inhibit withdrawal inhibit isis required required to to be be functional.
| |
| functional.
| |
| SURVEILLANCE SURVEILLANCE REQUIREMENTS REQUIREMENTS ----------
| |
| Perfo ing a CHANNEL FUNCT NAL TEST on each n lear
| |
| <eJAonc. t ins mentation source and int mediate range high st up rate NTROL ROD withdrawal' hibit and nuclear over wer channel, Loy-(ed-Io"" ensures that ensures that thethe instrume instru ation required to detec deviation from THERMAL POWER or detect a high startup r e is OPERABLE.
| |
| De:.sc-r,*~,::d ~I(
| |
| Performing the test 0 e within 24 hours, prio 0 initiating PHYSICS/
| |
| dcX<. not e("_~'f '7 TESTS, ensures t t the instrumentation is PERABLE shortly b~re, PHYSICS TEST begin and allows the 0 eratorr to to correct correct anyan /
| |
| instrumentat; pr~ ..L..
| |
| SR 3.1.9.~(j)
| |
| Verification that Verification that THERMAL THERMAL POWER POWER is:5 is 5 5%
| |
| 5% RTPRTP ensures ensures thatthat anan adequate margin adequate and the and for the for margin is the nuclear the operator operator to is maintained nuclear overpower maintained between,.ttJe overpower trip to determine trip setpoint.
| |
| determine any t
| |
| between e THERMAL setpoint. \!:!£>urly any change change in THERMAL POWER Hourly verification in core POWER level verification is core conditions, conditions, such such as level is adequate adequate as xenon redistribution xenon redistribution occurring occurring after after a a THERMAL THERMAL POWER POWER reduction, reduction, that that could cause THERMAL POWER to exceed could cause THERMAL POWER to exceed the specified limit~~@ the specified limit.
| |
| h
| |
| ,e BWOG STS BWOG STS 3.1.9-5 B 3.1.9-5 3.0, 03/31/04 Rev. 3.0, Rev.
| |
| | |
| TSTF-425, Rev. 3 PHYSICS TESTS PHYSICS TESTS Exceptions -
| |
| Exceptions - MODEMODE 2 2 B 3.1.9 B 3.1.9 BASES BASES REQUIREMENTS (continued)
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE (continued)
| |
| SR 3.1.9.{j)r(j)
| |
| Verification that Verification that the the nuclear nuclear overpower overpower trip trip setpoint setpoint isis within the limit within the limit specified for specified for PHYSICS PHYSICS TESTS TESTS ensures ensures that that core core protection protection atat the the reduced power reduced the operator the power leve PHYSICS TESTS.
| |
| PHYSICS operator adequa established trip established for adjusting adequa ec leve~isis established established and TESTS. Performing Performing the e time time for setpoint margin trip setpoint the nuclear margin before overpower and will before and trip for adjusting tfl~:uclear overpower trip setpoint. ~;~
| |
| will remain the verification remain in verification once for determinrng determining any in place place during any degradation and during degradation of during per 88 hours once per hours allows PHYSICS TESTS during PHYSICS setpoint.
| |
| of the allows the TESTS and Q) and 3.1.S@Yfj1 SR 3.1.9()"1.J/
| |
| SR The SDM The SDM is is verified verified by by performing performing a a reactivity reactivity balance balance calculation, calculation, considering the considering the following following reactivity reactivity effects:
| |
| effects:
| |
| a.
| |
| : a. RCS boron RCS boron concentration, concentration, b.
| |
| : b. CONTROL ROD CONTROL ROD position, position, c.
| |
| : c. RCS average RCS average temperature, temperature, d.
| |
| : d. Fuel burnup Fuel burnup based based on on gross gross thermal thermal energy energy generation, generatian, e.
| |
| : e. Samarium concentration, Samarium concentration, f.
| |
| : f. Xenon concentration, Xenon concentration, g.
| |
| : g. Isothermal temperature Isothermal temperature coefficient coefficient (fTC),
| |
| (ITC), when when below below the the point point of of adding heat adding (POAH),
| |
| heat (POAH),
| |
| h.
| |
| : h. Moderator defect, Moderator defect, when above the when above the POAH, POAH, and and i.i. Doppler defect, Doppler defect, when when above above the the POAH.
| |
| POAH.
| |
| Using the Using the ITC ITC accounts accounts for for Doppler Doppler reactivity reactivity in in this this calculation calculation when when the the reactor is reactor is subcritical subcritical oror critical critical but but below below the the POAH, POAH, and and the the fuel fuel temperature will temperature will be be changing changing at at the the same same rate rate as as the RCS.
| |
| the RCS.
| |
| G h e Frequency
| |
| [Ihe Frequency of 24 hours of 24 hours is is based based on on the the generally generally slow slow change change in in required boron required boron concentration occurring without occurring concentration and without thethe required and on required SDM.
| |
| on the SDM. f ---
| |
| the lowlow probability probability of
| |
| ~'--~*cr~~~!:r~_.~
| |
| of an an accident accident BWOG STS BWOG STS B 3.1.9-6 B 3.1.9-6 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Regulating Rod Regulating Rod Insertion Insertion Limits Limits B 3.2.1 B 3.2.1 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| If the If the regulating regulating rods rods cannot cannot be be restored restored toto within within thethe acceptable acceptable operating limits operating limits forfor thethe original original THERMALTHERMAL POWER, POWER, or or if if the the power power reduction cannot reduction cannot be be completed completed within the required within the required Completion Completion Time, Time, then then the reactor the reactor is is placed placed in MODE 3, in MODE 3, in in which which this this LCO LC0 doesdoes notnot apply.
| |
| apply. This This Action ensures Action ensures that that the the reactor reactor does does notnot continue continue operating operating in in violation violation of of the peaking the peaking limits, limits, the the ejected ejected rod rod worth, worth, the the reactivity reactivity insertion insertion rate rate assumed as assumed as initial initial conditions conditions in in the the accident accident analyses, analyses, or or the the required required minimum SDM minimum SDM assumed assumed in in the the accident accident analyses.
| |
| analyses. The The required required Completion Time Completion Time of of 6 6 hours hours is is reasonable, reasonable, basedbased on on operating operating experience regarding experience regarding the the amount amount of of time time required required to to reach reach MODEMODE 33 from from RTP without RTP without challenging challenging plant plant systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE 3.2.1.1 SR 3.2.1.1 SR REQUIREMENTS REQUIREMENTS This Surveillance This Surveillance ensures ensures that that the the sequence sequence and and overlap overlap limits limits are are not not violated. § violated. Surveillance Surveillance Frequency Frequency of of 12 12 hours hours is is acceptable acceptable becausebecause little rod little rod motion motion occurs occurs in in 12 12 hours hours due due toto fuel burnup and fuel burnup and thethe probability probability of a of a deviation deviation occurring occurring simultaneously simultaneously with with an an inoperable inoperable sequence sequence monitor in monitor in this this relatively relatively short short time time frame frame isis low.*
| |
| low. - Also, the Frequency Also, the Frequency takes intointo account account other other information information availableavailable in in the the control control roomroom forfor takes monitoring the monitoring the status status of of the the regulating regulating rods. rods. -< @&+I
| |
| ~nS~tz.)
| |
| SR 3.2.1.2 With an With an OPERABLE OPERABLE regulating regulating rod rod insertion insertion limit limit alarm, alarm, verification verification of of the the regulating rod regulating rod insertion insertion limits limits as as specified specified inin the the COLR COLR et ~.illd~QD 00 o
| |
| m2d'i9k?*is
| |
| % ? $ i s sufficient sufficient to to ensure ensure the the OPERABILITY OPERABILITY of of the the regulating regulating rodrod insertion limit insertion limit alarm alarm and and to to detect detect regulating regulating rod rod banks banks thatthat maymay be be
| |
| .[The F("'1!1~1(nl? approaching the approaching the -ecause rou insertion limits ecause little little rod rod motion motion due due toto I'.s, c:r-ffVClf (;/1 +c:..~._
| |
| burnup occurs fuel burnup fuel occurs in in 12 12 hours.
| |
| hours. Also, the Frequency Also, the Frequency takes takes intointo account account other information other information available available in in the the control control room room for for monitoring monitoring the the status status of of the regulating the regulating rodS'~ r o ds.
| |
| It15e r "Q)
| |
| BWOG STS SWaG STS B 3.2.1-8 83.2.1-8 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 APSR Insertion APSR Insertion Limits Limits 3.2.2 B 3.2.2 B
| |
| BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| IfIf the the APSRs APSRs cannot cannot be be restored restored to to their their intended intended positions positions within within the the required Completion required Completion Time Time of 24 hours, of 24 hours, thethe reactor reactor must must be be plQ.((ed p l a e d in in MODE 3, MODE 3, in in which which this this LCO L C 0 does does notnot apply.
| |
| apply. This This action action ensures ensures thatthat the the fuel does fuel does notnot continue continue to to bebe depleted depleted in in an an unintended unintended burnupburnup distribution. The distribution. The required required Completion Completion Time Time of of 66 hours hours is is reasonable, reasonable, based on based on operating operating experience experience regarding regarding the the time time required required to to reach reach MODE 33 from MODE from RTP RTP in in an an orderly orderly manner manner and and without without challenging challenging plantplant systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE 3.2.2.1 SR 3.2.2.1 SR REQUIREMENTS REQUIREMENTS Fuel cycle Fuel cycle designs designs that that allow allow APSR APSR withdrawal withdrawal near near EOC EOC do do not not permit permit reinsertion of reinsertion of APSRs APSRs afterafter the the time time ofof withdrawal.
| |
| withdrawal. When When the the plant plant computer is computer is OPERABLE, OPERABLE, the the operator operator willwill receive receive aa computer computer alarmalarm ifif the the APSRs sert after APSRsjcsert ' after that that time time inin core core life life when when thethe APSR APSR withdrawal withdrawal occurs-Gerificationthat occurs.(yerification that the the APSRs APSRs are are within within their their insertion insertion limits limits atat aa 12 hour 12 hour Frequency Frequency is is sufficient sufficient toto ensure ensure thatthat the the APSR APSR insertion insertion limits limits are preserved are preserved and and the the computer computer alarmalarm remains remains OPERABLE.
| |
| OPERABLE. The The 12 hour 12 hour Frequency Frequency required required forfor performing performing this this verification verification is is sufficient sufficient because APSRs because APSRs are are positioned positioned by by manual manual control control and and areare normally normally moved infrequently.
| |
| moved infrequently. The The probability probability of of aa deviation deviation occurring occurring simultaneously with simultaneously with anan inoperable inoperable computer computer alarm alarm isis low low inin this this relatively relatively short time short time frame.
| |
| frame. Also, Also, thethe Frequency Frequency takes takes into into account account otherother information available information available inin the the control control room room for for monitoring monitoring the the axial axial power power distribution in the reactor core. ~-_., ... '-_._
| |
| REFERENCES REFERENCES 1.
| |
| : 1. 10 CFR 10 CFR 50, 50, Appendix Appendix A, GDC 10 A, GDC 10 andand GDC GDC 26. 26. InSf~,~""
| |
| 2.
| |
| : 2. 10 CFR 10 CFR 50.46.
| |
| 50.46.
| |
| 3.
| |
| : 3. FSAR, Chapter FSAR, Chapter (( )) ..
| |
| 4.
| |
| : 4. FSAR, Chapter FSAR, Chapter (( ].].
| |
| BWOG STS BWOG STS B 3.2.2-5 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 AXlAL POWER IMBALANCE AXIAL POWER IMBALANCE Operating Operating Limits Limits B 3.2.3 B 3.2.3 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)(continued) the central the central region region ofof the the core core where where the the neutron neutron flux flux tends tends to be higher.
| |
| to be higher. ItIt also helps also helps prevent prevent measuring measuring anan AXlAL POWER IMBALANCE AXIAL POWER IMBALANCE that that isis excessively large excessively large when when the the reactor reactor is is operating operating at at low low THERMAL THERMAL POWER levels.
| |
| POWER levels. The The third third requirement requirement forfor placement placement of of detectors (i.e.,
| |
| detectors (Le.,
| |
| radial asymmetry) radial asymmetry) reduces reduces uncertainty uncertainty byby measuring measuring the the neutron flux at neutron flux at core locations core locations that that are are not not radially radially symmetric.
| |
| symmetric.
| |
| ci SR 3.2.3.1 SR 3.2.3.1
| |
| ~erification Verification of of the the AXlAL POWER IMBALANCE AXIAL POWER IMBALANCE indication indication every 12 hours every 12 hours
| |
| ~nsures nsures that that the the AXIAL POWER IMBALANCE AXIAL POWER IMBALANCE limitslimits are are not not violated violated and and takes into takes into account account other other information information and and alarms alarms available available to to the the operator operator in the in the control control room.
| |
| room. This This Surveillance Surveillance Frequency Frequency is is acceptable acceptable because because the mechanisms the mechanisms that that can can cause cause AXIAL AXlAL POWER POWER IMBALANCE, IMBALANCE, such such as as xenon redistribution xenon redistribution oror CONTROL CONTROL ROD ROD drive drive mechanism mechanism malfunctions malfunctions that cause that cause slow slow AXlAL POWER IMBALANCE AXIAL POWER IMBALANCE increases, increases, cancan bebe discovered by discovered by the the operator operator before before the the specified specified limits limits are are violated.
| |
| violated.
| |
| REFERENCES REFERENCES 1.
| |
| : 1. 10 CFR 50.46.
| |
| 10 CFR 50.46.
| |
| 2.
| |
| : 2. FSAR, Chapter FSAR, Chaater [15].
| |
| 1151.
| |
| BWOG STS SWOG STS B 3.2.3-7 Rev. 3.0, Rev. 03/31/04 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 QPT QPT B 3.2.4 B 3.2.4 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| SR 3.2.4.1 SR 3.2.4.1 6 Checking the lChecking lietermine System inputs System the QPT etermine whether inputs for indication every QPT indication whether the the plant for monitoring monitoring QPT every 7 plant computer 7 days days ensures computer software QPT are ensures that software and are functioning that the and Incore the operator operator can lncore Detector functioning properly properly and Detector and takes can takes into into account other account other information information and and alarms alarms available available to to the the operator operator in the in the control room.
| |
| control room. ThisThis procedure procedure allows allows the QPT mechanisms, the QPT mechanisms, such such as as xenon redistribution, xenon burnup gradients, redistribution, burnup gradients, andand CONTROL CONTROL ROD ROD drive drive mechanism malfunctions, mechanism malfunctions. which can cause which can cause slow develo~rnentof slow development of aa QPT, QPT, to be to be detected. operating experience has confirme he acce tability of a detected. Operating Surveillance Frequency Surveillance Frequency of 7 days.
| |
| of 7 days. . ( - - - - Inser Following restoration Following restoration of of the the QPT QPT to to within within the the steady steady state state limit, limit, operation operation at ~
| |
| at 95% RTP r 95% RTP may may proceed proceed provided provided thethe QPT QPT isis determined determined to to remain remain within the within the steady steady state state limit limit at at the the increased increased THERMAL THERMAL POWER POWER level. level. In In case QPT case QPT exceeds exceeds the the steady steady state state limit limit for for more more than than 2424 hours hours or or exceeds the exceeds the transient transient limit (Condition A, limit (Condition B, or A, B, D), the or D), the potential potential forfor xenon xenon redistribution is redistribution is greater.
| |
| greater. Therefore, Therefore, the the OPT QPT isis monitored monitored for for 12 consecutive 12 consecutive hourly hourly intervals intervals toto determine determine whether whether thethe period period of of any any oscillation due oscillation due to to xenon xenon redistribution redistribution causes causes thethe OPT QPT to to exceed exceed the the steady state steady state limit limit again.
| |
| again.
| |
| REFERENCES REFERENCES 1
| |
| : 1. 10 CFR 10 CFR 50.46.
| |
| 50.46.
| |
| 2.
| |
| : 2. FSAR, Section FSAR, Section (( )) .
| |
| 3.
| |
| : 3. ANSI N18.2-1973, American ANSI N18.2-1973, National Standards American National Standards Institute, Institute, August 6, August 6,1973.
| |
| 1973.
| |
| 4.
| |
| : 4. 10122A, Rev.
| |
| BAW 10122A, BAW Rev. 1, I,May 1984.
| |
| May 1984.
| |
| BWOG STS BWOG STS B 3.2.4-10 Rev. 3.0, Rev. 3.0,03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RPS Instrumentation RPS Instrumentation BB 3.3.1 3.3.1 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| If the If the Required Required ActionAction andand associated associated Completion Completion Time Time of of Condition Condition A A or B or B are are not not met met and and Table Table 3.3.1-1 3.3.1-1 directs directs entry entry into into Condition Condition G, the unit G, the unit must be must be brought brought to to aa MODE MODE in in which which thethe specified specified RPS RPS trip trip Function Function is is not required not required to to be be OPERABLE.
| |
| OPERABLE. To To achieve achieve this this status, status, THERMAL THERMAL ~
| |
| POWER must POWER must be be reduced reduced < [15]% RTP.
| |
| < [15J% RTP. The The allowed allowed Completion Completion Time Time of of 6 hours 6 hours is is reasonable, reasonable, based based onon operating operating experience, experience, to to reach reach
| |
| [15]% RTP
| |
| [15J% RTP fromfrom full full power power conditions conditions in in an an orderly orderly manner manner withoutwithout challenging plant challenging plant systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE The SRs The SRs forfor each each RPS RPS Function Function are are identified identified by by the the SRs SRs columncolumn of of REQUIREMENTS REQUIREMENTS Table 3.3.1-1 Table 3.3.1-1 for for that that Function.
| |
| Function. Most Most Functions Functions are are subject subject to to CHANNEL CHANNEL CHECK, CHANNEL CHECK, CHANNEL FUNCTIONALFUNCTIONAL TEST, TEST, CHANNEL CHANNEL CALIBRATION, CALIBRATION, and RPS and RPS RESPONSE RESPONSE TIME TIME testing.
| |
| testing.
| |
| The SRs The SRs are are modified modified by by aa Note.
| |
| Note. TheThe [firstJ
| |
| [first] Note Note directs directs the the reader reader to to Table 3.3.1-1 Table 3.3.1-1 to to determine determine the the correct correct SRsSRs to to perform perform for for eacheach RPSRPS Function.
| |
| Function.
| |
| REVIEWER'S
| |
| -----------------------------------REVIEWE
| |
| ---------------------*------------- NOTE.................................
| |
| R'S NOTE----------------------------------- --
| |
| The CHANNEL The CHANNEL FUNCTIONALFUNCTIONAL TEST TEST Frequencies Frequencies are are based based on on approved approved topical reports.
| |
| topical reports. For For a a licensee licensee to to use use these these times.
| |
| times, the the licensee licensee must must justify justify thethe Frequencies Frequencies as as required required by by the the NRCNRC Staff Staff SER SER for for the the topical topical report.
| |
| report.
| |
| SR 3.3.1.1 SR 3.3.1.1 Eedormance of
| |
| [Eerformance of the the CHANNEL CHANNEL CHECK CHECK once once every every 12 hours ensures 12 hours ensures that that a gross a gross failure failure ofof instrumentation instrumentation has has not occurred.aCHANNEL not occurred. CHANNEL CHECK CHECK is normally is normally a a comparison comparison of of the the parameter parameter indicated indicated on on oneone channel channel to to aa\
| |
| similar parameter similar parameter on on other other channels.
| |
| channels. It It is is based based on on the the assumption assumption that that instrument channels instrument channels monitoring monitoring thethe same same parameter parameter should should read read approximately the approximately the same same value.
| |
| value. Significant Significant deviations deviations between between two two 1 instrument channels instrument channels couldcould bebe an an indication indication of of excessive excessive instrument inst drift in one of one of the the channels channels or or of of something something even even moremore serious.
| |
| serious. CHANNELC CHECK will CHECK will detect detect gross gross channel channel failure; faiture; therefore, therefore, itit isis key ke in verifying that the that the instrumentation instrumentation continues continues to to operate operate properly betwe each properly between CHANNEL CALIBRATION.
| |
| CHANNEL CALIBRATION. c%~
| |
| ~ .1IIl -'""
| |
| )I BWOG STS BWOGSTS 3.3.1-25 6 3.3.1-25 B Rev. 3.0, 03/31/04 Rev. 3.0, 03131104
| |
| | |
| TSTF-425, Rev. 3 RPS Instrumentation RPS Instrumentation B 3.3.1 B 3.3.1 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| Agreement criteria are Agreement criteria are determined determined by by the the unit unit staff staff based based on on aa combination of combination of the the channel channel instrument instrument uncertainties, uncertainties, including isolation, including isolation, indication, and indication, and readability.
| |
| readability. If If a a channel channel is is outside outside the the criteria, criteria, itit may may be be an indication an indication thatthat the the transmitter transmitter or or the the signal signal processing processing equipment equipment has has drifted outside drifted outside its its limit.
| |
| limit. If If the the channels channels are are within within thethe criteria, criteria, itit isis an an indication that indication that the the channels channels are are OPERABLE.
| |
| OPERABLE. If If the the channels channels are are normally normally off scale off scale during during timestimes whenwhen surveillance surveillance is is required, required, the the CHANNEL CHANNEL CHECK will CHECK only verify will only verify that that they they are are off off scale scale in in the the same same direction.
| |
| direction. Off Off scale low scale low current current loop loop channels channels are are verified verified to to be be reading reading at at the the bottom bottom ofof the range the range andand notnot failed failed downscale.
| |
| downscale.
| |
| The agreement The agreement criteria criteria includes includes an an expectation expectation of of one one decade decade of of overlap overlap when transitioning when transitioning between between neutronneutron fluxflux instrumentation.
| |
| instrumentation. For For example, example, during a during a power power increase increase near near the the top top ofof the the scale scale of of the the intermediate intermediate range monitors, range monitors, a a power power rangerange monitor monitor reading reading is is expected expected with with at at least least one decade one decade overlap.
| |
| overlap. WithoutWithout such such anan overlap, overlap, the the power power rangerange monitors monitors are considered are considered inoperable inoperable unless unless itit is is clear clear that that anan intermediate intermediate range range monitor inoperability is responsible for the lack of monitor inoperability is responsible for the lack of the expected overlap. the expected overlap.
| |
| E h e Frequency, ahe Frequency, about about onceonce every every shift, shift, is is based based on on operating operating experience experience that demonstrates that demonstrates channel channel failure rare. Since failure is rare. Since the the probability probability of of two two random failures random failures in in redundant redundant channels channels in in any any 12 12 hour hour period period is is extremely extremely low, the low, the CHANNEL CHANNEL CHECK CHECK minimizes minimizes the the chance chance of of loss loss ofof protective protective function due function due toto failure failure of of redundant redundant channels~HANNEL channels CHECK supplements less supplements less formal formal but but more more frequent frequent cli'ecksof c channel OPERABILITY during OPERABILITY during normal normal operational operational use use of of the the displays associated with the with LCO's required the LCO's required channels.
| |
| channels. Ihs,ert Z For Functions For Functions that that trip trip on on a a combination combination of of several several measurements, measurements, such such as the as the Nuclear Nuclear Overpower Overpower RCS RCS FlowFlow andand Measured Measured AXIAL AXIAL POWERPOWER IMBALANCE Function, IMBALANCE Function, the the CHANNEL CHANNEL CHECK CHECK must must be be performed performed on on each input.
| |
| each input.
| |
| SR 3.3.1.2 This SR This SR isis the the performance performance of of aa heat heat balance balance calibration calibration for for the power the power c h a n n e l s ( e mMJr~when range channels@v?'i14 range $ , v h e n reactor reactor power power is> is > 15%15% RTP.
| |
| RTP. The The heat balance heat balance calibration calibration consistsconsists of of a comparison of a comparison of the the results results of of the the calorimetric with calorimetric with the the powerrange power range channel channel output.
| |
| output. The The outputs outputs of of the the power range power range channels channels are are normalized normalized to to the the calorimetric.
| |
| calorimetric. Note Note 1 Ito to the the SR states SR states ifif the the absolute absolute difference difference between between the the calorimetric calorimetric and and the the STS BWOG STS BWOG 3.3.1-26 6 3.3.1-26 B Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RPS Instrumentation RPS Instrumentation 3.3.1 B 3.3.1 B
| |
| BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| Nuclear Instrumentation Nuclear lnstrumentation System System (NIS)
| |
| (NIS) channel channel outputoutput is is >> [2]%
| |
| [2]% RTP,RTP, thethe NIS is NIS is not not declared declared inoperable inoperable but but mustmust be be adjusted.
| |
| adjusted. If If the the NISNIS channel channel cannot be cannot be properly properly adjusted, adjusted, the channel is the channel is declared declared inoperable.
| |
| inoperable. Note Note 2 2 clarifies that clarifies that this this Surveillance Surveillance is is required required only only if if reactor reactor powerpower is is 15% RTP r 15%
| |
| 2= RTP and and that that 2424 hours hours isis allowed allowed for for performing performing the the first first Surveillance after Surveillance after reaching reaching 15% 15% RTP.RTP. At lower power At lower power levels, levels, calorimetric calorimetric data are data are inaccurate.
| |
| inaccurate.
| |
| The power The power range range channel's channel's output output shall shall bebe adjusted adjusted consistent consistent with with the the calorimetric results calorimetric results ifif the the absolute absolute difference difference between between the the calorimetric calorimetric and and the power the power rangerange channel's channel's output output is is >> [2]%
| |
| [2]% RTP.
| |
| RTP. The The value value of [2]% is of [2]% is adequate because adequate because this this value value isis assumed assumed in in the the safety safety analyses analyses of of FSAR, FSAR, Chapter [14]
| |
| Chapter [I41 (Ref. 3). These (Ref. 3). These checks checks and, and, ifif necessary, necessary, the the adjustment adjustment of of the power the power rangerange channels channels ensure ensure that that channel channel accuracy accuracy is is maintained maintained within the within the analyzed analyzed error margins.zhe error margins. rThe 24 24 hour hour Frequency Frequency is is adequate, adequate.
| |
| based on based on unit unit operating operating experienct"which experience, which demonstrates demonstrates the the change change in in the difference the difference betweenbetween the the power power range range indication indication and and the the calorimetric calorimetric results rarely results rarely exceeds exceeds a a small small fraction fraction of [2]% in of [2]% in any any 2424 hourhour period.
| |
| period.
| |
| Furthermore, the Furthermore, the control control roomroom operators operators monitor monitor redundant redundant indications indications and alarms and alarms to to detect detect deviations deviations in in channel outputs.f->
| |
| channel outPUIs.?
| |
| SR 3.3.1.3
| |
| ~sert~)
| |
| A comparison of A comparison of power power range range nuclear nuclear instrumentation instrumentation channels channels against against incore detectors incore detectors shall shall bebe performed performed lifa;;;a:?'Qav6'?CiUfi!"I!:YJwhen ht & d a v J & - d w h e n reactor reactor power is power > 15%
| |
| is > RTP. The 15% RTP. The SRSR is is modified modified by by two two Notes.
| |
| Notes. Note Note 2 clarifies 2 clarifies 24 hours that 24 that hours is is allowed allowed for for performing performing the the first first Surveillance Surveillance after after reaching reaching 15% RTP.
| |
| 15% RTP. Note Note 1 states ifif the 1 states the absolute absolute difference difference between between the the power power range and range incore measurements and incore measurements is is 2= [2]% RTP, L [2]% RTP, the the power power range range channel channel is not is not inoperable, inoperable, but but anan adjustment adjustment of of the the measured measured imbalance imbalance to to agree agree with incore measurements the incore with the measurements is is necessary.
| |
| necessary. If If the the power power range range channel channel cannot be cannot be properly properly recalibrated, recalibrated, the the channel channel is is declared inoperable. The declared inoperable. The calculation of calculation of the the Allowable Allowable Value envelope assumes Value envelope assumes a a difference difference in in out out of core of core to incore measurements to incore measurements of 2.5%. Additional of 2.5%. inaccuracies beyond Additional inaccuracies beyond those that those that areare measured measured are are also also included included in in the setpoint envelope the setpoint envelope calculation. fThe The 31 31 day day Frequency Frequency is is adequate, adequate, considering considering that that long long I
| |
| ~. .
| |
| l ~ term calculation.
| |
| term drift Ivt3eil~)~ detectors drift ofU,e detectors is 5,
| |
| o f t e excore is slow.
| |
| excore linear slow. Also, linear amplifiers Also, the amplifiers is the excore excore readings is small small and readings are are a and burnup burnup of a strong strong function of the the function of of the the
| |
| '~--' power produced produced in the peripheral in the peripheral fuel fuel bundles, bundles, and and do do notnot represent represent an an
| |
| 'C power integrated reading integrated reading across across the the core.
| |
| core. The The slow slow changes changes in in neutron neutron flux flux during the during the fuel fuel cycle cycle can can also also be be detected detected at at this this interval.
| |
| interval. 4 BWOG STS BWOG STS B,3.3.1-27 B*3.3.1-27 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RPS Instrumentation RPS Instrumentation B 3.3.1 B 3.3.1 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| SR 3.3.1.4 A CHANNEL FUNCTIONAL A CHANNEL FUNCTIONAL TEST TEST is is performed performed on on each each required required RPS RPS channel to channel to ensure ensure thatthat the the entire entire channel channel will perform the will perform the intended intended function. A function. A successful successful test test ofof the the required contact(s) of required contact(s) of aa channel channel relay relay may be may be performed performed by by the the verification verification of of the the change change of of state state of of aa single single contact of contact of the the relay.
| |
| relay. ThisThis clarifies clarifies what what is is an an acceptable acceptable CHANNEL CHANNEL FUNCTIONAL TEST FUNCTIONAL TEST of of aa relay.
| |
| relay. This This is is acceptable acceptable because because all all of of the the other required other required contacts contacts of of the the relay relay areare verified verified byby other other Technical Technical Specifications and Specifications and non-Technical non-Technical Specifications Specifications tests tests at at least least once once perper refueling interval refueling interval with applicable extensions.
| |
| with applicable extensions. Setpoints Setpoints mustmust be be found found within the Allowable within the Allowable Values specified in Values specified in Table 3.3.1-1. Any Table 3.3.1-1. setpoint Any setpoint adjustment shall adjustment shall bebe consistent consistent with with thethe assumptions assumptions of of the the current current unit unit setpoint analysis.
| |
| specific setpoint specific analysis.
| |
| The as The found and as found and as as left left values values mustmust alsoalso bebe recorded recorded and and reviewed reviewed for for consistency with consistency with the the assumptions assumptions of of the the surveillance surveillance interval interval extension extension analysis. The analysis. The requirements requirements for for this this review review areare outlined outlined in in BAW-10167 BAW-10167 (Ref. 10).
| |
| (Ref. 10).
| |
| fihe Frequency
| |
| [The Frequency of [45] days of [45] days on on aa STAGGERED STAGGERED TEST TEST BASIS BASIS is is consistent with consistent with the retains aa high retains the calculations high level level of calculations of of reliability of Reference reliability for Reference 9 for this this test 9 that test interval.
| |
| interval. ?-~;se~+ i) that indicate indicate the RPS the RPS SR 3.3.1.5 SR 3.3.1.5 A Note to A Note to the the Surveillance Surveillance indicates indicates that that neutron neutron detectors detectors are are excluded excluded from CHANNEL from CHANNEL CALIBRATION.
| |
| CALIBRATION. This This Note Note is is necessary necessary because because of of the the difficulty in difficulty in generating generating an an appropriate appropriate detector detector input input signal.
| |
| signal. Excluding Excluding the the detectors is detectors is acceptable acceptable because because the the principles principles of of detector detector operation operation ensure a ensure a virtually virtually instantaneous instantaneous response.
| |
| response.
| |
| A CHANNEL CALIBRATION A CHANNEL CALIBRATION is is a complete check a complete check of of the the instrument instrument channel, including channel, including the the sensor.
| |
| sensor. The The test test verifies verifies that that the the channel channel responds responds to the to the measured measured parameter parameter within within the the necessary necessary rangerange and and accuracy.
| |
| accuracy.
| |
| CHANNEL CALIBRATION CHANNEL CALIBRATION leaves leaves the channel adjusted the channel adjusted to to account account for for instrument drift instrument drift to to ensure ensure thatthat the the instrument instrument channel channel remains remains operational operational between successive between successive tests. tests. CHANNEL CHANNEL CALIBRATION CALIBRATION shall shall find find that that measurement errors measurement errors and and bistable bistable setpoint setpoint errors errors areare within within thethe assumptions of assumptions of the the unit unit specific setpoint analysis.
| |
| specific setpoint analysis. CHANNEL CHANNEL CALIBRATIONS must CALIBRATIONS must be be performed performed consistent consistent withwith the the assumptions assumptions of of the unit the unit specific setpoint analysis.
| |
| specific setpoint analysis.
| |
| BWOG STS SWOG STS B 3.3.1-28 B 3.3.1-28 Rev. 3.0, Rev. 03131104 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RPS Instrumentation RPS Instrumentation 3.3.1 B 3.3.1 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| Whenever a Whenever a sensing sensing element element is is replaced, replaced, the the next next required required CHANNEL CHANNEL CALIBRATION of CALIBRATION of the the resistance resistance temperature temperature detectors detectors (RTD) (RTD) sensors sensors is is accomplished by accomplished by an inplace cross an inplace cross calibration calibration that that compares compares the the otherother sensing elements sensing elements with with the the recently recently installed installed sensing sensing element. element.
| |
| (The Fre~uency c ~ h Frequency e is jus~ifie~
| |
| is justified byby the assum~tion of the assumption of an an [I81[~8] month. month calibration c~libration mterval In Interval in the the determination determination of of the the magnitude magnitude of'eqUipment of'equipment drift drift In in the the setpointanalysis. ~~ert ~
| |
| SR 3.3.1.6 SR verifies This SR This verifies individual individual channel channel actuation actuation responseresponse times times are are lessless than than or equal or equal toto the the maximum maximum values values assumed assumed in in the the accident accident analysis. analysis.
| |
| Individual component Individual component response response timestimes areare not not modeled modeled in in the the analyses. analyses.
| |
| The analyses The analyses modelmodel thethe overall, overall, or or total, total, elapsed elapsed time time from from the the point point at at which the which the parameter parameter exceedsexceeds the the analytical analytical limit limit at at the the sensor sensor to to the the point point of rod insertion. Response time testing acceptance of rod insertion. Response time testing acceptance criteria for this unit criteria for this unit are included are included in in Reference Reference 2. 2.
| |
| A Note to A Note to the the Surveillance Surveillance indicates indicates that that neutron neutron detectors detectors are are excludedexcluded from RPS from RPS RESPONSE RESPONSE TIME TIME testing.
| |
| testing. ThisThis NoteNote is is necessary necessary because because of of the difficulty the difficulty inin generating generating an an appropriate appropriate detectordetector input input signal. signal. Excluding Excluding the detectors the detectors is is acceptable acceptable because because the the principles principles of of detector detector operation operation ensure a ensure a virtually virtually instantaneous instantaneous response.
| |
| response.
| |
| c Response time f;esponse EST BASIS.
| |
| LiisT bulk of bulk of the time tests the response tests are BASIS. Testing response time, Therefore, staggered Therefore, are conducted Testing of conducted on of the the final time, is staggered testing is included included in testing results results in on an final actuation in the
| |
| [I an [18]
| |
| actuation devices, the testing in response month STAGGERED 81 month devices, which testing of response time STAGGERED which make of eacheach channel.
| |
| time verification verification of make up channel.
| |
| up the the of these these devices every devices [I81 months.
| |
| every [18] months. The The [18][I81 month month Frequency Frequency is is based based on on unit unit operating experience, operating experience, which which shows shows that that random random failures failures of of instrumentation components instrumentation but not but not channel components causing channel failure, failure, are causing serious are infrequent serious response infrequent occurrences.
| |
| occurrences. A response time t time degradation, degradation, (tn~er.
| |
| ~._."",_"",-""
| |
| :2.#)
| |
| *."_"*."""__~."""""_,,,,,,,,,,,,",,.,.~~w....,....--'
| |
| BWOG STS BWOGSTS B 3.3.1-29 B 3.3.1-29 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RPS Manual RPS Manual Reactor Reactor Trip Trip 3.3.2 B 3.3.2 B
| |
| BASES BASES SURVEILLANCE SURVEILLANCE SR 3.3.2.1 SR 3.3.2.1 REQUIREMENTS REQUIREMENTS This SR This SR requires requires thethe performance performance of of a a CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST ofof the Manual the Manual Reactor Reactor Trip Trip Function.
| |
| Function. This This test test verifies verifies the the OPERABILITY OPERABILITY of of the Manual the Manual Reactor Reactor Trip Trip by by actuation actuation of of the the CRD CRD trip trip breakers.
| |
| breakers. A A successful test successful test of of the the required contact(s) of required contact(s) a channel of a channel relay relay may may be be performed by performed by the the verification verification of of the the change change of of state state of of a a single single contact contact of of the relay.
| |
| the relay. This This clarifies clarifies what is an what is an acceptable acceptable CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TEST of TEST of aa relay.
| |
| relay. This This is is acceptable acceptable because because all all of of the the other other required required contacts of contacts of the the relay relay are are verified verified by by other other Technical Technical Specifications Specifications and and non-Technical Specifications non-Technical Specifications tests tests at at least least once once per per refueling refueling interval interval with with applicable extensions.
| |
| applicable extensions. The The Frequency Frequency shallshall be be once once prior prior to to each each reactor reactor startup if startup if not not performed performed within the preceding within the preceding 7 7 days days to to ensure ensure the the OPERABILITY of the Manual Reactor Trip Function OPERABILITY of the Manual Reactor Trip Function prior to achieving prior to achieving criticality. The criticality. The Frequency Frequency was was developed developed in in consideration consideration thatthat these these Surveillances are Surveillances are only only performed performed during during a a unit unit outage.
| |
| outage.
| |
| REFERENCES REFERENCES I. FSAR,
| |
| : 1. FSAR, Chapter Chapter [7J.
| |
| [7].
| |
| BWOG STS BWOG STS B 3.3.2-3 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RPS -- RTM RPS RTM 3.3.3 B 3.3.3 B
| |
| BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| C.l and C.1 C.2 and C.2 Condition C Condition C applies applies ifif two two or or more more RTMs RTMs are are inoperable inoperable or or ifif the the Required Required Actions Actions of of Condition Condition A are not A are not met met within within the the required required Completion Completion Time Time in in MODE 4 or MODE or 5.5. In In this this case, case, the the unit unit must must be be placed placed in in aa MODE MODE in in which which L C 0 does the LCO the does not not apply.
| |
| apply. This This is is done done by by opening opening all CRD trip all CRD trip breakers breakers or or removing power removing power from from all CRD trip all CRD trip breakers.
| |
| breakers. The The allowed allowed Completion Completion Time of Time 6 hours of 6 hours is is reasonable, reasonable, basedbased on on operating operating experience, experience, to to open open allall CRD trip CRD trip breakers breakers or or remove remove power power from from all CRD trip all CRD trip breakers breakers without without challenging unit challenging unit systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE 3.3.3.1 SR 3.3.3.1 SR REQUIREMENTS I
| |
| REQUIREMENTS
| |
| -----------------------------------REVIEWER'S
| |
| -----------------------------------REVI NOTE...................................
| |
| EWER'S NOTE---------.-------------------------
| |
| The CHANNEL The CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST Frequency Frequency is is approved approved for for all B&W all B&W power plants power plants except except forfor TMI TMI based based onan on an approved approved topical topical report.
| |
| report. No No further evaluations further evaluations or or justifications are required justifications are required for for the the evaluated evaluated plants plants toto incorporate the incorporate the 23 23 day day STAGGERED STAGGERED TEST BASIS Frequency.
| |
| TEST BASIS Frequency.
| |
| The SRs include performance of a CHANNEL FUNCTIONAL TES~
| |
| EL FUNCTIONAL T E S ~
| |
| ~ o~! 8MBE@sIJ3A§f§. This This test test shall shall verify verify the the OPERABILITY of the RTM and its ability to receive receive and and properly properly respond respond to channel to channel triptrip and and reactor reactor trip signals. A trip signals. successful test A successful test of of the the required required contact(s) of contact(s) of a a channel channel relay relay may may bebe performed performed by by the the verification verification of of the the change of change of state state of of a a single single contact contact ofof the the relay.
| |
| relay. This This clarifies clarifies what what is is an an acceptable CHANNEL acceptable CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST of a reiay.
| |
| of a relay. This This is is acceptable acceptable because all because all of of the the other other required required contacts contacts of of the the relay relay areare verified verified by by other other Technical Specifications Technical Specifications and and non-Technical non-Technical Specifica~s Specificatio s teststests at at least least once per once per refueling refueling inteNal interval with with applicable extensions.$aalculations have applicable extensions.L£alculations have shown that shown that the the Frequency Frequency (23 (23 days) days) maintains maintains a highhigh level level of of reliability reliability of of the Reactor the Reactor Trip Trip System System in in BAW-10167A, BAW-10167A, Sup Sup lement ement 3 3 (Ref.
| |
| (Ref. 2). 2 ) . 9 REFERENCES REFERENCES 1.
| |
| : 1. FSAR, Chapter FSAR, Chapter [7].[7].
| |
| 2.
| |
| : 2. BAW-10167A, Supplement BAW-10167A, Supplement 3, 3, February February 1998.
| |
| 1998.
| |
| BWOG STS BWOG STS B 3.3.3-4 Rev. 3.0, Rev. 3.0, 03/31/04 03131104
| |
| | |
| TSTF-425, Rev. 3 CRD Trip CRD Trip Devices Devices 3.3.4 B 3.3.4 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| E . l and E.1 and E.2 E.2 If the If the Required Required Actions Actions of of Condition Condition A, B, or A, B, C are or C are not not met met within within the the required Completion required Completion Time Time in MODE 4 or in MODE 5, the or 5, the unit unit must must be be brought brought to a to a MODE in MODE in which which the the LCO L C 0 does does not not apply.
| |
| apply. To To achieve achieve thisthis status, status, allall CRD CRD trip breakers trip breakers must must be be opened opened or or power power from from allall CRD CRD triptrip breakers breakers removed within removed within 6 6 hours.
| |
| hours. The The allowed allowed Completion Completion Time Time of 6 hours of 6 hours is is reasonable, based reasonable, based on on operating operating experience, experience, to to open open all CRD trip all CRD trip breakers breakers or remove or remove power power from from allall CRD CRD trip trip breakers breakers without without challenging challenging unit unit systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE SR 3.3.4.1 SR 3.3.4.1 REQUIREMENTS REQUIREMENTS
| |
| ----------------------------------REVI
| |
| --------+------------------------- REV1EWER'S --
| |
| NOTE--------- ..................... ---
| |
| EWER'S NOTE---------**------------------------
| |
| The CHANNEL The CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST Frequency Frequency is is approved approved for for all B&W all B&W plants except plants except for for TMITMI based based on on an an approved approved topical topical report.
| |
| report. No No further further evaluations or evaluations or justifications justifications are are required required forfor the the evaluated evaluated plantsplants toto incorporate the incorporate the 23 23 day day STAGGERED STAGGERED TEST TEST BASIS BASIS Frequency.
| |
| Frequency.
| |
| SR 3.3.4.1 ~erform a CHANNEL EL FUNCTIONAL FUNCTIONAL TEST@vd23 TEST^^) dt&sJ
| |
| <<in: iatA~P $1 PASI:}. This This test test verifies verifies the the OPERABILITY OPERABILITY of of the trip the trip devices devices by by actuation actuation of of the the end end devices.
| |
| devices. Also,Also, this this test test independently verifies independently verifies the the undervoltage undervoltage and and shunt shunt trip trip mechanisms mechanisms of of the the AC breakers. A AC breakers. A successful successful testtest of of the the required required contact{s) contact(s) of of aa channel channel relay may relay may be be performed performed by by the the verification verification of of the the change change of of state state ofof aa single contact single contact of of the the relay.
| |
| relay. This This clarifies clarifies what what isis an an acceptable acceptable CHANNEL CHANNEL FUNCTIONAL TEST FUNCTIONAL TEST of of a relay. This a relay. This isis acceptable acceptable because because all all of of the the other required other required contacts contacts of of the the relay relay are are verified verified by by other other Technical Technical Specifications and Specifications and non-Technical non-Technical Specifications Specifications tests tests atat least least once once per refueling interval refueling interval with with applicable applicable extensions.(Qalculations extensions.~alculationshave have shown shown that the that the Frequency Frequency (23 (23 days) days) maintains maintains a a high high level level of of reliability reliability ofof the the Reactor Trip Reactor Trip SystemSystem in BAW-1OI67A, Supplement in BAW-10167A, Supplement 3 3 (Ref.
| |
| (Ref. 2).
| |
| 2).
| |
| .fi\
| |
| REFERENCES REFERENCES I. FSAR,
| |
| : 1. FSAR, Chapter Chapter [7]. 171. (+ ~ ,l,s e r t T i )
| |
| 2.
| |
| : 2. BAW-10167A. Supplement BAW-10167A, Sumlement 3, 3. February Februarv 1998.1998.
| |
| BWOG STS BWOG STS B 3.3.4-6 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 ESFAS Instrumentation ESFAS Instrumentation B 3.3.5 B 3.3.5 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| SR 3.3.5.1 Performance of Performance of the CHANNEL CHECK~2 the CHANNEL C ~ ~ ~ ~ ~ensures m e n sthat thatu a a r e s gross failure g-ross failure ofof instrumentation instrumentation has has notnot occurred.
| |
| occurred. A CHANNEL CHECK A CHANNEL CHECK is normally is normally a a comparison comparison of of the the parameter parameter indicated indicated on on one one channel channel to to aa similar parameter similar parameter on on other other channels.
| |
| channels. ItIt is is based based on on the the assumption assumption that that instrument channels instrument channels monitoring monitoring the the same same parameter parameter should should readread approximately the approximately the same same value.
| |
| value. Significant Significant deviations deviations between between the the two two instrument channels instrument channels couldcould be be anan indication indication of of excessive excessive instrument instrument drift drift in in one of one of the the channels channels or or of of something something even even more more serious.
| |
| serious. CHANNEL CHANNEL CHECK will CHECK will detect detect gross gross channel channel failure; failure; therefore, therefore, itit isis key key inin verifying verifying that the that the instrumentation instrumentation continuescontinues to to operate operate properly properly between between each each CHANNEL CALIBRATION.
| |
| CHANNEL CALIBRATION.
| |
| Agreement criteria are Agreement criteria are determined determined by by the the unit unit staff, staff, based based on on a a combination of combination of the the channel channel instrument instrument uncertainties, uncertainties, including including isolation, isolation, indication, and indication, and readability.
| |
| readability. If If aa channel channel is is outside outside thethe criteria, criteria, itit may may be be an indication an indication thatthat the the transmitter transmitter or or the the signal signal processing processing equipment equipment has has drifted outside drifted outside its its limit.
| |
| limit. If If the the channels channels are are normally normally off off scale scale during during times times when surveillance is when surveillance is required, required, the the CHANNEL CHANNEL CHECK CHECK will will only only verify verify that that they are they are off off scale scale inin the the same same direction.
| |
| direction. Off Off scale scale low low current current loop loop channels are channels are verified verified to to be be reading reading at at the the bottom bottom of the range of the range andand not not failed downscale.
| |
| failed downscale.
| |
| E h e Frequency, Uhe Frequency, about about once once everyevery shift, shift. isis based based on on operating operating experience experience that demonstrates that demonstrates channel channel failure failure is is rare.
| |
| rare. Since Since the probability of the probability of two two random failures random failures in in redundant redundant channelschannels in in any any 12 hour period 12 hour period is is extremely extremely low, the low, the CHANNEL CHANNEL CHECK CHECK minimizes minimizes the the chance chance of of loss loss ofof protective protective function due function due toto failure failure ofof redundant redundant channelschannel The CHANNEL CHECK supplements less supplements less formal, formal, but but more more frequent, frequent checks of channel operability during normal during normal operational operational use use of of the the displays displa ssociated . h the LCO's required channels.
| |
| required channels. J.-t.I ser ~ t SR 3.3.5.2 A Note defines A Note defines a a channel channel as as being being OPERABLE OPERABLE for for up to 88 hours up to hours while while bypassed for bypassed for Surveillance Surveillance testing testing provided provided the the remaining remaining two two ESFAS ESFAS channels are channels are OPERABLE OPERABLE or or tripped.
| |
| tripped. The The NoteNote allows allows channel channel bypassbypass forfor testing without testing without defining defining itit as as inoperable, inoperable, althoughalthough during during this this time time period period itit cannot initiate cannot initiate ESFAS.
| |
| ESFAS. This This allowance allowance is is based based on on the the inability inability to to perform perform the Surveillance the Surveillance in in the the time time permitted permitted by by the the Required Required Actions.
| |
| Actions. EightEight hours is hours is the the average average time time required required to to perform perform the the Surveillance.
| |
| Surveillance. It is is not not acceptable to routinely remove channels from service for more than acceptable to routinely remove channels from service for more than 8 hours 8 hours toto perform perform required required Surveillance Surveillance testing.
| |
| testing.
| |
| BWOG STS BWOG STS B 3.3.5-15 B 3.3.5-15 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 ESFAS Instrumentation ESFAS Instrumentation 3.3.5 B 3.3.5 B
| |
| BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| A CHANNEL A CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST is is performed performed on on each each required required ESFASESFAS channel to channel to ensure ensure the the entire entire channel channel willwill perform perform thethe intended intended functions.
| |
| functions.
| |
| A successful test A successful test ofof the the required contact(s) of required contact(s) of a a channel channel relay relay may may be be performed by performed by the the verification verification of of the the change change of of state state of of a a single single contact contact of of the relay.
| |
| the relay. This This clarifies clarifies what what is is an an acceptable acceptable CHANNEL CHANNEL FUNCTIONALFUNCTIONAL TEST of TEST of aa relay.
| |
| relay. This This is is acceptable acceptable because because all all of of the the other other required required contacts of contacts of the the relay relay are are verified verified by by other other Technical Technical Specifications Specifications and and non-Technical Specifications non-Technical Specifications tests tests atat least least once once perper refueling refueling interval interval with with applicable extensions.
| |
| applicable extensions. Any setpoint adjustment Any setpoint adjustment shall shall bebe consistent consistent with with the assumptions the assumptions of of the the current current unitunit specific setpoint analysis.
| |
| specific setpoint analysis.
| |
| E h e Frequency Uhe Frequency of 31 days of 31 days is is based based on on unit unit operating operating experience, experience, with with regard to regard to channel channel OPERABILITY OPERABILITY and and drift, drift, which which demonstrates demonstrates that that failure of failure of more more thanthan oneone channel channel of of aa given given function function inin any any 31 31 day day interval interval is a rare event.
| |
| ~ri~a (5nSe.l~~
| |
| rareev'J SR 3.3.5.3 CHANNEL CALIBRATION CHANNEL CALIBRATION is is aa complete complete checkcheck of of the the instrument instrument channel, channel, including the including the sensor.
| |
| sensor. The The test test verifies verifies that that the the channel channel responds responds to to aa measured parameter measured parameter withinwithin thethe necessary necessary rangerange andand accuracy.
| |
| accuracy.
| |
| CHANNEL CALIBRATION CHANNEL CALIBRATION leaves leaves thethe channel channel adjusted adjusted to to account account for for instrument drift instrument drift to to ensure ensure thatthat the the instrument instrument channel channel remains remains operational operational between successive between successive tests. tests. CHANNEL CHANNEL CALIBRATION CALIBRATION shall shall find that find that measurement errors measurement errors andand bistable setpoint errors bistable setpoint errors are are within within the the assumptions of assumptions of the the unit unit specific setpoint analysis.
| |
| specific setpoint analysis. CHANNEL CHANNEL CALIBRATIONS must CALIBRATIONS must be be performed performed consistent consistent withwith the the assumptions assumptions of of the unit the unit specific setpoint analysis.
| |
| specific setpoint analysis.
| |
| F i s Frequency GiS Frequency is is justified justified by by the the assumption assumption of of an an [18] month calibration
| |
| [I81 month calibration mterval to Interval to determine determine the the magnitude magnitude of of equipment equipment driftdrift in in the the setpoint setpoint
| |
| ~rl:~ SR 3.3.5.4 SR 3.3.5.4 SR 3.3.5.4 SR ensures that 3.3.5.4 ensures that the the ESFAS ESFAS actuation actuation channel channel response response times times areare less than less than oror equal equal to to the the maximum maximum times times assumed assumed in in the the accident accident analysis. The analysis. The response response time time values values areare the the maximum maximum values values assumed assumed in in the safety the safety analyses.
| |
| analyses. Individual Individual component component response response times times are are not not modeled in modeled in the the analyses.
| |
| analyses. Response Response time time testing testing acceptance acceptance criteriacriteria for for this unit this unit are are included included in in Reference Reference 1. 1. The The analyses analyses model model the the overall overall or or total elapsed total elapsed timetime from from thethe point point at at which which the the parameter parameter exceedsexceeds the the BWOG STS BWOG STS B 3.3.5-16 B 3.3.5-16 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 ESFAS Instrumentation ESFAS Instrumentation 3.3.5 B 3.3.5 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)
| |
| (continued) setpoint value actuation setpoint actuation value atat the the sensor sensor toto the the point point at at which tl-ie end which tl1e end device device is actuated.
| |
| is actuated. Thus, Thus, this this SR SR encompasses encompasses the the automatic automatic actuation actuation logic logic covered by components covered components by LCO 3.3.7 and L C 0 3.3.7 and thethe operation operation of of the the mechanical mechanical ESF components.
| |
| ESF components.
| |
| 5Response time rR"esponse EST BASIS.
| |
| LTEST bulk of bulk of the time tests tests are BASIS. Testing the response are conducted Testing of response time, conducted on of the the final is included time, is on an included in an [18]
| |
| final actuation in the
| |
| [I&] month month STAGGERED actuation devices, STAGGERED devices, which the testing testing of which make of each make up each channel.
| |
| channel.
| |
| up the the Therefore, staggered Therefore, staggered testing testing results results in in response response time time verification verification of of these these devices every devices [18] months.
| |
| every [18] months. The The 1818 month month testtest Frequency Frequency is is based based on on REFERENCES REFERENCES unit operating unit operating experience, instrumentation but not but 1
| |
| not channel experience, which instrumentation components channel failure failure are FSAR, Chapter [7].
| |
| are infrequent shows that which shows components causingcausing serious that random serious response infrequent occurrences.
| |
| occurrences. ,--=f a:;-
| |
| random failures failures of response time of time degradation degradation P
| |
| : 2. 10 CFR 50.49.
| |
| 3.
| |
| : 3. [Unit Specific
| |
| [Unit Specific Setpoint Setpoint Methodology.]
| |
| Methodology.]
| |
| 4.
| |
| : 4. FSAR, Chapter FSAR, [14].
| |
| Chapter [14].
| |
| BWOG STS BWaG STS B 3.3.5-17 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 ESFAS Manual ESFAS Manual Initiation Initiation B 3.3.6 B 3.3.6 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| Condition A Condition applies when A applies when one one manual manual initiation initiation channel channel of of one one oror more more ESFAS Functions ESFAS Functions becomes becomes inoperable.
| |
| inoperable. Required Action A.1 Required Action must be A.1 must be taken to taken to restore restore the the channel channel to to OPERABLE OPERABLE status status within within thethe next next 72 hours.
| |
| 72 hours. The The Completion Completion Time Time of 72 hours of 72 hours isis based based on on unit unit operating operating experience and experience and administrative administrative controls, controls, whichwhich provide provide alternative alternative means means of ESFAS of ESFAS Function Function initiation initiation via via individual individual component component controls.
| |
| controls. The The 72 hour 72 hour Completion Completion Time Time is is consistent consistent with with the the allowed allowed outage outage timetime for for the safety the safety systems systems actuated actuated by by ESFAS.
| |
| ESFAS.
| |
| 6.1 and 8.1 8.2 and B.2 Required Action Required Action B.1B.1 and and Required Required ActionAction B.2 B.2 apply apply if if Required Required Action Action A.l A.1 cannot be cannot be met met within within the the required required Completion Completion Time. Time. If If Required Required Action A Action . l cannot A.1 cannot be be met met within within thethe required required Completion Completion Time, Time, thethe unit unit must be must be brought brought to to aa MODE MODE in in which which the the LCO L C 0 does does not not apply.
| |
| apply. To To achieve this achieve this status, status, the the unit unit must must be be brought brought to to at at least least MODE MODE 3 3 within within 6 hours 6 hours and and to to MODE 5 5 within within 3636 hours.
| |
| hours. The The allowed allowed Completion Completion Times Times are reasonable, are reasonable, based based on on operating operating experience, experience, to to reach reach the the required required MODES from MODES from full full power power conditions conditions in in anan orderly orderly manner manner and and without without challenging unit challenging unit systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE SR 3.3.6.1 SR 3.3.6.1 REQUIREMENTS REQUIREMENTS This SR This SR requires requires the the performance performance of of aa CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST of of the ESFAS the ESFAS manualmanual initiation.
| |
| initiation. ThisThis test test verifies verifies that that the the initiating initiating circuitry circuitry is OPERABLE is OPERABLE and and will actuate the will actuate the end end device (i.e., pump, device (i.e., pump, valves, valves, etc.).
| |
| etc.).
| |
| A successful test A successful test of of the the required contact(s) of required contact(s) of aa channel channel relayrelay may may bebe performed by performed by the the verification verification of of the the change change of of state state ofof a a single single contact contact of of the relay.
| |
| the relay. This This clarifies clarifies what what is is an an acceptable acceptable CHANNEL CHANNEL FUNCTIONALFUNCTIONAL TEST of TEST of aa relay.
| |
| relay. This This isis acceptable acceptable becausebecause all all of of the the other other required required contacts of contacts of the the relay relay are are verified verified by by other other Technical Technical Specifications Specifications and and non-Technical SpecificJltions Specific ions tests tests at at least least once once perper refueling refueling interval interval with with I?
| |
| non-Technical extensions. The [18]
| |
| applicable extensions.LIhe applicable month Frequency
| |
| [I81 month Frequency is is based based on on the the need need to perform to perform thisthis Surveillance Surveillance under under the the conditions conditions that that apply apply during during a unit a unit outage and outage and thethe potential potential forfor an an unplanned unplanned transient transient if if the the Surveillance Surveillance were performed with were performed the reactor with the reactor at at power.
| |
| power. This This Frequency Frequency is is demonstrated to demonstrated to be be sufficient, sufficient, based based on on operating operating experience, experience, which which shows these shows these components components usually usually passpass the the Surveillance Surveillance when performed when performed on the [18] month Frequency.
| |
| REFERENCES None.
| |
| BWOG STS BWOG STS 3.3.6-3 B 3.3.6-3 B Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 ESFAS Automatic ESFAS Automatic Actuation Logic Actuation Logic B 3.3.7 B 3.3.7 BASES BASES SURVEILLANCE SURVEILLANCE SR 3.3.7.1 SR 3.3.7.1 REQUIREMENTS REQUIREMENTS SR3.3.
| |
| 3 TA ASI . [rhe test demonstrates tha every automatic actuation logic associated with one of the two safety system trains successfully trains performs the successfully performs the two-out-of-three two-out-of-three logiclogic combinations combinations every every 1 311 days.
| |
| days. All a c t ~ a ~ o ~ J ~ g ~ ~ ~ ~ ~..§?Jt~~
| |
| automatic actuaJL<mJQg!£.~.2~..!!lu~.~~stesLE}y..~!Y All automatic ~ ~ ~ h ..... , u ~ ~ ~ & d ~
| |
| he tes The test simulates s/mu a es the required one-out-of-three e required one-out-of-three inputs inputs toto the the logic loqic circuit circuit and verifies and verifies the the successful successf~loperation operation of of the the automatic automatic actuation actuationlogic.
| |
| logic. A A
| |
| successful test successful test ofof the the required required contact(s) contact(s) of of a a channel channel relay relay may may bebe performed by performed by the the verification verification of of the the change change of of state state ofof a a single single contact contact of of the relay.
| |
| the relay. This This clarifies clarifies what is an what is an acceptable acceptable CHANNEL FUNCTIONAL CHANNEL FUNCTIONAL TEST of TEST of a a relay.
| |
| relay. This This isis acceptable acceptable because because all all of of the the other other required required contacts of contacts of the the relay relay are are verified verified byby other other Technical Technical Specifications Specifications andand non-Technical Specifications non-Technical Specifications tests tests at at least least once once perper refueling refueling interval interval with with applicable app Ica e ex extensions.*The Frequency is enslons. The Frequency is based based on on operating operating experience experience that demonstrates that demonstrates the the rarity raritv of of more more than than one one channel channel failing failina within within the the same 31 same day interval.(
| |
| 31 day interva1.f --r:iYlse.rf Y~nsrrf 3) 21 Automatic actuation logic Automatic actuation logic response response timetime testing testing is is incorporated incorporated into into the the response time response time testing testing required required by L C 0 3.3.5.
| |
| by LCO 3.3.5.
| |
| REFERENCES REFERENCES 1.
| |
| : 1. 10 CFR 10 CFR 50.46.
| |
| 50.46.
| |
| 2.
| |
| : 2. BAW-10103A, Rev.
| |
| BAW-10103A, Rev. 3,3, July July 1977.
| |
| 1977.
| |
| BWOG STS BWOGSTS B 3.3.7-4 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EDG LOPS EDG LOPS B 3.3.8 B 3.3.8 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| If one If one channel channel per per EDG EDG in in one one oror more more Functions Functions is is inoperable, inoperable, itit must must bebe tripped within tripped within 1 1 hour.
| |
| hour. WithWith a a channel channel in in trip, trip, the the LOPS LOPS channels channels are are configured to configured to provide provide a a one*out-of-two one-out-of-two logic logic to to initiate initiate a a trip trip of of the the offsite power.
| |
| incoming offsite incoming power. In trip, one In trip, one additional additional valid valid actuation actuation will cause a will cause a LOPS signal LOPS signal on on the the bus.
| |
| bus. TheThe 1 1 hour hour Completion Completion Time Time is is reasonable reasonable to to evaluate and evaluate and to to take take action action byby correcting correcting a a degraded degraded condition condition in in an an orderly manner orderly manner and and takes takes into into account account the the low low probability probability of of an an event event requiring LOPS requiring LOPS occurring occurring during during this this interval.
| |
| interval.
| |
| Condition B Condition B applies applies whenwhen twotwo oror more more undervoltage undervoltage or or two two oror more more degraded voltage degraded voltage channels channels on on a single bus a single bus are are inoperable.
| |
| inoperable.
| |
| Required Action Required Action B.1 B . l requires requires allall but but one one inoperable inoperable channel channel to to be be restored to restored to OPERABLE OPERABLE status status within within 1 hour. With Ihour. With two two or or more more channels channels inoperable, the inoperable, the logic logic isis not not capable capable of of providing providing an an automatic automatic EDG LOPS LOPS signal for signal for valid valid loss loss ofof voltage voltage or or degraded degraded voltagevoltage conditions.
| |
| conditions. The The 1 1 hour hour Completion Time Completion Time is is reasonable reasonable to to evaluate evaluate and and to to take take action action byby correcting the correcting the degraded degraded condition condition in in an an orderly orderly manner manner and and takes takes into into account the account the low low probability probability of of an an event event requiring requiring LOPS LOPS occurring occurring during during this interval.
| |
| this interval.
| |
| Condition C Condition applies if C applies if the the Required Required Action Action of of Condition Condition A A oror Condition Condition B B and the and the associated associated Completion Completion Time Time is is not not met.
| |
| met.
| |
| Required Action Required Action C.1 ensures that C.1 ensures that Required Required Actions Actions for for affected affected diesel diesel generator inoperabilities generator inoperabilities are are initiated.
| |
| initiated. Depending Depending on on unit MODE, the unit MODE, the Actions specified Actions specified in 3.8.1, "AC L C 0 3.8.1, in LCO Sources -- Operating,"
| |
| "AC Sources Operating," or or LCD L C 0 3.8.2, 3.8.2, are required are required immediately.
| |
| immediately.
| |
| SURVEILLANCE SURVEILLANCE 3.3.8.1 SR 3.3.8.1 SR REQUIREMENTS CHEC REQUIREMENTS 3.3.8.1 is SR 3.3.8.1 SR is the the performance performance of of the CHANNEL CHECK(Q"r~e~
| |
| the CHANNEL
| |
| @ ot)-
| |
| G??!5@s)to ensure that ensure that aa gross gross failure failure ofof instrumentation instrumentation has has not not occurred. A occurred. CHANNEL CHECK A CHANNEL CHECK is is normally normally a a comparison comparison of of the the BWOG STS BWOG STS B 3.3.8-5 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EDG LOPS EDG LOPS B 3.3.8 B 3.3.8 BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued) parameter indicated parameter indicated on on oneone channel channel to to aa similar similar parameter parameter on on other other channels. It channels. it is is based based on on thethe assumption assumption that that instrument instrument channels channels monitoring the monitoring the samesame parameter parameter should should read read approximately approximately the the same same value. Significant value. Significant deviations deviations betweenbetween the the twotwo instrument instrument channels channels could could be an be an indication indication of of excessive excessive instrument instrument drift drift in in one one ofof the the channels channels or or of of something even something even more more serious.
| |
| serious. CHANNEL CHANNEL CHECK CHECK will will detect detect gross gross channel failure; channel failure; therefore, therefore, itit is key in is key in verifying verifying that that the the instrumentation instrumentation continues to continues to operate operate properly properly betweenbetween each each CHANNEL CHANNEL CALIBRATION.
| |
| CALIBRATION.
| |
| Agreement criteria Agreement criteria are are determined determined by by the the unit unit staff staff based based onon a a combination of combination of thethe channel channel instrument instrument uncertainties, uncertainties, including including isolation, isolation, indication, and indication, and readability.
| |
| readability. If If aa channel channel is is outside outside the the criteria, criteria, itit may may bebe an indication an indication thatthat the the transmitter transmitter or or the the signal signal processing processing equipment equipment has has drifted outside drifted outside its its limit.
| |
| limit. If If the the channels channels are are within within the criteria, itit is the criteria, is an an indication that indication that the channels are the channels are OPERABLE.
| |
| OPERABLE.
| |
| C ~ h Frequency,
| |
| [The Frequency, e about once about once everyevery shift, shift, is is based based on on operating operating experience experience that demonstrates that demonstrates channel channel failure failure isis rare.
| |
| rare. SinceSince the the probability probability of of two two random failures random failures in in redundant redundant channelschannels in in any any 12 12 hour hour period period is is low, low, the the CHANNEL CHECK CHANNEL CHECK minimizes minimizes the the chance chance of of loss loss ofof protective protective function function due to due to failure failure of of redundant channels. Jhe CHANNEL CHECK supplements less supplements less formal.
| |
| formal, but but more more frequent checks of channel OPERABILITY during OPERABILITY during normal normal operational se of the displays associated with this with LC03 required this LCO's required channels. __ 1 /)
| |
| J.-n5e~ /.....J SR 3.3.8.2 SR 3.3.8.2 The Note The Note allows allows channel channel bypass bypass forfor testing testing without defining itit as without defining as inoperable although inoperable although during during this this time time period period it it cannot cannot actuate actuate a a diesel diesel start. This start. This allowance allowance is is based based on on the the assumption assumption that that 44 hours hours is is the the average time average time required required to to perform perform channel channel Surveillance.
| |
| Surveillance. The The 4 4 hour hour testing testing allowance does allowance does not not significantly significantly reduce reduce the the probability probability that that the the EDG EDG will will start when start when necessary.
| |
| necessary. It It is is not not acceptable acceptable to to routinely routinely remove remove channels channels from service from service forfor moremore thanthan 4 4 hours hours to to perform perform requiredrequired Surveillance Surveillance testing.
| |
| testing.
| |
| A CHANNEL A CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST is is performed performed on on each each required required EDG EDG LOPS channel LOPS channel to to ensure ensure the the entire entire channel channel will will perform perform the the intended intended function. A function. successful test A successful test ofof the the required contact(s) of required contact(s) of a a channel channel relay relay may be may be performed performed by by the the verification verification of of the the change change of of state state of of a a single single contact of contact of the the relay.
| |
| relay. This clarifies what This clarifies what is is an an acceptable acceptable CHANNEL CHANNEL BWOG STS BWOG STS B 3.3.8-6 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EDG LOPS EDG LOPS B 3.3.8 B 3.3.8 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| FUNCTIONAL TEST FUNCTIONAL TEST of of a a relay.
| |
| relay. This This is acceptable b is acceptable e c a ~ all beca~e all e ofof the the other required other required contacts contacts of of the the relay relay are are verified verified byby other other Technical Technical Specifications and Specifications and non-Technical non-Technical Specifications Specifications tests tests at at least least once once per per refueling interval refueling interval with applicable extensions.
| |
| with applicable extensions. Any setpoint adjustments Any setpoint adjustments shall be shall be consisten setpoint based on based consisten~ith setpoint analysis.
| |
| analvsis. The thereliably on the P ith the relia I Ity of the assumptions The Frequency assumptions of Freauencv of of the the components of 31 of the 31 days the current days is a
| |
| current unit is considered unit specific specific considered reasonable reasonable components and on operati~J! ..;;<:E~,~.i~.o.ce that demonstrates that demonstrates channel channel failure failure isis rare.
| |
| rare. ~. _r\-..i _ J.~2.
| |
| ,Cpr"1. .
| |
| ,->--",-~,~
| |
| SR 3.3.8.3 A CHANNEL CALIBRATION A CHANNEL CALIBRATION is is a a complete complete checkcheck of of the the instrument instrument channel, including channel, including thethe sensor.
| |
| sensor. The The setpoints setpoints and and the the response response to to a a loss loss of voltage of voltage andand aa degraded degraded voltagevoltage testtest shall shall include include a a single single point point verification that verification that the the trip trip occurs occurs within within the the required required delay delay time, time, as as shown shown in in Reference 1.
| |
| Reference CHANNEL CALIBRATION I. CHANNEL CALIBRATION shall shall find find that that measurement measurement setpoint errors setpoint errors are are within within thethe assumptions assumptions of of the the unit unit specific specific setpoint setpoint analysis. CHANNEL analysis. CHANNEL CALIBRATIONS CALIBRATIONS must must bebe performed performed consistent consistent with with the assumptions the assumptions of of the the unit unit specific setpoint analysis specific setpoint analysis in in Reference Reference 4. 4.
| |
| )J
| |
| [ r ~ h eFrequency
| |
| [The Frequency is is based based on on operating operating experience experience and and consistency consistency with with the typical the typical industry industry refueling refueling cyclecycle andand isis justified by the justified by the assumption assumption of of an an 18 month 18 month calibration calibration interval interval in in the the determination determination of of equipment equipment drift drift in in the the setpoint calculation.
| |
| setpoint calculation. .C f!" f k ~ ;l.)
| |
| ~ nse".~ A) d r
| |
| REFERENCES REFERENCES 1. FSAR, Section FSAR, Section [8.3].
| |
| [8.3].
| |
| 2.
| |
| : 2. FSAR, Chapter FSAR, Chapter [14].[14].
| |
| 3.
| |
| : 3. IEEE-279-1971, April IEEE-279-1971, 1972.
| |
| April 1972.
| |
| 4.
| |
| : 4. [Unit Name],
| |
| [Unit Name], [Unit
| |
| [Unit Specific Specific Setpoint Setpoint Methodology].
| |
| Methodology].
| |
| BWOG STS BWOG STS B 3.3.8-7 Rev. 3.0, Rev. 3.0,03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Source Range Source Range Neutron Neutron Flux Flux B 3.3.9 B 3.3.9 BASES BASES SURVEILLANCE SURVEILLANCE 3.3.9.1 SR 3.3.9.1 SR REQUIREMENTS REQUIREMENTS Performance of Performance of thethe CHANNEL CHECK^^&^^^
| |
| CHANNEL CHEcKwn;:?erY 1~Uffi)ensures 1 ~ u r s ) e n s u r e sthat that a gross a gross failure failure of of instrumentation instrumentation has has not not occurred.
| |
| occurred. A CHANNEL CHECK A CHANNEL CHECK is normally is normally a a comparison comparison of of the the parameter parameter indicated indicated on on one one channel channel to a to a similar parameter similar parameter on on other other channels.
| |
| channels. ItIt is is based based on on the the assumption assumption that that instrument channels instrument channels monitoring monitoring the the same same parameter parameter should should readread approximately the approximately the same same value.
| |
| value. Significant Significant deviations deviations betweenbetween the the two two instrument channels instrument channels could could be be anan indication indication of of excessive excessive instrument instrument drift drift in in one of one of the the channels channels or or of of something something even even more more serious.
| |
| serious. CHANNEL CHANNEL CHECK will CHECK will detect detect gross gross channel channel failure; failure; therefore, therefore, itit is is key key inin verifying verifying that the that the instrumentation instrumentation continues continues to to operate operate properly properly between between each each CHANNEL CALIBRATION.
| |
| CHANNEL CALIBRATION.
| |
| Agreement criteria are Agreement criteria are determined determined by by the the unit unit staff, staff, based based on on aa combination of combination of the the channel channel instrument instrument uncertainties, uncertainties, including including isolation, isolation, indication, and indication, and readability.
| |
| readability. If If a a channel channel is is outside outside the the criteria, criteria, itit may may be be an indication an indication that that the the transmitter transmitter or or the the signal signal processing processing equipment equipment has has drifted outside drifted outside its its limit.
| |
| limit. If If the the channels channels are are within within thethe criteria, criteria, itit isis an an indication that indication that the the channels channels are are OPERABLE.
| |
| OPERABLE. If If the the channels channels are are normally normally off scale off scale during during times times when surveillance is when surveillance is required, required, the the CHANNEL CHANNEL CHECK will CHECK will only only verify verify that that they they areare off off scale scale in in the the same same direction.
| |
| direction. Off Off scale low scale low current current loop loop channels channels are are verified verified to to be be reading reading at at the the bottom bottom of of the range the range andand not not failed failed downscale.
| |
| downscale.
| |
| The agreement The agreement criteria criteria includes includes an an expectation expectation of of one one decade decade of of overlap overlap when transitioning when transitioning between between neutron neutron flux flux instrumentation.
| |
| instrumentation. For For example, example, during a during a power power reduction reduction near near thethe bottom bottom of of the the scale scale forfor the the intermediate intermediate range monitors, range monitors, a a source source rangerange monitor monitor reading reading is is expected expected with with at at least least one decade one decade overlap.
| |
| overlap. WithoutWithout such such an an overlap, overlap, the the source source rangerange monitors monitors are considered are considered inoperable inoperable unless unless itit isis clear clear that that anan intermediate intermediate range range monitor inoperability monitor inoperability is is responsible responsible for for the the lack lack ofof the the expected expected overlap.overlap.
| |
| P h e Frequency,
| |
| [The Frequency, about about onceonce every every shift, shift, is is based based on on operating operating experience experience that demonstrates that demonstrates channel channel failure failure is is rare.
| |
| rare. Since Since the the probability probability of of two two random failures random failures in in redundant redundant channels channels in in any any 12 12 hour hour period period is is extremely extremely low, the low, the CHANNEL CHANNEL CHECK CHECK minimizes minimizes the the chance chance of of loss loss ofof protective protective function due function due to to failure failure of of redundant redundant channels. The CHANNEL CHECK supplements less supplements less formal, formal, but but more more frequent, frequent, chec s 0 channel OPERABILITY during OPERABILITY during normal normal operational operational use use of of the the displays displays associated associated with the with LCO's required the LCO's required channels.
| |
| channels. When When operating operating in in Required Required Action A.1, Action A.l, CHANNEL CHANNEL CHECK CHECK is is still still required.
| |
| required. However, However, in in this this BWOG STS BWOG STS B 3.3.9-4 B 3.3.9-4 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Source Range Source Range Neutron Neutron FluxFlux B 3.3.9 B 3.3.9 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)(continued) condition, a condition, a redundant redundant source source rangerange is is not not available available for for comparison.
| |
| comparison.
| |
| CHANNEL CHECK CHANNEL CHECK may may still still be be performed performed via via comparison comparison with with intermediate range intermediate range detectors, detectors, ifif available, available, andand verification verification thatthat the the OPERABLE source OPERABLE source range range channel channel is is energized energized andand indicating indicating a a value value consistent with consistent with current current unit unit status.
| |
| status.
| |
| SR 3.3.9.2 For source For source range range neutron neutron flux flux channels, channels, CHANNEL CHANNEL CALIBRATION CALIBRATION is is a a
| |
| complete check complete check and and readjustment readjustment of of the the channels channels from from thethe preamplifier preamplifier input to input to the the indicators.
| |
| indicators. This This test test verifies verifies the the channel channel responds responds to to measured parameters measured parameters within within thethe necessary necessary rangerange and and accuracy.
| |
| accuracy.
| |
| CHANNEL CALIBRATION CHANNEL CALIBRATION leaves leaves the the channel channel adjusted adjusted to to account account forfor instrument drift instrument drift to to ensure ensure that that the instrument channel the instrument channel remains remains operational operational between successive between successive tests.
| |
| tests.
| |
| The SR is The SR is modified modified by a Note by a Note excluding excluding neutron neutron detectors detectors from from CHANNEL CALIBRATION.
| |
| CHANNEL CALIBRATION. It It is is not not necessary necessary to to test test the the detectors detectors because generating because generating a meaningful test a meaningful test signal signal is is difficult.
| |
| difficult. The detectors are The detectors are of simple of simple construction, construction, andand any any failures failures in in the the detectors detectors will will bebe apparent apparent as change as change in in channel channel output.
| |
| output.
| |
| Frequency of rThe Frequency of [18] months is
| |
| [18] months is based based on on demonstrated demonstrated instrument instrument HANNEL CALIBRATION Lt;'HANNEL CALIBRATION reliability reliability over over an [I83 month an [18] month interval, interval, such such that that the instrument is not adversely affected by drift.
| |
| REFERENCES REFERENCES None.
| |
| BWOG STS BWOG STS B 3.3.9-5 Rev. 3.0, Rev. 03131104 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Intermediate Range Intermediate Range Neutron Neutron Flux Flux B 3.3.10 B 3.3.10 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| Required Action Required Action B.1 6.1 isis modified modified by by a a Note Note whichwhich permits permits plantplant temperature changes temperature changes providedprovided the the temperature temperature change change is is accounted accounted for for in the calculated SDM. Introduction of temperature changes, including in the calculated SDM. Introduction of temperature changes, including temperature increases temperature increases when when a a positive positive MTC MTC exists, exists, must must be be evaluated evaluated to to ensure they ensure they dodo not not result result inin aa loss loss ofof required required SDM. SDM.
| |
| SURVEILLANCE SURVEILLANCE 3.3.10.1 SR 3.3.10.1 SR REQUIREMENTS REQUIREMENTS Performance of Performance of the CHANNEL C the CHANNEL CHECK~ry HECK- p.:t!Ou~ensures our ensures that that a gross a gross failure failure of of instrumentation instrumentation has has not not occurred.
| |
| occurred. A A CHANNEL CHANNEL CHECK CHECK is normally is normally a a comparison comparison of of the the parameter parameter indicatedindicated on on one one channel channel to to aa similar parameter similar parameter on on other other channels.
| |
| channels. It It is is based based on on the the assumption assumption that that instrument channels instrument channels monitoring monitoring the the same same parameter parameter should should read read approximately the approximately the same same value.
| |
| value. Significant Significant deviations deviations between between the the two two instrument channels instrument channels could could be be anan indication indication of of excessive excessive instrument instrument drift drift in in one of one of the the channels channels or or of of something something even even more more serious.
| |
| serious. CHANNEL CHANNEL CHECK will CHECK detect gross will detect gross channel channel failure; failure; therefore, therefore, itit is is key key in in verifying verifying that the that the instrumentation instrumentation continuescontinues to to operate operate properly properly between between each each CHANNEL CALIBRATION.
| |
| CHANNEL CALIBRATION.
| |
| Agreement criteria are Agreement criteria are determined determined by by the the unit unit staff staff based based on on a a combination of combination of thethe channel channel instrument instrument uncertainties, uncertainties, including including isolation, isolation, indication, and indication, and readability.
| |
| readability. If a channel If a channel is is outside outside thethe criteria, criteria, itit may may be be an indication that the transmitter or the signal processing an indication that the transmitter or the signal processing equipment has equipment has drifted outside drifted outside its its limit.
| |
| limit. If If the the channels channels are are within the criteria, within the criteria, itit is is an an indication that indication that the the channels channels are OPERABLE.
| |
| are OPERABLE.
| |
| The agreement The agreement criteria criteria includes includes an an expectation expectation of of one one decade decade of of overlap overlap when transitioning between whentransitioning between neutron neutron flux flux instrumentation.
| |
| instrumentation. For For example, example, during a during a power power increase increase near near thethe top top ofof the the scale scale for for the the source source range range monitors, an monitors, an intermediate intermediate range range monitor monitor readingreading is is expected expected with with at at least least one decade one decade overlap.
| |
| overlap. Without Without such such an an overlap, overlap, the the intermediate intermediate range range monitors are monitors are considered considered inoperable inoperable unless unless itit is is clear clear that that a a source source rangerange monitor inoperability monitor inoperability is is responsible responsible for for the the lack lack ofof the the expected expected overlap.
| |
| overlap.
| |
| Further, during Further, during a a power power reduction reduction near near thethe bottom bottom of of the the scale scale forfor the the power range power range monitors, monitors, an an intermediate intermediate range range monitor monitor reading reading is is expected expected with at with at least least one one decade decade overlap.
| |
| overlap. Without Without such such anan overlap, overlap, the the intermediate range intermediate range monitors monitors are are considered considered inoperable inoperable unless unless itit is is clear clear a power that a that power rangerange monitor monitor inoperability inoperability is is responsible responsible for for the the lack lack ofof the the expected overlap.
| |
| expected overlap.
| |
| SWOG STS BWOG STS 3.3.10-3 B 3.3.10-3 B Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Intermediate Range Intermediate Range Neutron Neutron FluxFlux B 3.3.10 B 3.3.10 BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| Frequency, about Ghe Frequency, about once once every every shift, shift, is is based based on on operating operating experience experience lThatat demonstrates demonstrates channel channel failure failure is is rare.
| |
| rare. Since Since thethe probability probability of of two two random failures random failures in in redundant redundant channels channels in in any any 1212 hour hour period period is is extremely extremely 6@
| |
| low, the low, the CHANNEL CHANNEL CHECK CHECK minimizes minimizes the the chance chance of of loss loss of of protective protective function due function due to to failure failure of of redundant channe9The CHANNEL redundant channeyThe CHANNEL CHECK CHECK supplements supp ements less ess formal, ormal, butbut more more frequent, frequent, checks checks of of channel channel OPERABILITY during OPERABILITY during normal normal operational operational use use of of the the displays displays associated associated with with the LCO's required the LCO's required channels.
| |
| channels.
| |
| When operating When operating in in Required Required Action Action A.1, A.1, CHANNEL CHANNEL CHECK CHECK is is still still required. However, required. However, in in this this condition, condition, a a redundant redundant intermediate intermediate range range isis not available not available for for comparison.
| |
| comparison. CHANNEL CHANNEL CHECK CHECK may may still still be be performed performed via comparison via comparison with with power power or or source source rangerange detectors, detectors, if if available, available, and and verification that verification that the the OPERABLE OPERABLE intermediate intermediate range range channel channel is is energized energized and indicates and indicates a a value value consistent consistent with with current current unit unit status.
| |
| status.
| |
| SR 3.3.10.2 For intermediate For intermediate range range neutron neutron flux flux channels, channels, CHANNEL CHANNEL CALIBRATION CALIBRATION is a is a complete complete check check and and readjustment readjustment of of the the channels, channels, from from the the preamplifier input preamplifier input to to the the indicators.
| |
| indicators. This This test test verifies verifies thethe channel channel responds to responds to a a measured measured parameter parameter within the necessary within the necessary range range and and accuracy. CHANNEL accuracy. CHANNEL CALIBRATION CALIBRATION leaves leaves thethe channel channel adjusted adjusted to to account for account for instrument instrument drift drift to to ensure ensure that that the the instrument instrument channelchannel remains remains operational between operational between successive successive tests.tests.
| |
| The SR The is modified SR is modified by by a a Note Note excluding excluding neutron neutron detectors detectors from from CHANNEL CALIBRATION.
| |
| CHANNEL CALIBRATION. It It is is not not necessary necessary to to test test the the detectors detectors because generating because generating a a meaningful meaningful test test signal signal isis difficult.
| |
| difficult. In In addition, addition, thethe detectors are are of of simple simple construction, construction, and and an~ailures an failures in in the the detectors detectors will will detectors be apparent be apparent as operating experience operating cycle and cycle
| |
| [I81 month
| |
| [18]
| |
| and is as a a change experience and is justified change in justified by month interval interval such in channel channel output.
| |
| and consistency consistency with demonstrated instrument by demonstrated such that that the the instrument L
| |
| output. TheThe Frequency with tt e Frequency is e typical typical industry instrument reliability instrument is is not reliability over not adversely is based based on industry refueling refueling over an adversely affected an affected by on by L@ rift.
| |
| REFERENCES REFERENCES None.
| |
| None.
| |
| BWOG STS BWOG STS B 3.3.10-4 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EFlC Instrumentation EFIC Instrumentation B 3.3.11 B 3.3.1 1 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| D.1, D.2.1, D.2.2, E.1, 0.1,0.2.1,0.2.2, E.1, and and F.1F.l If the If the Required Required Actions Actions cannotcannot be be met met within within thethe required required Completion Completion Time or Time or ifif more more than than two two channels channels are are inoperable inoperable in in one one or or more more Functions, the Functions, the unit unit must must be be placed placed in in aa MODE MODE or or condition condition in in which which the the requirement does requirement does not not apply.
| |
| apply. This This isis done done by by placing placing the the unit unit in in aa nonapplicable MODE nonapplicable MODE for for the the particular particular Function.
| |
| Function. The The nonapplicable nonapplicable MODE is MODE is toto open open the the CRD CRD trip trip breakers breakers for for Function Function 1.a, MODE 44 for I.a, MODE for Function 1.b, Function l.b, less less than than 10% 10% RTP RTP forfor Function Function 1.d, l.d, and and SG pressure less SG pressure less than 750 than 750 psigpsig forfor all all other other Functions.
| |
| Functions. The The allowed allowed Completion Completion Times Times are are reasonable, based reasonable, based on on operating operating experience, experience, to to reach reach the the required required unit unit conditions from conditions from full power conditions full power conditions in in an an orderly orderly manner manner and and without without challenging unit challenging unit systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE A Note indicates A Note indicates that that the SRs for the SRs for each each EFIC EFlC instrumentation instrumentation FunctionFunction REQUIREMENTS REQUIREMENTS are identified are identified in in the SRs column the SRs column of of Table Table 3.3.11-1.
| |
| 3.3.1 1-1. All Functions are All Functions are subject to subject to CHANNEL CHANNEL CHECK, CHECK, CHANNELCHANNEL FUNCTIONAL FUNCTIONAL TEST, TEST, and and CHANNEL CALIBRATION.
| |
| CHANNEL CALIBRATION. The The SG SG -- Low Low Level Level Function Function is is the the only only Function that Function that was was modeled modeled in in transient transient analysis, analysis, and and thus thus is is the the only only EFWEFW Initiation Function Initiation Function subjected subjected to to response response time testing. Response time testing. Response time time testing is testing is also also required required for for Main Main Steam Steam LineLine andand MFWMFW Isolation.
| |
| Isolation.
| |
| Individual EFIC Individual EFlC subgroup subgroup relays relays mustmust also also bebe tested, one at tested, one at aa time, time, to to verify the verify the individual individual EFIC EFlC components components will actuate when will actuate required. Some when required. Some components cannot components cannot be be tested tested at at power power since since their their actuation actuation mightmight leadlead to to unit trip unit trip oror equipment equipment damage. damage. These These are are specifically specifically identified identified andand mustmust be tested be tested when when shut shut down.
| |
| down. The The various various SRsSRs account account for for individual individual functional differences functional differences and and forfor test test frequencies frequencies applicable applicable specifically specifically to to the Functions the Functions listed listed inTable 3.3.1 1-1. The in Table 3.3.11-1. The operational operational bypasses bypasses associated with associated with each each EFICEFlC instrumentation instrumentation channel channel are are also also subject subject to to these SRs these SRs to to ensure ensure OPERABILITY OPERABILITY of of the the EFIC EFIC instrumentation instrumentation channel.channel.
| |
| SR 3.3.11.1 Performance of Performance of the the CHANNEL CHANNEL C CHECK~ry H E C K ~ W l19~ur§)ensures
| |
| ~ o~u r~~ ~ e n~s u r that that es gross failure a gross a failure of of instrumentation instrumentation has has not occurred. A not occurred. CHANNEL CHECK A CHANNEL CHECK is normally is normally a a comparison comparison of of the the parameter parameter indicated indicated on on one one channel channel to a to a similar parameter similar parameter on on other other channels.
| |
| channels. It It is is based based on on the the assumption assumption that that instrument channels instrument channels monitoring monitoring the the same same parameter parameter should should readread BWOG STS BWOG STS BB 3.3.11-16 3.3.1 1-16 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EFlC Instrumentation EFIC Instrumentation B 3.3.11 B 3.3.11 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued) approximately the approximately the same same value.
| |
| value. Significant Significant deviations deviations between between the the two two instrument channels instrument channels could could be be anan indication indication of of excessive excessive instrument instrument drift drift in in one of one of the the channels channels or or ofof something something even even moremore serious.
| |
| serious. CHANNEL CHANNEL CHECK will CHECK detect gross will detect gross channel channel failure; therefore, it failure; therefore, it is is key key inin verifying verifying that the that the instrumentation instrumentation continues continues to to operate operate properly properly between between each each CHANNEL FUNCTIONAL CHANNEL FUNCTIONAL TEST TEST and and CHANNEL CHANNEL CALIBRATION.
| |
| CALIBRATION.
| |
| Agreement Agreement criteriacriteria are are determined determined by by the the unit unit staff, staff, based based on on a a combination of combination of thethe channel channel instrument instrument uncertainties, uncertainties, including including isolation, isolation, indication, and indication, and readability.
| |
| readability. If If a a channel channel is is outside outside the the criteria, criteria, itit may may be be an indication an indication that that thethe transmitter transmitter or or the the signal signal processing processing equipment equipment has has drifted outside drifted outside its its limit.
| |
| limit. If If the the channels channels are are within within thethe criteria, criteria, itit is is an an indication that indication that thethe channels channels are are OPERABLE.
| |
| OPERABLE. If If the the channels channels are are normally normally off scale off scale during during timestimes whenwhen surveillance surveillance is is required, required, the the CHANNEL CHANNEL CHECK will CHECK will only only verify verify that that they they are are off off scale scale in in the the same same direction.
| |
| direction. Off Off scale low scale low current current loop loop channels channels are are verified verified to to be be reading reading at at the the bottom bottom of of the range the range andand not not failed failed downscale.
| |
| downscale.
| |
| E h e Frequency, Uhe Frequency, about about onceonce every every shift, shift, isis based based on on operating operating experience experience that demonstrates that demonstrates channel channel failure failure is is rare.
| |
| rare. Since Since the the probability probability of of two two random failures random failures in in redundant redundant channels channels in in any any 12 12 hour hour period period is is extremely extremely low, the low, the CHANNEL CHANNEL CHECK CHECK minimizes minimizes the the chance chance of of loss loss ofof protective protective function due function due toto failure failure of of redundant channels+The CHANNEL redundant channels~The CHAN C supplements less supplements less formal, formal, but but more more frequent, frequent, checks of channel operability during normal during normal operational operational use use of of the the displays associa with the LC required channels.
| |
| required channels. r nSer.{.; Z SR 3.3.11.2 A CHANNEL FUNCTIONAL A CHANNEL FUNCTIONAL TEST TEST verifies verifies thethe function function of of the the required required trip, interlock, trip, interlock, and and alarm alarm functions functions of of the the channel.
| |
| channel. A A successful successful test test of of the the contact(s) of required contact(s) required of aa channel channel relayrelay may may be be performed performed by by the the verification of verification of the the change change of of state state of of a a single single contact contact of of the the relay.
| |
| relay. This This clarifies what clarifies what is is an an acceptable acceptable CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST of of aa relay.
| |
| relay.
| |
| This is This is acceptable acceptable because because all all of of the the other other required required contacts contacts of of the the relay relay are verified are verified by other Technical by other Technical Specifications Specifications and and non-Technical non-Technical Specifications tests Specifications tests at at least least once once per per refueling refueling interval interval with with applicable applicable extensions. Setpoints extensions. Setpoints for for both both trip trip and and bypass bypass removal removal functions functions must must be be found within found within the the Allowable Allowable Value Value specified specified in in the the LCO.
| |
| LCO. (Note (Note thatthat thethe Allowable Values for Allowable Values for the the bypass bypass removal removal functions functions are are specified specified in in the the Applicable MODES Applicable MODES or or Other Other Specified Specified Condition Condition columncolumn of of STS BWOG STS BWOG BB 3.3.11-17 3.3.11-17 Rev. 3.0, Rev. 03/31/04 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EFlC Instrumentation EFIC Instrumentation B 3.3.11 B 3.3.1 1 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)(continued) 3.3.11-1 as Table 3.3.11-1 Table as limits limits on on applicability applicability for for the the trip trip Functions.)
| |
| Functions.) Any Any setpoint adjustment setpoint adjustment shallshall bebe consistent consistent with with the the assumptions assumptions of of the the current unit current unit specific setpoint analysis.
| |
| specific setpoint analysis.
| |
| E h e Frequency (ihe Frequency of 31 days of 31 days isis based based on on unit unit operating operating experience experience with with regard to regard to channel channel OPERABILITY OPERABILITY and and drift, drift, which which demonstrates demonstrates that that failure of failure of more more than than one one channel channel of of aa given given function function in in any any 3131 day day interval interval is a rare event.
| |
| SR 3.3.11.3 CHANNEL CALIBRATION CHANNEL CALIBRATION is is a a complete complete checkcheck of of the the instrument instrument channelchannel including the including the sensor.
| |
| sensor. The The test test verifies verifies thethe channel channel responds responds to to aa measured parameter measured parameter withinwithin the the necessary necessary range range and and accuracy.
| |
| accuracy.
| |
| CHANNEL CALIBRATION CHANNEL CALIBRATION leaves leaves the the channels channels adjusted adjusted to to account account for for instrument drift instrument drift to to ensure ensure that that the the instrument instrument channel channel remains remains operational operational between successive between successive tests.
| |
| tests. CHANNEL CHANNEL CALIBRATION CALIBRATION shall shall find find that that measurement errors measurement errors andand bistable setpoint errors bistable setpoint errors are within the are within the assumptions of assumptions of the unit specific the unit setpoint analysis.
| |
| specific setpoint analysis. CHANNEL CHANNEL CALIBRATIONS must CALIBRATIONS must bebe performed performed consistent consistent withwith the the assumptions assumptions of of the unit the unit specific setpoint analysis.
| |
| specific setpoint analysis.
| |
| E h e Frequency
| |
| [Q,e Frequency is is based based on on the the assumption assumption of of an an [18]
| |
| 1181 month month calibration calibration interval in in the the determination determination of of the the magnitude magnitude of of equipment equipment drift drift in in the the interval setpoint analysis.
| |
| setpoint analysis. ~er.! 9 SR 3.3.11.4 This SR This SR verifies verifies individual individual channel channel actuation actuation response response times times are are less less than than or equal or equal toto the the maximum maximum value value assumed assumed in in the the accident accident analysis.
| |
| analysis.
| |
| Response time Response time testing testing acceptance acceptance criteriacriteria are are included included in in "Unit "Unit Specific Specific Response Time Response Time Acceptance Acceptance Criteria" Criteria" (Ref.
| |
| (Ref. 6).
| |
| 6).
| |
| Individual component Individual component response response timestimes are are not not modeled modeled in in the the analysis.
| |
| analysis.
| |
| The analysis The analysis models models the the overall overall or or total total elapsed elapsed time, time, from from thethe point point at at which the which the parameter parameter exceeds exceeds the the actuation setpoint value actuation setpoint value at at the the sensor, sensor, to the to the point point at at which which thethe end end device device is is actuated.
| |
| actuated.
| |
| BWOG STS BWOG STS B 3.3.11-18 3.0, 03/31/04 Rev. 3.0,03/31/04 Rev.
| |
| | |
| TSTF-425, Rev. 3 EFIC Instrumentation EFIC Instrumentation B 3.3.11 B 3.3.11 BASES BASES REQUIREMENTS (continued)
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE (continued)
| |
| [~EFICRESPONSE
| |
| [EFIC RESPONSE TIME TIME teststests are are conducted conducted on on an an [18]
| |
| (181 month month STAGGERED TEST STAGGERED TEST BASIS.
| |
| BASIS. Testing Testing ofof the the final final actuation actuation devices, devices, which which make up make up the the bulk bulk of of the the EFIC EFlC RESPONSE RESPONSE TIME, TIME, is is included included inin the the testing testing of each of each channel.
| |
| channel. Therefore, Therefore, staggered staggered testing testing results results inin response response time time verification of verification of these these devices devices every [I81 months.
| |
| every [18] months. The The [18]
| |
| [18] month month test test Frequency is Frequency is based based onon unit unit operating operating experience, which shows experience, which shows that that random failures random failures of of instrumentation instrumentation components components causing causing serious serious response response time degradation, time degradation, but but not not channel channel failure, failure, are are infrequent infrequent occurrences.
| |
| occurrences.
| |
| EFlC RESPONSE EFIC RESPONSE TIMES TIMES cannot be determined cannot be determined at power since at power since equipment operation required.&
| |
| REFERENCES REFERENCES 1.
| |
| 1.
| |
| 2.
| |
| 2.
| |
| FSAR, Section FSAR, 10 CFR 10 CFR 50.49.
| |
| 50.49.
| |
| is Section [14.1].
| |
| [14.1]. c~~~~~~ 7 equipment operation is required.-e:~---*_* ;-~-------:--~-""
| |
| ~r15~. . . +-::t),...
| |
| 2) 3.
| |
| : 3. [Unit Name],
| |
| [Unit Name], [Unit
| |
| [Unit Specific Specific Setpoint Setpoint Methodology].
| |
| Methodology].
| |
| : 4. FSAR, Chapter FSAR, Chapter [7].
| |
| [7].
| |
| 5.
| |
| : 5. IEEE-279-1971, April IEEE-279-1971, 1972.
| |
| April 1972.
| |
| 6.
| |
| : 6. [Unit Specific
| |
| [Unit Specific Response Response Time Time Acceptance Criteria].
| |
| Acceptance Criteria].
| |
| BWOG STS BWOG STS B 3.3.11-19 Rev. 3.0, Rev. 3.0, 03/31/04 03131104
| |
| | |
| TSTF-425, Rev. 3 EFlC Manual EFIC Manual Initiation Initiation 3.3.12 B 3.3.12 B
| |
| BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| With one With one or or both both manual manual initiation initiation switches switches of of one one oror more more EFICEFlC Functionts) inoperable Function(s) inoperable in in both both actuation actuation channels, channels, one one actuation actuation channel channel for each for each Function Function must must be be restored restored to to OPERABLE OPERABLE status status within within 1 1 hour.
| |
| hour.
| |
| With the With channel restored, the channel restored, the the second second channel channel mustmust be be placed placed in in the the tripped condition tripped condition within within 7272 hours hours (Required (Required Action A.l). With Action A.1). With the the channel channel in the in the tripped tripped condition, condition, the the single-failure single-failure criterion criterion isis met met andand the the operator operator can still can still initiate initiate one one actuation actuation channel channel given given a a single single failure failure inin the the other other channel. The channel. The Completion Completion Time Time allotted allotted to to restore restore thethe channel channel allowsallows thethe operator to operator to take take all all the the appropriate appropriate actions actions for for the the failed failed channel channel and and still still ensures that ensures that thethe risk risk involved involved in in operating operating with with the the failed failed channel channel is is acceptable.
| |
| acceptable.
| |
| C.l and C.1 and C.2 C.2 If Required If Required ActionAction A.l A.1 oror Required Required Action B . l cannot Action B.1 cannot be be met met within within thethe required Completion Time, the unit must be brought required Completion Time, the unit must be brought to a MODE in which to a MODE in which L C 0 does the LCO the does not not apply.
| |
| apply. To To achieve achieve this this status, status, the the unit unit must must be be brought brought to at to at least least MODEMODE 3 3 within within 6 6 hours hours andand to MODE 4 to MODE 4 within within 12 12 hours.
| |
| hours. The The allowed Completion allowed Completion Times Times are are reasonable, reasonable, basedbased on operating on operating experience, to experience, to reach reach thethe required required MODES MODES from from full full power power conditions conditions in in an an orderly manner orderly manner and and without without challenging challenging unitunit systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE 3.3.12.d SR 3.3.12.1 SR REQUIREMENTS REQUIREMENTS This SR This SR requires requires the the performance performance of of a a CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST to to ensure that ensure that thethe channels channels can can perform perform their their intended intended functions.
| |
| functions. A A successful test successful test of of the the required contact(s) of required contact(s) of a a channel channel relayrelay may may be be performed by performed by the the verification verification of of the the change change of of state state of a single of a single contact contact of of the relay.
| |
| the relay. ThisThis clarifies clarifies what what is is an an acceptable acceptable CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TEST of TEST of aa relay.
| |
| relay. ThisThis isis acceptable acceptable because because all all of of the the other other required required contacts of contacts of the the relay relay are are verified verified by by other other Technical Technical Specifications Specifications and and non-Technical Specifications non-Technical Specifications tests tests at at least least once once per per refueling refueling interval interval with with applicable extensions.
| |
| applicable extensions. For For MFWMFW and and Main Main Steam Steam LineLine Isolation, Isolation, the the test test need not need not include include actuation actuation of of the the end end device.
| |
| device. ThisThis isis due due to to the the risk risk of of aa unit transient unit transient caused caused by by the the closure closure of of valves valves associated associated with with MFWMFW and and g,
| |
| @;nSe
| |
| -:ti tr
| |
| ~ Frequency Main Steam Main Steam Line demon~trates Frequency of demonstrates the Line Isolation of 31 Isolation or days is 31 days the rarity or actuating is based rarity of actuating EFW based on of more EFW during on operating more than during testing operating experience than one testing at experience that one channel channel failing that failing within at power.
| |
| within thethe same c
| |
| power. f!.he same The 31
| |
| --I_._ day interval3
| |
| _,~~.!ay Interva!~i -
| |
| REFERENCES REFERENCES 1.
| |
| : 1. IEEE-279-1971. A IEEE-279-1971, April 1972.
| |
| ~ r i1972.
| |
| l BWOG STS BWOG STS B 3.3.12-3 B 3.3.12-3 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EFlC Logic EFIC Logic B 3.3.13 B 3.3.13 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| The EFIC The EFlC System System has has notnot been been analyzed analyzed for for failure failure of of one one train train ofof one one Function and Function and thethe opposite opposite train train ofof the the same same Function.
| |
| Function. In In this this condition, condition, the potential the potential for for system system interactions interactions that that disable disable heat heat removal removal capability capability on EFW on EFW has has notnot been been evaluated.
| |
| evaluated. Consequently, Consequently, any any combination combination of of failures in failures in both channels A both channels and B A and B is is not not covered covered by by Condition Condition A and must A and must be addressed by be addressed by entry entry into L C 0 3.0.3.
| |
| into LCO 3.0.3.
| |
| 6.1 and 8.1 and B.2B.2 If Required If Action A Required Action A.1. l cannot cannot be be met met within within thethe required required Completion Completion Time, the Time, the unit unit must must be be brought brought to to a MODE in a MODE in which which the the LCO L C 0 does does notnot apply. To apply. To achieve achieve this this status, status, thethe unit unit must must be be brought brought to to at at least least MODE within 66 hours MODE 33 within hours and and to MODE 44 within to MODE within 12 12 hours.
| |
| hours. TheThe allowed allowed Completion Times Completion Times areare reasonable, reasonable, based based on on operating operating experience, experience, to to reach the reach the required required MODES MODES from from full full power power conditions conditions in in an an orderly orderly manner and manner and without challenging unit without challenging unit systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE SR 3.3.13.1 SR 3.3.13.1 REQUIREMENTS REQUIREMENTS This SR This SR requires requires thethe performance performance of of aa CHANNEL CHANNEL FUNCTIONALFUNCTIONAL TEST TEST to to ensure that ensure that the the channels channels can can perform perform theirtheir intended intended functions.
| |
| functions. This This test test verifies MFW verifies MFW and and Main Main Steam Steam Line Line Isolation Isolation and and EFWEFW initiation initiation automatic automatic actuation logics actuation logics are functional. A are functional. successful test A successful test of of the the required required contact(s) of contact(s) of a a channel channel relay relay maymay be be performed performed by by the the verification verification of of the the change of change of state state of a single of a single contact contact of of the the relay.
| |
| relay. ThisThis clarifies clarifies what what is is an an acceptable CHANNEL acceptable CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST of of a a relay.
| |
| relay. This This isis acceptable acceptable because all because all of of the the other other required required contacts contacts of of the the relay relay are are verified verified by by other other Technical Specifications Technical Specifications and and non-Technical non-Technical Specifications Specifications tests tests at at least least once per once per refueling refueling interval interval withwith applicable applicable extensions.
| |
| extensions. This This test test simulates simulates the required the required inputs inputs to to the the logic logic circuit circuit and and verifies verifies successful successful operation operation of of the automatic the automatic actuation actuation logic.
| |
| logic. TheThe test test need need not not include include actuation actuation of of the the end device.
| |
| end device. ThisThis isis due due to to the the risk risk ofof aa unit unit transient transient caused caused by by the the closure of valves associated of valves associated with MFW an~. an ain Steam Steam Line Line Isolation lsolation oror closure actuation of actuation based on based of EFW on operating more than one more during testing EFW during operating experience, one channel with MFW testing at experience, which channel failing at power.
| |
| power. The which has failing within within the C ain The Frequency Frequency of emonstrated the has emonstrated the same same 31 31 day of 31 day interval.
| |
| 31 days the rarity days is rarity of interval. ~
| |
| of is REFERENCES REFERENCES I. FSAR.
| |
| : 1. FSAR, Chapter Chapter [7].[7]. ~~
| |
| QnsertY BWOG STS BWOGSTS B 3.3.13-5 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 EFIC -
| |
| EFlC - EFWEFW -- Vector Vector Valve Valve Logic Logic BB 3.3.14 3.3.14 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| B.l and 8.1 B.2 and B.2 If Required If Action A.1 Required Action cannot be A.1 cannot be met met within within the the required required Completion Completion Time, the Time, the unit unit must must be be brought brought to to aa MODE MODE in in which which the the LCO L C 0 does does not not apply. To apply. To achieve achieve this this status, status, the the unit unit must must bebe brought brought to to at at least least MODE 3 MODE 3 within within 6 6 hours hours and and toto MODE MODE 4 4 within within 12 12 hours.
| |
| hours. The The allowed allowed Completion Times Completion Times areare reasonable, reasonable, basedbased on on operating operating experience, experience, to to reach the reach the required required unitunit conditions conditions from from full full power power conditions conditions inin an an orderly orderly manner and manner and without without challenging challenging unitunit systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE SR 3.3.14.1 SR 3.3.14.1 REQUIREMENTS REQUIREMENTS c m~1~.
| |
| SR 3.3,14.1 SR
| |
| @!1 & .This 3.3.14.1 is logic performs logic is the performs its
| |
| ~erformanceof the performance
| |
| ~ h /test test s demonstrates its function of aa CHANNEL CHANNEL FUNCTIONAL demonstrates that function as as desired.
| |
| desired. A that the FUNCTIONAL TEST EFlC -- EFW the EFIC successful test A successful test of of the TEST EFW -- vector vector valve the required required valve contact(s) of contact(s) a channel of a channel relay relay may may be be performed performed by by the the verification verification ofof the the change of change of state state of a single of a single contact contact ofof the the relay.
| |
| relay. This This clarifies clarifies what what isis an an CHANNEL FUNCTIONAL acceptable CHANNEL acceptable FUNCTIONAL TEST TEST of of a a relay. This is relay. This is acceptable acceptable because all because all of of the the other other required required contacts contacts of of the the relay relay are are verified verified byby other other Technical Specifications Technical Specifications and and non-Technical non-Technical Specifications Specifications tests tests atat least least once per once per refueling refueling interval interval with with applicable extensions. @e Frequency applicable extensions.l!Ee Frequency is is based on based on operating one channel one operating experience channel failing experience that failing within within the the same that demonstrates same 31 demonstrates the 31 day day interval.
| |
| interval. <
| |
| the ranty rar~tyof Z
| |
| more than of more than REFERENCES REFERENCES None.
| |
| None. 1 BWOG STS BWOG STS B 3.3.14-4 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RB Purge RB Isolation -- High Purge Isolation High Radiation Radiation B 3.3.15 B 3.3.15 BASES BASES SURVEILLANCE SURVEILLANCE SR 3.3.15.1 SR 3.3.15.1 REQUIREMENTS REQUIREMENTS SR 3.3.15.1 SR 3.3.15.1 is is the the performance performance of of the the CHANNEL CHANNEL CHECK CHECK for for the RB the RB purge isolation -- high purge isolation high radiation instrumentation~n~ev~hoy@to radiation instrumentationn2'eryftho)ll1':gto ensure that ensure that a a gross gross failure failure of of instrumentation instrumentation has has not not occurred.
| |
| occurred. A A CHANNEL CHECK CHANNEL CHECK is is normally normally a a comparison comparison of of the the parameter parameter indicatedindicated on one on one channel channel to to a a similar similar parameter parameter on on other other channels.
| |
| channels. It It is is based based on on the assumption the assumption that that instrument instrument channelschannels monitoring monitoring the the same same parameter parameter should read should read approximately approximately the the same same value.
| |
| value. Significant Significant deviations deviations between two between two instrument instrument channelschannels could could be be an an indication indication of of excessive excessive instrument drift instrument drift in in one one of of the the channels channels or or of of something something even even more more serious.
| |
| serious.
| |
| Performance of Performance of thethe CHANNEL CHANNEL CHECK CHECK helps helps toto ensure ensure that that the the instrumentation continues instrumentation continues to to operate operate properly properly between between each each CHANNEL CHANNEL CALIBRATION. The CALIBRATION. The highhigh radiation radiation instrumentation instrumentation shouldshould be be compared compared to similar to similar unitunit instruments instruments located located throughout throughout the the unit.
| |
| unit. If If the the radiation radiation monitor uses monitor uses keepkeep alivealive sources sources or or check check sources sources OPERABLE OPERABLE from from the the control room, control room, the the CHANNEL CHANNEL CHECK CHECK should should also also note note thethe detector's detector's response to response to these sources.
| |
| these sources.
| |
| Agreement Agreement criteria criteria are are determined determined by by the unit staff, the unit staff, based based on on a a combination of combination of the the channel channel instrument instrument uncertainties, uncertainties, including including isolation, isolation, indication, and indication, and readability.
| |
| readability. If If a a channel channel is is outside outside the the criteria, criteria, itit may may bebe an indication an indication that that thethe transmitter transmitter or or the the signal signal processing processing equipment equipment has has drifted outside drifted outside its its limit.
| |
| limit. If If the the channels channels are are within the criteria, within the criteria, itit isis an an indication that indication that thethe channels channels are OPERABLE. fie Frequency, are OPERABLE.l!h.e Frequency, about about once once every shift, every shift, is is based based on on operating operating experience experience that that demonstrates demonstrates channel channel failure is failure is rare.
| |
| rare. [At [At this this unit, unit, the the following following administrative administrative controls controls and and design features design features (e.g., (e.g., downscale downscale alarms) immediatel alert operators to loss of loss of function.]
| |
| function.] ~ -"In..Serl2 SR 3.3.15.2 g~_§Ftr~gUir~sthe performance performance of of a CHANNEL a CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST o e/evfry f!2 dllmto to ensure ensure that that the the channels channels can can perform perform their their intended functions. This This test test verifies verifies thethe capability capability of of the the instrumentation instrumentation to provide to provide the the RB RB isolation.
| |
| isolation. A successful test A successful test of of the the required required contact(s) contact(s) of of a channel a channel relay relay may may be be performed performed by by the the verification verification of of the the change change of of state of state of a a single single contact contact of of the the relay.
| |
| relay. This This clarifies clarifies what what is is an an acceptable acceptable CHANNEL FUNCTIONAL CHANNEL FUNCTIONAL TEST TEST of of aa relay.
| |
| relay. This This isis acceptable acceptable because because all of all of the the other other required required contacts contacts of of the the relay relay are are verified verified by by other other BWOG STS BWOG STS B 3.3.15-5 B 3.3.15-5 Rev. 3.0, Rev. 3.0, 03/31/04 03131104
| |
| | |
| TSTF-425, Rev. 3 RB Purge RB Isolation -- High Purge Isolation High Radiation Radiation B 3.3.15 B 3.3.15 BASES BASES REQUIREMENTS (continued)
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE (continued)
| |
| Technical Specifications Technical Specifications and and non-Technical non-Technical Specifications Specifications tests tests atat least least once per once per refueling refueling interval interval with with applicable applicable extensions.
| |
| extensions. Any setpoint Any setpoint adjustment shall adjustment shall bebe consistent consistent with with the the assumptions assumptions of of the the current current unit unit setpoint analysis.
| |
| specific setpoint specific analysis.
| |
| In MODES In MODES 1, 1, 2, 2, 3, 3, and and 4,4, the the test test does does notnot include include thethe actuation actuation of of the the purge valves, purge valves, as as these these valves valves are are normally normally closed.
| |
| closed.
| |
| E h e justification
| |
| [he justification ofof a 92 day a 92 day Frequency, Frequency, in in view view ofof the the fact fact that that there there isis only one only one channel.
| |
| channel, is is Draft Draft NUREG-1366 NUREG-I366 (Ref. 4). ~:
| |
| (Ref. 4).
| |
| n,ser .2,.
| |
| .t r)
| |
| SR 3.3.15.3 CHANNEL CALIBRATION CHANNEL CALIBRATION is is aa complete complete check check ofof the the instrument instrument loop loop and and the sensor.
| |
| the sensor. TheThe test test verifies verifies that that the the channel channel responds responds to to aa measured measured parameter within parameter within the the necessary necessary range range and and accuracy.
| |
| accuracy. CHANNEL CHANNEL CALIBRATION leaves CALIBRATION leaves thethe channel channel adjusted adjusted to to account account for for instrument instrument drifts between drifts between successive successive calibrations calibrations to to ensure ensure that that the the channel channel remains remains operational between operational between successive successive tests. tests. CHANNEL CHANNEL CALIBRATIONS CALIBRATIONS must must be performed be performed consistent consistent with with thethe unit unit specific setpoint analysis.
| |
| specific setpoint analysis.
| |
| The CHANNEL The CALIBRATION is CHANNEL CALIBRATION is aa complete complete check check of of the the instrumentation instrumentation and detector.
| |
| and detector. In MODES MODES 1, 1,2, and 4, 3, and 2, 3. 4, the CHANNEL CALIBRATION the CHANNEL CALIBRATION does not does not include include the the actuation actuation of of the the purge purge valves, valves, since since they they areare normally closed.
| |
| normally closed.
| |
| ~e E h e [18]
| |
| 1181 month month Frequency Frequency is is based based on on the the need need toto perform perform thisthis Surveillance under Surveillance under the the conditions conditions that that apply apply during during a a unit unit outage outage and and the the potential for for an an unplanned unplanned transient transient if if the the Surveillance Surveillance were performed
| |
| +-----
| |
| potential were performed with the with the reactor reactor at at power.
| |
| power. <7---
| |
| REFERENCES REFERENCES 1.
| |
| : 1. FSAR, Section FSAR, Section [14.1].
| |
| [14.1].
| |
| 2.
| |
| : 2. 10 CFR 10 50.49.
| |
| CFR 50.49.
| |
| 3.
| |
| : 3. [Unit Specific
| |
| [Unit Specific Setpoint Setpoint Methodology].
| |
| Methodology].
| |
| 4.
| |
| : 4. Draft NUREG-1366.
| |
| Draft NUREG-1366.
| |
| BWOG STS BWOG STS B 3.3.15-6 Rev. 3.0, Rev. 03/31/04 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Control Room Control Room Isolation -
| |
| Isolation - High High Radiation Radiation B 3.3.16 B 3.3.16 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| Required Action Required Action C.2 places places thethe core core in in aa safe safe and and stable stable configuration configuration in in which itit is which is less less likely likely to to experience experience an an accident accident that that could could result result inin a a
| |
| significant release significant release of of radioactivity.
| |
| radioactivity. The The reactor reactor must must be be maintained maintained in in these conditions these conditions until until the the automatic automatic isolation isolation capability capability is is returned returned to to operation or operation or when when manual manual action action places places one one train train ofof the the CREVS CREVS into into the the emergency recirculation emergency recirculation mode. mode. The The Completion Completion Time Time ofof "Immediately" "Immediately" for for Required Action Required Action C.2.1 C.2.1 and and Required Required Action C.2.2 is Action C.2.2 is consistent consistent with the with the urgency of urgency of the the situation situation and and accounts accounts for the high for the high radiation radiation function, function, which provides the which provides the only only automatic automatic Control Control Room Room Isolation Isolation Function Function capable of capable of responding responding to to radiation radiation release release due due toto a a fuel fuel handling handling accident accident
| |
| [involving handling
| |
| [involving handling recently recently irradiated irradiated fuel].
| |
| fuel]. TheThe Completion Completion Time Time does does not preclude not preclude placingplacing any any fuel fuel assembly assembly into into a a safe safe position position before before ceasing ceasing any such any such movement.
| |
| movement.
| |
| Note that Note that inin certain certain circumstances, circumstances, such such as as fuel fuel handling handling [involving
| |
| [involving handling recently handling recently irradiated irradiated fuel]
| |
| fuel] in the fuel in the fuel building building during during powerpower operation, both Condition A and Condition operation, both Condition A and Condition C may apply in the event C may apply in the event ofof channel failure.
| |
| channel failure.
| |
| SURVEILLANCE SURVEILLANCE SR 3.3.16.1 SR 3.3.16.1 REQUIREMENTS REQUIREMENTS SR 3.3.16.1 SR 3.3.16.1 is is the the performance performance of of aa CHANNEL CHANNEL CHECK CHECK for for the the Control Control Room Isolation Room Isolation - High- High Radiation Radiation actuation actuation instrumentation d-6 instrumentation p-ncp:::ev@
| |
| -to
| |
| {r2di~to ensure ensure that that aa gross gross failure failure of of instrumentation instrumentation has has notnot occurred. A occurred. A CHANNEL CHANNEL CHECK CHECK is is normally normally a a comparison comparison of of the the parameter indicated parameter indicated on on one one channel channel to to aa similar similar parameter parameter on on other other channels. It channels. It is is based based on on the the assumption assumption that that instrument instrument channels channels monitoring the monitoring the same same parameter parameter should should read read approximately approximately the the same same value. Significant value. Significant deviations deviations between between the the two two instrument instrument channels channels couldcould be an be an indication indication of of excessive excessive instrument instrument driftdrift inin one one ofof the the channels channels or or of of something even something even more more serious.
| |
| serious.
| |
| Performance of Performance of the the CHANNEL CHANNEL CHECK CHECK helps helps ensure ensure that that thethe instrumentation continues instrumentation continues to to operate operate properly properly between between each each CHANNEL CHANNEL CALIBRATION. The CALIBRATION. The highhigh radiation radiation instrumentation instrumentation should should be be compared compared with similar unit with similar unit instruments instruments locatedlocated throughout throughout the the unit.
| |
| unit. IfIf the the radiation radiation monitor uses monitor uses keep keep alivealive sources sources or or check check sources sources operated operated from from the the control room, control room, the the CHANNEL CHANNEL CHECK CHECK should should alsoalso note note the the detector's detector's response to response to these these sources.
| |
| sources.
| |
| BWOG STS SWOG STS B 3.3.16-4 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Control Room Control Room Isolation Isolation -- High High Radiation Radiation BB 3.3.16 3.3.16 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| Agreement criteria Agreement criteria are are determineddetermined by by the the unitunit staff, staff, based based on on a a combination of combination of thethe channel channel instrument instrument uncertainties, uncertainties, including including isolation, isolation, indication, and indication, and readability.
| |
| readability. If If a a channel channel is is outside outside the the criteria, criteria, itit may may be be an indication an indication that that the the transmitter transmitter or or the the signal signal processing processing equipmentequipment has has drifted outside drifted outside its its limit. limit. If If the the channels channels are are withinwithin the the criteria, criteria, itit is is an an indication that indication every shift, every failure is failure that the shift, is is rare.
| |
| the channels is based based on rare. [At [At this channels are on operating this unit, are OPERABLE.lThe operating experiencelnat unit, the the following OPERABLE. The Frequency, following administrative F
| |
| experience at demonstrates administrative controls Frequency, about about once demonstrates channel controls and channel and once design features design features (e.g., (e-g., downscale downscale alarms) alarms) immediately immediately alert alert operators operators to to loss of function.]
| |
| loss of function.J~VI S ef't- ;;2.)
| |
| y z f l~ e r 2) t SR 3.3.16.2 A Note defines A Note defines a a channel channel as as being being OPERABLE OPERABLE for for up up to to 33 hours hours whilewhile bypassed for bypassed for surveillance surveillance testing. testing. The The Note Note allows allows channel channel bypass bypass for for testing without testing defining itit as without defining as inoperable, inoperable, although although during during this this time time period period itit cannot actuate cannot actuate a a control control room room isolation. isolation. ThisThis is is based based on on the the average average time required time required to to perform perform channel channel surveillance. surveillance. It It is is not not acceptable acceptable to to routinely remove routinely remove channels channels from from service service forfor more more than than 3 3 hours hours to to perform perform required surveillance required surveillance testing. testing.
| |
| SR 3.3.16.2 is! rformance of erformance of aa CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST onc e rf92Jf'a s 0 ensure ensure that that the the channels channels can can perform perform their their I n e unctions. This is test test verifies verifies the the capability capability of of the the instrumentation instrumentation to provide to provide the the automatic automatic Control Control Room Room Isolation.
| |
| Isolation. A successful test A successful test ofof the the contact(s) of required contact(s) required of a a channel channel relay relay may may be be performed performed by by the the verification of verification of the the change change of of state state of of a a single single contact contact of of the the relay.
| |
| relay. This This clarifies what clarifies what isis an an acceptable acceptable CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TEST TEST of of a a relay.
| |
| relay.
| |
| This is This is acceptable acceptable because because all all of of the the other other required required contacts contacts of of the the relay relay are verified are verified by by other other Technical Technical Specifications Specifications and and non-Technical non-Technical Specifications tests Specifications tests at at leastleast once once per per refueling refueling interval interval with applicable with applicable extensions. Any extensions. Any setpoint setpoint adjustment adjustment shall shall be be consistent consistent with with the the assumptions of assumptions of the the current current unit unit specific setpoint analysis.
| |
| specific setpoint analysis.
| |
| 1 ~e justification of of a a 92 92 day day Frequency, Frequency, in in viewview of of the the fact f a d that that there there is is rnSef1..Z channel, is only one channel, is Draft Draft NUREG-1366 NUREG-1366 (Ref. (Ref. 3). 3). -:11
| |
| -
| |
| * _ ',.,......,..,._~.~_. ......
| |
| _ _ _ _ " _ I _ +
| |
| * C _ I * - ~ + - ~"
| |
| - ~"'w_."".~-_
| |
| ~-d . . . . .*
| |
| *~-,
| |
| ,.,,_7
| |
| + "+'
| |
| 9 BWOG STS BWOG STS B 3.3.16-5 B 3.3.16-5 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Control Room Control Room Isolation -
| |
| Isolation - High High Radiation Radiation 3.3.16 B 3.3.16 B
| |
| BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)
| |
| (continued)
| |
| SR 3.3.16.3 This SR This SR requires requires the the performance performance of of a a CHANNEL CHANNEL CALIBRATION CALIBRATION with with a a setpoint Allowable setpoint Allowable Value Value ofof S; [25] mR/hr I [25] mR/hr to to ensure ensure that that the the instrument instrument channel remains channel remains operational operational with the correct with the correct setpoint.
| |
| setpoint. This This test test is a is a complete check of complete check of the the instrument instrument loop loop and and the the transmitter.
| |
| transmitter.
| |
| CHANNEL CALIBRATION CHANNEL CALIBRATION is is a a complete complete check check of of the the instrument instrument loop loop and and the sensor.
| |
| the sensor. TheThe test test verifies verifies that that the the channel channel responds responds to to a a measured measured parameter within parameter within the the necessary necessary range range andand accuracy.
| |
| accuracy. CHANNEL CHANNEL CALIBRATION leaves CALIBRATION leaves thethe channel channel adjusted adjusted to to account account forfor instrument instrument drifts between drifts between successive successive calibrations calibrations to to ensure ensure that that the the channel channel remains remains operational between operational between successive successive tests. CHANNEL CALIBRATIONS tests. CHANNEL CALIBRATIONS must must be performed be performed consistent consistent with the unit with the unit specific setpoint analysis.
| |
| specific setpoint analysis.
| |
| G h e Frequency Ghe Frequency is is based based on on the the assumption assumption of of an an [18]
| |
| [I81 month month calibration calibration
| |
| ~ntervalin Interval in the the determination determination of of the the magnitude magnitude of of equipment equipment drift drift in in the tbe analysis and setpoint analysis setpoint and isis consistent consistent with with the the typical typical refueling refueling cycle.
| |
| cycle.
| |
| I REFERENCES REFERENCES 1.
| |
| : 1. FSAR, Section FSAR, Section [14.1].
| |
| [14.1].
| |
| 2.
| |
| : 2. [Unit Specific
| |
| [Unit Specific Setpoint Setpoint Methodology].
| |
| Methodology].
| |
| 3.
| |
| : 3. Draft NUREG-1366.
| |
| Draft NUREG-1366.
| |
| BWOG STS BWOG STS B 3.3.16-6 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 PAM Instrumentation PAM Instrumentation B 3.3.17 B 3.3.17 BASES BASES SURVEILLANCE SURVEILLANCE As noted at As noted at the the beginning beginning of of the SRs, the the SRs, the SRsSRs apply apply to to each each PAMPAM REQUIREMENTS REQUIREMENTS instrumentation Function instrumentation Function in in Table 3.3.17-1.
| |
| Table 3.3.17-1.
| |
| SR 3.3.17.1 Performance of Performance of the the CHANNEL C H E C K ~ d@for CHANNEL CHECK?rlvefrl! ~ & Veach ~ ~ ~
| |
| each O ~
| |
| required instrumentation required instrumentation channel channel that that is is normally normally energized energized ensures ensures that that a gross a gross failure failure of of instrumentation instrumentation has has not not occurred.
| |
| occurred. A CHANNEL CHECK A CHANNEL CHECK is normally is normally a a comparison comparison of of the the parameter parameter indicated indicated on on one one channel channel with with a similar a similar parameter parameter on on other other channels.
| |
| channels. It It is is based based on on thethe assumption assumption that that instrument channels monitoring the same instrument channels monitoring the same parameter should read parameter should read approximately the approximately the same same value.
| |
| value. Significant Significant deviations deviations between between the the two two instrument channels instrument channels could could bebe anan indication indication of of excessive excessive instrument instrument drift drift in in one of one of the the channels channels or or of of something something even even more more serious.
| |
| serious. CHANNEL CHANNEL CHECK will CHECK will detect detect gross gross channel channel failure; failure; therefore, therefore, itit is is key key to to verifying verifying that the that the instrumentation instrumentation continues continues to to operate operate properly properly between between each each CHANNEL CALIBRATION.
| |
| CHANNEL CALIBRATION. The The high high radiation radiation instrumentation instrumentation should should be be compared with compared with similar similar unit unit instruments instruments located located throughout throughout the the unit.
| |
| unit. If If the the radiation monitor radiation monitor usesuses keep keep alive alive sources sources or or check check sources sources OPERABLE OPERABLE from the from the control control room, room, thethe CHANNEL CHANNEL CHECK CHECK should should also also note note the the detector's response detector's response to to these these sources.
| |
| sources.
| |
| Agreement Agreement criteriacriteria areare determined determined by by the the unitunit staff, staff, based based on on aa combination of combination of the the channel channel instrument instrument uncertainties, uncertainties, including including indication indication and readability.
| |
| and readability. If If a a channel channel is is outside outside the the criteria, criteria, itit may may be be an an indication indication that the that the sensor sensor or or the the signal signal processing processing equipment equipment has has drifted drifted outside outside itsits limit. If limit. If the the channels channels are are within the criteria, within the criteria, itit is is an an indication indication that that the the channels are channels are OPERABLE.
| |
| OPERABLE. If If the the channels channels are are normally normally off off scale scale during during times when times surveillance is when surveillance is required, required, the the CHANNEL CHANNEL CHECK CHECK will only will only verify that verify that they they are are offoff scale scale inin the the same same direction. Offscale low direction. Offscale low current current channels are loop channels loop are verified verified to to be be reading reading at at the the bottom bottom of of the the range range and and not failed downscale.
| |
| not ~iled downsc~, cJ~
| |
| 7 Frequency is f;e Frequency is based based on on unit unit operating operating experience experience that that demonstrates demonstrates lffi'annel failure failure is r a p TThe is rar h e CHANNEL CHANNEL CHECK CHECK supplements supplements less less formal formal G5e' *he ut more ut more frequent the displays requent checks displays associated checks of associated with of channels channels during this LCO's with this during normal L C 0 3 required normal operational required channels.
| |
| operational use channels.
| |
| use of of BWOG STS BWOG STS B 3.3.17-12 B 3.3.17-12 Rev. 3.1, Rev. 3.1, 12/01/05 12/01/05
| |
| | |
| TSTF-425, Rev. 3 PAM Instrumentation PAM Instrumentation B 3.3.17 B 3.3.17 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| SR 3.3.17.2 complete check of the instrument channel, including the sensor. This test verifies the channel respo~ndsto measured parameters within the necessary range and accwracy.
| |
| A A Note Note clarifies clarifies that that the the neutron neutron detectors detectors are are not not required required to to be be tested tested as as part of part of the the CHANNEL CHANNEL CALIBRATION.
| |
| CALIBRATION. There There is is no no adjustment adjustment that that can can be made be made to to the the detectors.
| |
| detectors. Furthermore, Furthermore, adjustment adjustment of of the the detectors detectors is is unnecessary because unnecessary because they they are are passive passive devices, devices, withwith minimal minimal drift.
| |
| drift. Slow Slow changes in changes in detector detector sensitivity sensitivity are are compensated compensated for for by by performing performing thethe daily calorimetric daily calorimetric calibration calibratian and and the the monthly monthly axial axial channel channel calibration.
| |
| calibration.
| |
| For the For the Containment Containment Area Area Radiation Radiation instrumentation, instrumentation, a a CHANNEL CHANNEL CALIBRATION may CALIBRATION may consist consist ofof an an electronic electronic calibration calibration of of the the channel, channel, notnot including the including the detector, detector, for for range range decades decades aboveabove 10 Rlhr, and 10 Rlhr, and a a one one point point calibration check calibration check of of the the detector detector below below 10 Rlhr with 10 R/hr with aa gamma gamma source.
| |
| source.
| |
| Whenever a Whenever a sensing sensing element element is is replaced, replaced, the the next next required required CHANNEL CHANNEL CALIBRATION of CALIBRATION of the resistance temperature the resistance temperature detectors detectors (RTD)
| |
| (RTD) sensors sensors is is accomplished by accomplished by an inplace cross an inplace cross calibration calibration that that compares compares the the other other sensing elements sensing elements with with the the recently recently installed installed sensing sensing element.
| |
| element.
| |
| Whenever a Whenever sensing element a sensing element is is replaced, replaced, the the next next required required CHANNEL CHANNEL CALIBRATION of CALIBRATION of the the Core Core Exit Exit thermocouple thermocouple sensors sensors is is accomplished accomplished by by an inplace an inplace cross cross calibration calibratian that that compares compares the the other other sensing sensing elements elements with the with the recently recently installed installed sensing sensing element.
| |
| element.
| |
| 4
| |
| ._.**,I?
| |
| fThe The Frequency Frequency is is based based on on operating operating experience experience and and consistency consistency withwith Lffie e typical typical industry industry refueling refueling cycle cycle and and isis justified justified byby the the assumption assumption of of an an
| |
| [18] month calibration interval in the determination of the magnitude of
| |
| ,,_. ~9uipment drift.
| |
| REFERENCES REFERENCES 1. (( Unit
| |
| : 1. Unit Specific Specific Documents Documents (e.g., FSAR, NRC (e.g., FSAR, NRC Regulatory Regulatory Guide Guide 1.97 1.97 SER letter).
| |
| SER letter). ))
| |
| 2.
| |
| : 2. Regulatory Guide Regulatory Guide 1.97.1.9'7.
| |
| : 3. NUREG-0737, 1979.
| |
| 4.
| |
| : 4. 32-1 177256-00, "Technical 32-1177256-00, "Technical Basis Basis for for Reactor Reactor Vessel Vessel Level Level Indication Indication System (RVLlS)
| |
| System (RVLIS) Action Statement," April Action Statement," 1990.
| |
| 10, 1990.
| |
| April 10, BWOG STS BWOG STS 3.3.17-13 B 3.3.17-13 B 3.1, 12/01/05 Rev. 3.1,12/01/05 Rev.
| |
| | |
| TSTF-425, Rev. 3 Remote Shutdown Remote Shutdown System System B 3.3.18 B 3.3.18 BASES BASES SURVEILLANCE SURVEillANCE [ SR 3.3.18.1
| |
| [SR 3.3.18.1 REQUIREMENTS REQUIREMENTS Performance of Performance of the the CHANNEL CHECK(&&^^^ 3rla~
| |
| CHANNEL CHECK(9rJRi?ery 3).days)forfor each each required instrumentation required instrumentation ohannel ahannel that that isis normally normally energized energized ensures ensures thatthat a gross a gross failure failure of of instrumentation instrume~ntationhas has notnot occurred.
| |
| occurred. A CHANNEL CHECK A CHANNEL CHECK is normally is normally a a comparison comparison of of the the parameter parameter indicated indicated on on one one channel channel to to a a
| |
| similar parameter on other channels. It is based on the assumption that similar parameter on other channels. It is based on the assumption that instrument channels instrument channels monitoring monitoring the the same same parameter parameter should should readread approximately the approximately the same same value.
| |
| value.
| |
| Significant deviations Significant deviations betweenbetween the the twotwo instrument instrument channels channels couldcould bebe anan indication of indication of excessive insltrument drift excessive instrument drift in in one one of of the the channels channels or or of of something even something even more more serious.
| |
| serious. CHANNEL CHANNEL CHECK CHECK will will detect detect gross gross channel failure; channel failure; therefore,it therefore, it is is key key in in verifying verifying thatthat the the instrumentation instrumentation continues to continues to operate operate properly properly between between each each CHANNEL CHANNEL CALIBRATION.
| |
| CALIBRATION.
| |
| Agreement criteria are Agreement criteria det~erminedby are determined by the the unit unit staff staff based based on on aa combination of combination of the the channel channel instrument instrument uncertainties, uncertainties, including including indication indication and readability.
| |
| and readability. If If the the channel channel is is outside outside the criteria, itit may the criteria, may be be an an indication that indication that thethe sensor sensor or or the the signal signal processing processing equipment equipment has has drifted drifted outside its outside its limit.
| |
| limit. If If the the channels channels are are within within the the criteria, criteria, itit is is an an indication indication that the that the channels channels are are OPERABLE.
| |
| OPERABLE. As specified in As specified in the the Surveillance, Surveillance, a a CHANNEL CHECK CHANNEL CHECK is is only only required required for for those those channels channels that that are are normally normally energized. If energized. If the the channels channels are are normally normally off off scale scale during during times times when when surveillance is surveillance is required, required, thethe CHANNEL CHANNEL CHECK CHECK will only verify will only verify that that they they are off are off scale scale in in the the same same direction.
| |
| direction. Off Off scale scale lowlow current current loop loop channels channels are verified are verified to to be be reading reading at at the the bottom bottom of of the the range range and and notnot failed failed downscale.
| |
| downscale.
| |
| c, G.f 31 kl~)
| |
| b h e Frequency~s
| |
| {j;e ~ r e ~ u e n cbased based
| |
| ~ i s on on unit unit operating operating experience, experience, which which demonstrates that channel failure demonstrates that channel failure is rare. J ~ is rare. ]
| |
| InsetID SR 3.3.18.2 SR 3.3.18.2 SR 3.3.18.2 verifies verifies each each required required RemoteRemote Shutdown Shutdown System System transfer transfer switch and switch and control control circuit plerforms their circuit performs their intended intended function.
| |
| function. This This verification is verification is performed performed fnDm from thethe remote remote shutdown shutdown panel panel and and locally, locally, as as appropriate. Operation appropriate. Operation of of the the equipment equipment from from the the remote remote shutdown shutdown panel panel is not is not necessary.
| |
| necessary. The The Surveillance Surveillance can can be be satisfied satisfied by by performance performance of of a a
| |
| continuity check.
| |
| continuity check. This This will will ensure ensure that that ifif the the control control room room becomes becomes BWOG STS SWOG STS 3.3.18-4 B 3.3.18-4 B Rev. 3.0, Rev. 03/31/04 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Remote Shutdown Remote Shutdown System System 3.3.18 B 3.3.18 B
| |
| BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)(continued) inaccessible, the the unit unit can can be be placed placed and and maintained maintained in ODE 3 3 from from the the inaccessible.
| |
| remote shutdown panel and the local control stations. The [I81 month remote Frequency shutdown Frequency is conditions that conditions is based that apply nplanned transient unplanned panel based on on the apply during and during a transient ifif the the the need need to a unit local control to perform perform this unit outage the Surveillance outage and Surveillance were stations.
| |
| this Surver and the C
| |
| in~ODE Survel nce The the potential potential for performed with were performed
| |
| [18] month nce under under the an for an the the reactor with the reactor at at power. Operating power. Operating experience experience demonstrates demonstrates that that remote remote shutdown shutdown control control channels seldom channels seldom fail to pass fail to pass thethe Surveillance Surveillance when performed at when performed at the' the 81 month
| |
| [18] month Frequency.
| |
| Frequency9 SR 3.3.18.3 CHANNEL CALIBRATION CHANNEL CALIBRATION is is aa complete complete checkcheck of of the the instrument instrument looploop and and sensor. The sensor. The test test verifies tihat the verifies that the channel channel responds responds to to measured measured parameters within parameters the necessary within the necessary range range and and accuracy.
| |
| accuracy.
| |
| Note clarifies A Note A clarifies that that the the neutron neutron detectors detectors areare not not required required to to be be tested tested asas part of part of the the CHANNEL CHANNEL CALIBRATION.
| |
| CALIBRATION. There There is is no no adjustment adjustment thatthat can can be made be made to to the the detectors.
| |
| detectors. Furthermore, Furthermore, adjustment adjustment of of the the detectors detectors is is unnecessary because unnecessary because they they are are passive passive devices, devices, withwith minimal minimal drift.
| |
| drift. Slow Slow changes in changes in detector detector sensitiVity sensitivity are are compensated compensated for for byby performing performing the the daily calorimetric daily calorimetric calibraticn calibration and and thethe monthly monthly axial axial channel channel calibration.
| |
| calibration.
| |
| Whenever a Whenever a sensing sensing element elemlent is is replaced, replaced, thethe next next required required CHANNEL CHANNEL CALIBRATION of CALIBRATION of the the resistance resistance temperature temperature detectors detectors (RTD)(RTD) sensors sensors is is accomplished by accomplished by an inplace cross an inplace cross calibration calibration that that compares compares the the other other sensing elements sensing elements with with thethe recently recently installed installed sensing sensing element.
| |
| element.
| |
| Ge Frequency
| |
| [;e Frequency is is based based on oln operating experience and operating experience consistency with and consistency with the typicalal industry industry refueling refueling cycle cycle and is justified and is justified byby the the assumption assumption of of an an
| |
| [18] month th calibration calibration interval interval in in the the determination determination of of the the magnitude magnitude of of equipment drift.
| |
| REFERENCES REFERENCES 1.
| |
| : 1. 10 CFR 10 CFR 50,50, Appendix Appendix A, GDC 19.
| |
| A, GDC 19.
| |
| BWOG STS BWOG STS B 3.3.18-5 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Pressure, Res Pressure, Temperature, Temperature, and and Flow Flow DNB DNB Limits Limits B 3.4.1 B 3.4.1 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| If the If the Required Required Action Action A.l A.1 isis not not metmet within within thethe Completion Completion Time, Time, thethe plant must plant must be be brought brought to to aa MODE MODE in in which which the the LCO L C 0 does does not not apply.
| |
| apply. To To achieve this achieve this status.
| |
| status, the the plant plant must must be be brought brought to to at at least least MODE MODE 2 2 within within 6 hours.
| |
| 6 hours. In In MODE MODE 2. 2, the the reduced reduced power power condition condition eliminates eliminates thethe potential for potential for violation violation of of the the accident accident analysis analysis bounds.
| |
| bounds.
| |
| The 6 The 6 hour hour Completion Completion Time Time is is reasonable, reasonable, based based on on operating operating experience, to experience, to reduce reduce powerpower in in anan orderly orderly manner manner in in conjunction conjunction with with even control even control of of steam steam generator generator heat heat removal.
| |
| removal.
| |
| SURVEILLANCE SURVEILLANCE SR 3.4.1.I SR 3.4.1.1 REQUIREMENTS REQUIREMENTS Since Required Since Required Action Action A.l allows a A.1 allows a Completion Completion Time Time of of 2 hours to 2 hours to restore restore parameters that parameters that are are notnot within within limits, them-&~urveillance limits, theGiK§(mSurveillance Frequency Frequency loop (hot for loop for (hot leg) leg) pressure pressure is is sufficient sufficient to to ensure ensure thatthat the the pressure pressure can can bebe restored to restored to aa normal normal operation.
| |
| operation, steadysteady state state condition condition following following load load changes and changes and other expected transient other expected transient operations.
| |
| operations. The The RCSRCS pressure pressure value specified value specified is is dependent dependent on on thethe number number of of pumps pumps in in operation operation and and has been has been adjusted adjusted to to account account for for the the pressure pressure loss loss difference difference between between the core the core exit exit and and thethe measur measu~nt nt location.
| |
| location. The The value value used used inin the the plant plant safety analysis safety analysis is 2135 psia.E is 2135 pS'ia.JJ,!:1~ 12 12 hour hour interval interval hashas been been shown shown by by operating practice operating practice to to be suff~c~ent be sufficient to regularly to regularly assess assess potential potential degradation and degradation and to to verify verify operation operation is is within within safety safety analysis analysis assum assu . ns.
| |
| 'l..)el A Note has A Note has been been added added to to indicate indicate the the pressure pressure limits limits are are toto be be app Ie to the loop the loop with with twotwo pumps pumps in in operation operation for for the the three three pump pump operating operating condition.
| |
| condition.
| |
| SR 3.4.1.2 Since Required Since Required Action Action A.l allows a A.1 allows a Completion Completion Time Time of of 22 hours hours toto restore restore parameters that parameters that are are notnot w~ithin limits, the wiithin limits, t h eO??'fQjd]
| |
| f i ~ ~ ~Surveillance urveillan Frequency ce Frequency for hot for hot leg leg temperature temperature is is sufficient sufficient to to ensure ensure thatthat the RCS coolant the ReS coolant temperature can temperature can bebe restored restored to to a a normal normal operation.
| |
| operation, steady steady state state condition condition following load following load changes changes and arld other other expected expected transient transient operations.
| |
| operations. Uhe nhe hour interval 12 hour 12 interval has has been been shown shown by by operating operating practice practice to to be be sufficiel1lt sufficiefit to to regularly assess regularly assess potential potential degradation degradation and to verify that 0 eration is within safety within safety analysis assumptions. ~;:;;
| |
| analysis assumptions. & ert 2-BWOG STS BWOG STS B 3.4.1-4 B3.4.1-4 Rev. 3.0, Rev. 03/31/04 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Pressure, Res Pressure, Temperature, Temperature, and and Flow DNB Limits Flow DNB Limits B 3.4.1 B 3.4.1 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)
| |
| (continued)
| |
| A Note has A Note has been been added added to to indicate indicate thethe temperature temperature limits limits are are to to be be applied to applied to the the loop loop with with twotwo pumps pumps in in operation operation forfor the the three three pump pump operating condition.
| |
| operating condition.
| |
| SR 3.4.1.3 2J?Uacsurveillanc~~e¢y I
| |
| ~ h e ( l 2 ~ u ~ ~ u r v e i l l a n c & ~ r & eM The[ @@iJ~ReS tot;;:-~s RCS total flow rate IS performed performed using the using the installed installed flow flow instrumentation.
| |
| instrumentation. {[he E h e 12 12 hour hour interval interval has has been been shown by shown by operating operating practi1ce practice to to be be sufficient sufficient to to regularly regularly assess assess potential potential degradation and degradation and to to verify verify thatthat operation operation is is within within safety safety analysis analysis assumptions.
| |
| assumptions. ~Q 6EE''I I JrlSer r 1 J D SR 3.4.1.4 Measurement of RCS total flow rate by performance erformance of of aa precision precision calorimetric heat calorimetric heat balance balan Inni.c~e7,;e~v;;k.718Rf;~E;::\allows allows the the installed installed RCS flow RCS flow instrumentation instrumentat 0 e calibrated and verifies ifies that that the the actual actual flow is RCS flow RCS is greater greater than than or or equal equal to to the the minimum minimum required required RCS RCS flow flow rate.
| |
| rate.
| |
| fi£e Frequency of of [18]
| |
| [I81 months months reflects reflects the the importance importance of of verifying verifying flow flow outage when after a refueling outage wlhen thethe core core has has been been altered altered or RCS flow or RCS flow characteristics may characteristics may have have been been modified, modified, which which maymay have have caused caused change change
| |
| ~~V The Surveillance The surveillance is is modified modified by by a a Note Note that that indicates indicates the the SRSR does does notnot need to need to be be performed performed untiluntil stable stable thermal thermal conditions conditions are are established established at at higher power higher power levels.
| |
| levels. TheThe Note Note isis necessary necessary to to allow allow measurement measurement of of the the flow rate flow rate at at normal normal operating operating conditions conditions at at power power in MODE 1.
| |
| in MODE 1. The The Surveillance cannot Surveillance cannot be be performed performed at at low low power power or or in in MODE MODE 2 2 or or below below because at because at low low power power thethe ~ AT across the T across the core core will will be be too too small small to to provide provide valid results.
| |
| valid results.
| |
| REFERENCES REFERENCES 1.
| |
| : 1. FSAR, Chapter FSAR, r 51.
| |
| C h a ~ t e[15].
| |
| I1 BWOG STS BWOG STS B 3.4.1-5 Rev. 3.0, 03/31/04 Rev. 3.0, 03131104
| |
| | |
| TSTF-425, Rev. 3 RCS Minimum RCS Minimum Temperature Temperature for for Criticality Criticality B 3.4.2 B 3.4.2 BASES BASES ACTIONS ACTIONS With T With Tavg avg below 525"F, the below 525°F, the plant plant mustmust be be brought brought to to aa MODE MODE in in which which the the L C 0 does LCO does notnot apply.
| |
| apply. To To achieve achieve this this status, status, the the plant plant must must bebe brought brought toto MODE 2 MODE 2 with with Kef! 1.0 in Keff<< 1.0 in 30 30 minutes.
| |
| minutes. Rapid Rapid reactor reactor shutdown shutdown can can be be readily and readily and practically practically achieved achieved in in aa 30 30 minute minute period.
| |
| period. The The Completion Completion Time reflects Time reflects the the ability ability to to perform perform this this Action Action andand maintain maintain thethe plant plant within the within the analyzed analyzed range.
| |
| range. If If T can be T,,avg can be restored restored within within the 30 minute the 30 minute time period, time period, shutdown shutdown is n~otrequired.
| |
| is not required.
| |
| SURVEILLANCE SURVEILLANCE SR 3.4.2.1 SR 3.4.2.1 REQUIREMENTS REQUIREMENTS RCS loo=erage RCS loop average temperature temperature is is required required to to be be%erified at or erified at or above above
| |
| (, 1\ 525°F(eyiW121aeur$.
| |
| 525°F(e~12bYI~*[he ~~to;er'm Ehe SR 0 ver' oop avav temperwreg
| |
| ( k x L
| |
| \,fYerr.ue¥lt:}
| |
| \ + ' /
| |
| ~ every 12 every 12 hours hours takes takes into cont~nuouslyavailable continuously available to into account to the account indications the operator indicatio:
| |
| operator in in the oop Lnd a an the control a arms control room room and temper l a z ht aatt are and is are is res
| |
| ~-----.... consistent with consistent with other other routine routine Surveillances Surveillances which which are are typically typically performed performed r nse"r1 ;2 once per once shift.%^
| |
| per shift. addition, operators In addition, operators are are trained trained toto be sensitive to be sensitive to RCS RCS durin temperature during temperature - ~approach approach
| |
| .. to criticality to criticality and and will will ensure ensure that that the the minimum temperature minimum temperature for for criticality criticality is is met met as as criticality is approached.
| |
| criticality is approached.
| |
| REFERENCES REFERENCES 1
| |
| : 1. FSAR, Chapter FSAR, 1 r151.
| |
| C h a ~ t e[15].
| |
| BWOG STS BWOG B 3.4.2-2 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS PIT RCS PIT Limits Limits B 3.4.3 B 3.4.3 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| Condition C Condition C isis modified modified by by aa Note Note requiring requiring Required Required Action Action C.2C.2 to to be be completed whenever completed whenever thethe Condition Condition is is entered.
| |
| entered. The The Note Note emphasizes emphasizes the the need to need to perform perform the the evaluation evaluation of of the the effects effects ofof the the excursion excursion outside outside the the allowable limits.
| |
| allowable limits. Restoration Restoration alone, alone, per per Required Required Action Action C.1,C.l, is is insufficient because insufficient because higher higher than than analyzed analyzed stresses stresses may may have have occurred occurred and may and may have have affected RGPB integrity.
| |
| affected RGPB integrity.
| |
| SURVEILLANCE SURVEILLANCE 3.4.3.1 SR 3.4.3.1 SR REQUIREMENTS REQUIREMENTS Verification that Verification that operation operation is is within within the the PTLR PTLR limits is rrequired~
| |
| limits is equiredm
| |
| ((3§ilii~when r d w h e n RCS RCS pressure pressure and and temperature temperature conditions conditions are are undergoing planned changes.
| |
| considered reasonable UhiS Frequency is considered reasonable in in view view ofof the the control control room room indication available to to monitor monitor RCS status. Also, RCS status. Also, since since temperature temperature rate rate of change of change limits limits are are specified specified inin hourly hourly increments, increments, 30 30 minutes minutes permits permits assessment and assessment and correction correction for for minor minor deviations deviations within within aa reasonable reasonable time.~ ~D o;serf:J.
| |
| Surveillance for Surveillance heatup, cooldown, for heatup, cooldown, or or ISLH ISLH testing testing may may be be discontinued discontinued when the when the definition definition given given in in the the relevant relevant plant plant procedure procedure for for ending ending the the is satisfied.
| |
| activity is activity satisfied.
| |
| SR is This SR This is modified modified byby a Note that a Note that requires requires this this SRSR to to be be performed performed only only during system during heatup, cooldown, system heatup, cooldown, and and ISLH ISLH testing.
| |
| testing.
| |
| REFERENCES REFERENCES BAW-10046A, Rev.
| |
| I. BAW-10046A,
| |
| : 1. 1, July Rev. 1, July 1977.
| |
| 1977.
| |
| 2.
| |
| : 2. 10 CFR 10 CFR 50, 50, Appendix Appendix G. G.
| |
| 3.
| |
| : 3. ASME, ASME, BoilerBoiler and and Pressure Pressure Vessel Vessel Code, Code, Section Section III, Ill, Appendix Appendix G. G.
| |
| 4.
| |
| : 4. Regulatory Guide Regulatory Guide 1.99, 1.99, Revision Revision 2, May 1988.
| |
| 2, May 1988.
| |
| 5.
| |
| : 5. NUREG-0800, Section NUREG-0800, Section 5.3.1, 5.3.1, Rev.
| |
| Rev. 1, 1, July July 1981.
| |
| 1981.
| |
| 6.
| |
| : 6. ASTM ASTM E E 185-82, 185-82, July 1982.
| |
| July 1982.
| |
| 7.
| |
| : 7. 10 CFR 10 CFR 50, 50, Appendix Appendix H. H.
| |
| 8.
| |
| : 8. ASME, ASME, BoilerBoiler and and Pressure Pressure Vessel Vessel Code, Code, Section Section XI,XI, Appendix Appendix E. E.
| |
| BWOG STS BWOG STS B 3.4.3-7 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Loops -- MODES RCS Loops RCS MODES 11 and and 22 B 3.4.4 B3.4.4 BASES BASES SURVEILLANCE SURVEILLANCE SR 3.4.4.1 SR 3.4.4.1 REQUIREMENTS REQUIREMENTS SR requires This SR This requires verification v e r i f i c a t i~Y.f3Pi12 o n ~ v ~ ~ fh¢rgof I 2 f o f the M the required required number number of of loops in loops in operation.
| |
| operation. Verification Verificationincludesincludes flowflow rate, rate, temperature, temaerature, or Duma or pump status monitoring, status monitoring, which removalwhile which help while maintaining maintainingthe help ensure ensure that the margin marginto that forced forced flow to DNB.
| |
| DNB. Efhe r h e 12 is providing heat flow is providing 12hour hour interval heat '
| |
| intervalhas has removal been shown been shown by by operating operating practicepractice to to be be sufficient sufficient toto regularly regularly assess assess degradation and degradation and verify verify operation operationwithinwithin safety safety analyses analyses assumptions.
| |
| assumptions. In In addition, control addition, controlroom room indication indication and and alarms alarms willwill normally normallyindicate indicateloop loop status.
| |
| status. < --..----
| |
| ---~---- ----,
| |
| Chapter (( )] ..
| |
| REFERENCES REFERENCES I.FSAR,
| |
| : 1. FSAR, Chapter I
| |
| -TYlser+ 1 BWOG STS BWOG STS B 3.4.4-4 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Loops RCS -
| |
| Loops - MODE MODE 3 3 B 3.4.5 B 3.4.5 BASES BASES SURVEILLANCE SURVEILLANCE 3.4.5.1 SR 3.4.5.1 SR REQUIREMENTS REQUIREMENTS This SR This SR requires requires verification verification&s& Grl1 t. h~u~hat hat the required the required number number of of loops and pumps is in operation. Verification includes flow rate, loops and pumps is in operation. Verification includes flow rate, temperature, or temperature, or pump pump status status m itoring, which m~'toring, help ensure which help ensure that that forced forced flow is flow is providing providing heat heat removal.
| |
| removal. The The 1212 hour hour interval interval has has been been shown shown byby operating practice operating practice toto be be sufficien r"r regular1 assess RCS loop status. Inn sufficien 0o regularly addition, control addition, control room room indication indication and and alarms alarms will normall indicate loop status.
| |
| status. :-G,5 e,rt ' ).,
| |
| SR 3.4.5.2 Verification that Verification that each requ~iredRCP each requlired RCP isis OPERABLE OPERABLE ensures ensures that that the the single single failure criterion failure criterion is is met met and and that that an an additional RCS loop additional RCS loop can can bebe placed placed inin operation, ifif needed, operation, needed, to to maintain maintain decay decay heat heat removal removal and and reactor reactor coolant coolant circulation. Verification circulation. Verification is is performed performed by by verifying verifying proper proper breaker breaker alignment and alignment and power availlability to power availability to each each required required pump.
| |
| pump. Alternatively, Alternatively, verification that verification that a a pump pump is is ,in in operation operation also also verifies verifies proper breaker proper breaker alignment and alignment reasonable in reasonable and power power availability.
| |
| in view view ofof other 5f availlability.IThe The Frequency other admin'isErative Frequency of admin~srative controls 7 days of 7 days is controls available is considered available and considered has and has experience. ~'--Y1-$-e-(-1-'J)-
| |
| been shown been shown to to be be acceptable acceptable by by operating operating experience.
| |
| T ~ n s V3t This SR This SR isis modified modified by by a a Note Note that that states the SR states the SR isis not not required required toto be be performed until 24 hours a~ftera required pump is not performed until 24 hours after a required pump is not in operation. in operation.
| |
| REFERENCES REFERENCES None.
| |
| None.
| |
| BWOG STS BWOGSTS B 3.4.5-4 3.1, 12/01/05 Rev. 3.1, Rev. 12/01/05
| |
| | |
| TSTF-425, Rev. 3 Loops -- MODE RCS Loops RCS MODE 4 4 3.4.6 B 3.4.6 B
| |
| BASES BASES SURVEILLANCE SURVEILLANCE SR 3.4.6.1 SR 3.4.6.1 REQUIREMENTS REQUIREMENTS This Surveillance This requires v Surveillance requires verification~ibe1Uryof e r i f i c a t i o n ~ e m a othe the f required required DHR DHR RCS loop or RCS or loop inin operation operation to 40 ensure ensure forced forced flow flow is is providing providing decay decay heatheat removal. Verification removal. Verification includes includes flow flow rate, rate, temperature, temperature, or or pump pump status status monitoring.Dhe monitoring. [fhe 12 12 hour hour interval interval has has been been shownshown by by operating operating practice practice to to be sufficient be sufficient to to regularly regularly assess assess ReSRCS loop status. In addition, control room indication room indication andand alarms alarmis will normally indicate loop status.
| |
| will normally SR 3.4.6.2 Verification that Verification that each each required required pump pump is is OPERABLE OPERABLE ensures ensures thatthat an an additional RCS additional RCS or DHR loop or DHR loop can can bebe placed placed in in operation operation if if needed needed to to maintain decay maintain decay heat heat removal removal and and reactor reactor coolant coolant circulation.
| |
| circulation. Verification Verification is performed is performed by by verifying verifying proper proper breaker breaker alignment alignment and and power power available available to to each required each required pump.
| |
| pump. Alternatively, verification that Alternatively, verification that aa pump pump is is in in operation operation also verifies also verifies proper proper breaker breaker alignment alignment and and powerpower availability.
| |
| availability. TheThe G-Frequency of (F';-equency of 77 days days is is considered considered reasonable
| |
| ~~:~;i~~a::;e:~~IS;:cl:a_~::~~O:~rt])
| |
| reasonable in dministrative controls and has been shown to be acceptable b operating experience. F-in view view of
| |
| ++--
| |
| of other other
| |
| .--@z23 This SR This SR is is modified modified byby a a Note Note that that states states the the SR SR isis not not required required to to be be performed until performed until 24 24 hours hours after after aa required required pump pump is is not not in in operation.
| |
| operation.
| |
| REFERENCES REFERENCES None.
| |
| None.
| |
| BWOG STS BWOG STS B 3.4.6-4 3.1, 12/01/05 Rev. 3.1,12/01/05 Rev.
| |
| | |
| TSTF-425, Rev. 3 Res Loops -- MODE RCS Loops MODE 5, 5, Loops Loops Filled Filled B 3.4.7 B 3.4.7 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| C.l and C.1 and C.2 C.2 If no If no required required DHRDHR loop loop is is in in operation, operation, except except as as provided provided in in Note Note 1,1, or or no required no required DHR DHR loop loop isis OPERABLE, OPERABLE, all all operations operations involving involving introduction introduction of coolant of coolant into into the the RCS RCS withwith boron boron concentration concentration less less than than required required to to meet the meet the minimum minimum SDM SDM of L C 0 3.1.1 of LCO 3.1 . I must must be be suspended suspended and and action action toto restore a restore a DHR DHR looploop to to OPERABLE OPERABLE status status and and operation operation must must be be initiated.
| |
| initiated.
| |
| The required The required margin margin toto criticality criticality must must notnot bebe reduced reduced in in this this type type ofof operation. Suspending operation. Suspending the the introduction introduction of of coolant coolant intointo the RCS of the RCS of coolant coolant with boron with boron concentration concentration less less than than required required to to meet meet thethe minimum minimum SOM SDM of of LC0 3.1.1 LCO 3.1.1 isis required required to to assure assure continued continued safe safe operation.
| |
| operation. With With coolant coolant added without added without forced forced circulation, circulation, unmixed unmixed coolant coolant could could be be introduced introduced to to the core, the core, however however coolant coolant addedadded withwith boron boron concentration concentration meetingmeeting thethe minimum SDM minimum SDM maintains maintains acceptable acceptable marginmargin to to subcritical subcritical operations.
| |
| operations.
| |
| The immediate The immediate Completion Completion Time Time reflects reflects the the importance importance of of maintaining maintaining operation for operation for decay decay heat heat removal.
| |
| removal.
| |
| SURVEILLANCE SURVEILLANCE 3.4.7.1 SR 3.4.7.1 SR REQUIREMENTS REQUIREMENTS This SR This SR requires requires verificatiorx§f"rjl:?lb~that v e r i f i c a t i o m $ 7 m t h a t the the required required DHR DHR loop loop isis in operation.
| |
| in operation. Verification includes flow Verification includes rate, temperature.
| |
| flow rate, temperature, or or pump pump status status r
| |
| ~e nitoring, which
| |
| ~nitoring, The 12 12 hour sufficient to sufficient to regularly indication and indication help ensure which help hour Frequency Frequency has regularly assess and alarms ensure that has been that forced assess degradation alarms will will normally forced flow been shown shown by flow isis providing by operating providing heat operating practice degradation In addition, control room normally indicate indica loop s a us.
| |
| heat removal.
| |
| practice to removal.
| |
| to be be SR 3.4.7.2 Verifying the Verifying the SGs are are OPERABLE OPERABLE by ensuring their by ensuring their secondary secondary side side water water levels are levels are ~ [50]% ensures 2 [50]% ensures that that redundant redundant heat heat removal removal pathspaths areare available ifif the the second second DHR DHR loop loop isis not not OPERABy;,.
| |
| OPERABL . If If both both DHR DHR loops loops available are OPERABLE, are OPERABLE, this has been has been shown shown by this Surveillance Surveillance is by operating operating practice is not not needed.Uhe practice to to be f
| |
| needed. The 12 be sufficient sufficient to 12 hour hour Frequency to regularly Frequency regularly assess assess degradation and degradation and verify verify operation operation withinwithin safety safety analyses analyses assumptions.!>
| |
| assumptions.
| |
| qnSe@
| |
| BWOG STS BWOG STS BB 3.4.7-4 3.4.7-4 Rev. 3.1,12/01/05 Rev. 3.1. 12/01/05
| |
| | |
| TSTF-425, Rev. 3 RCS Loops -- MODE RCS Loops MODE 5, 5, Loops Loops Filled Filled B 3.4.7 B 3.4.7 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)
| |
| (continued)
| |
| SR 3.4.7.3 Verification that Verification that each each required required DHRDHR pump pump is is OPERABLE OPERABLE ensures ensures thatthat redundant paths redundant paths for for heat heat removal removal areare available.
| |
| available. The The requirement requirement also also ensures that ensures that the the additional additional loop loop can can be be placed placed inin operation operation ifif needed needed to to maintain decay maintain decay heat heat removal removal andand reactor reactor coolant coolant circulation.
| |
| circulation. IfIf the the secondary side secondary side water level is water level is 2
| |
| ~ [50]%
| |
| [50]% inin both both SGs, SGs, this this Surveillance Surveillance is is not not needed. Verification needed. Verification isis performed performed by by verifying verifying proper proper breaker breaker alignment alignment and power and power available available toto each each required pump. Alternatively, required pump. Alternatively, verification verification that a that a pump pump is is in in o teration also o~eration also verifies availability. The Frequency power availability.Qhe power verifies proper Frequency of of 7 proper breaker 7 days days is breaker alignment is considered alignment and considered reasonable and reasonable in in
| |
| <-<----------fh5&
| |
| view of view of other other administrative administrative controls controls available available andand has has been been shown shown to to be be acceptable by acceptable This SR This SR is by operating operating experience.
| |
| is modified modified by by a experience.
| |
| a Note Note that that states states the SR is the SR is not not required required to (Jn5e,...~
| |
| to be be
| |
| ~- - - a d
| |
| performed until performed 24 hours until 24 hours after after a a required required pumppump is is not not in in operation.
| |
| operation.
| |
| REFERENCES REFERENCES None.
| |
| None.
| |
| BWOG STS BWOG STS B 3.4.7-5 Rev. 3.1,12/01/05 Rev. 3.1, 12/01/05
| |
| | |
| TSTF-425, Rev. 3 RCS Loops RCS Loops -- MODEMODE 5, 5, Loops Loops Not Not Filled Filled B 3.4.8 B 3.4.8 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| B.l and B.1 and B.2B.2 If no If no required required looploop isis OPERABLE OPERABLE or or the the required required loop loop is is not not in in operation, operation, except as except as provided provided by by Note Note 1 1 in in the the LCO, LCO, the the Required Required Action Action requires requires immediate suspension immediate suspension of of all all operations operations involving involving introduction introduction of of coolant coolant into the into the RCSRCS with with boron boron concentration concentration less less than than required required to to meet meet the the minimum SDM minimum SDM of L C 0 3.1.1 of LCO 3.1.1 and and requires requires initiation initiation of of action action to to immediately restore immediately restore oneone DHR DHR loop loop to to OPERABLE OPERABLE status status andand operation.
| |
| operation.
| |
| The Required The Required ActionAction forfor restoration restoration doesdoes not not apply apply to to the the condition condition of of both loops both loops not not inin operation operation when when the the exception exception Note Note in in the L C 0 is the LCO is in in force. Suspending force. Suspending the the introduction introduction of of coolant coolant intointo the the RCSRCS of of coolant coolant withwith boron concentration boron concentration less less than than required required to to meet meet the the minimum minimum SDM SDM of of LC0 3.1.1 LCO 3.1.Iisis required required to to assure assure continued continued safe safe operation.
| |
| operation. With With coolant coolant added without added forced circulation, without forced circulation, unmixed unmixed coolantcoolant couldcould be be introduced introduced to to the core, the core, however however coolant coolant addedadded with boron concentration with boron concentration meeting meeting the the minimum SDM minimum SDM maintains maintains acceptable acceptable marginmargin to to subcritical subcritical operations.
| |
| operations.
| |
| The immediate The immediate Completion Completion Time Time reflects reflects thethe importance importance of of maintaining maintaining operations for operations for decay decay heatheat removal.
| |
| removal. The The action action to to restore restore mustmust continue continue until one until one loop loop isis restored.
| |
| restored.
| |
| SURVEILLANCE SURVEILLANCE SR 3.4.8.1 REQUIREMENTS REQUIREMENTS This Surveillance This Surveillance requires v e r i f i c a t i oV2n hiur~that requires verification@m m t h a t the required the required loop is loop in operation.
| |
| is in Verification includes operation. Verification includes flow rate, temperature, flow rate, temperature, or pump or pump status monitoring, status monitoring, which which help help ensure ensure thatthat forced forced flowflow is is providing providing heat heat removal.nhe removal.Uhe 12 12 hour hour interval interval has has been been shown shown by by operating operating practice practice to to be sufficient
| |
| 'be sufficient to to regularly regularly assess assess degradation degradation and and verify verify operation operation within within safety analyses safety analyses assumptions.
| |
| assumptions.
| |
| -nsert 2)
| |
| SR 3.4.8.2 Verification that Verification that each each required required pump pump is OPERABLE ensures is OPERABLE ensures that that redundancy for redundancy for heat heat removal removal is is provided.
| |
| provided. The The requirement requirement also also ensures ensures that an that an additional additional loop loop can can bebe placed placed in in operation operation if if needed needed to to maintain maintain decay heat decay heat removal removal and and reactor reactor coolant coolant circulation.
| |
| circulation. Verification Verification is is performed by performed by verifying verifying proper proper breaker breaker alignment alignment and and powerpower available available to to each required each required pump.
| |
| pump. Alternatively, verification that Alternatively, verification that a a pump pump is is in in operation operation also verifies also verifies proper proper breaker breaker alignment alignment and and power power availability.
| |
| availability. The The Frequency of
| |
| §equency of 7 7 days days is is considered considered reasonable reasonable in in view view of of other other a
| |
| L-administrative c?ntrols admini.strative controls available available and and has has been been shown shown to to be be acce.~t~
| |
| acceptable b ,
| |
| operating expenence.
| |
| operatmg experience. J7i
| |
| -4 7i--.--__C&t .- .__. -~
| |
| ..,:;:::=....:~~--
| |
| This SR This SR is is modified modified by by a a Note Note that that states states thethe SRSR is is not not required required to be to be performed until performed 24 hours until 24 hours afterafter aa required required pump pump is is not not inin operation.
| |
| operation.
| |
| BWOG STS BWOG STS B 3.4.8-3 B 3.4.8-3 Rev. 3.0, 03/31/04 Rev. 3.0, 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Pressurizer Pressurizer B 3.4.9 B 3.4.9 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| Six hours Six hours is is a a reasonable reasonable time time based based upon upon operating operating experience experience to to reach reach MODE 3 MODE 3 from from fullfull power power without without challenging challenging plantplant systems systems and and operators.
| |
| operators.
| |
| Further pressure Further pressure and and temperature temperature reduction reduction to MODE 4 to MODE 4 with with RCS RCS temperature SI[275I0F temperature places the
| |
| [27SrF places the plant plant into into a MODE where a MODE where the the LCO L C 0 is is not not applicable. The applicable. [24] hour The [24] hour Completion Completion Time Time toto reach reach the the nonapplicable nonapplicable MODE is MODE is reasonable reasonable based based upon upon operating operating experience.
| |
| experience.
| |
| If the If the [emergency]
| |
| [emergency] power power supplies supplies to to the the heaters heaters are are not not capable capable of of providing [126]
| |
| providing [I261 kW,kW, or or the the pressurizer pressurizer heaters heaters areare inoperable, inoperable, restoration restoration is required is required in 72 hours.
| |
| in 72 hours. The The Completion Completion Time Time of of 72 72 hours hours is is reasonable reasonable considering the considering the anticipation anticipation thatthat a a demand demand caused caused by by loss loss of offsite of offsite power will power will notnot occur occur in in this this period.
| |
| period. Pressure Pressure control control may may be be maintained maintained during this during this time time using using normal normal station station powered powered heaters.
| |
| heaters.
| |
| D.l and 0.1 and 0.2D.2 If pressurizer If pressurizer heater heater capability capability cannot cannot be be restored restored within within thethe allowed allowed Completion Time Completion Time of of Required Required Action the plant C.?, the Action C.1, plant must must bebe brought brought toto aa MODE in MODE in which which the L C 0 does the LCO does notnot apply.
| |
| apply. To To achieve achieve thisthis status, status, the the plant plant must be must be brought brought to MODE 33 within to MODE within 6 6 hours hours andand toto MODE MODE 4 4 within within the the following 6 following 6 hours.
| |
| hours. The The Completion Completion Time Time of 6 hours of 6 hours is is reasonable, reasonable, based based on operating on operating experience, experience, to to reach reach MODE MODE 33 from from full full power power conditions conditions in in an orderly an orderly manner manner and and without without challenging challenging plant plant systems.
| |
| systems. Similarly, Similarly, the the Completion Time Completion Time of 12 hours of 12 hours toto reach reach MODE MODE 4 is is reasonable reasonable based based on on operating experience operating experience to to achieve achieve power power reduction reduction from from fullfull power power conditions in conditions in an an orderly orderly manner manner and and without challenging plant without challenging plant systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE SR 3.4.9.1 SR 3.4.9.1 REQUIREMENTS REQUIREMENTS This SR This SR requires requires that that during during steady steady state state operation, operation, pressurizer pressurizer water water level is level is maintained maintained below below the the nominal nominal upper upper limit limit to to provide provide a a minimum minimum space for space for a a steam b bble. The steam ~bble. The Surveillance Surveillance is is periormed performed by observing by observing the indicated the level.$he 12 indicated level.12he 12 hour hour interval interval has has been been shown shown by by operating operating practice to practice to be suffic~entto be sufficient to regularly regularly assess assess thethe level level for any deviation for any deviation and and verify that operation verify that operation is is within safety analyses within safety analyses assumptions.
| |
| assumptions. Alarms Alarms areare also available also available for early detection for early detection of of abnormal abnormal levellevel indications.
| |
| indications. 9 STS BWOG STS BWOG 3.4.9-5 B 3.4.9-5 B Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Pressurizer Pressurizer B 3.4.9 B 3.4.9 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)
| |
| (continued)
| |
| [SR 3.4.9.2
| |
| [SR 3.4.9.2 The SR requires The SR requires the the power power supplies supplies are are capable capable ofof producing producing the the minimum power minimum power andand the the associated associated pressurizer pressurizer heaters heaters are are verified verified to to be be at their at their design design rating.
| |
| rating. (This (This may may bebe done done byby testing testing the the power power supply supply output and by performing an an electrical electrical check check on on heater heater element element continuity continuity and resistance.fThe Frequency of of ((18] months] is
| |
| ((I81 months] is considered considered adequate adequate to detect heater~gradation and has has been been shown shown by by operating operating experience to be acceptable.
| |
| experience to be acceptable. ]
| |
| w/3$z&xa
| |
| ]
| |
| ~-----
| |
| .~ J.
| |
| Inse,rL2...
| |
| 0
| |
| [ S R 3.4.9.3
| |
| [SR 3.4.9.3 This SR This SR isis not not applicable applicable if if the the heaters heaters are are permanently permanently powered powered by by 1E power 1E power supplies.
| |
| supplies.
| |
| This Surveillance This Surveillance demonstrates demonstrates that the heaters that the heaters can can be be manually manually to, and transferred to, transferred and energized energized by,by, emergency emergency powerpower supplies.(jhe supplies.nhe Frequency of Frequency [I81 months of [18] months is is based based on on a a typical typical fuel fuel cycle cycle and is and is consistent with similar verifications of emergency power.
| |
| REFERENCES 1. NUREG*0737, November 1980.
| |
| BWOG STS BWOG STS B 3.4.9-6 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Pressurizer PORV Pressurizer PORV B 3.4.11 B 3.4.11 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued) and 8.2 B.1 and B.1 B.2 If the If the block block valve valve is is inoperable, inoperable, itit mustmust be be restored restored to OPERABLE status to OPERABLE status within within 1 1 hour.
| |
| hour. The The prime prime importance importance for for the the capability capability to to close close the the block block valve valve is to isolate is to isolate aa stuck stuck open open PORV.
| |
| PORV. Therefore, Therefore, if if the the block block valve valve cannot be cannot be restored restored to to OPERABLE OPERABLE status status within within 1 hour, the 1 hour, the Required Required Action Action is is to to close close the the block block valve valve and and remove remove power power within within 1 1 hour hour rendering the rendering the PORV PORV isolated.
| |
| isolated. The The 1 hour Completion I hour Completion TimesTimes areare consistent with consistent an allowance with an allowance of of some some timetime for for correcting correcting minor minor problems, problems, restoring the restoring the valve valve toto operation, operation, and and establishing establishing correct correct valve valve positions positions and restricting and restricting the the time time without adequate protection without adequate protection against against RCSRCS depressurization.
| |
| depressurization.
| |
| and Co2 C.l and C.1 C.2 If the If the Required Required ActionAction and and associated associated Completion Completion Time Time cannot cannot bebe met, met, the plant the plant must must be be brought brought to to aa MODE MODE in in which which thethe requirement requirement does does not not apply. To apply. To achieve achieve thisthis status, status, thethe plant plant must must be be brought brought to at least to at least MODE 3 MODE 3 within within 6 6 hours hours and to MODE 4 to MODE 4 within hours. The 12 hours.
| |
| within 12 The 6 hours hours allowed is allowed is reasonable, reasonable, based based on on operating operating experience, experience, to to reach MODE 3 reach MODE 3 from full from full power power conditions conditions in in an an orderly orderly manner manner and and without challenging without challenging plant systems.
| |
| plant systems. Similarly, Similarly, the the 1212 hours hours allowed allowed is is reasonable, reasonable, basedbased onon operating experience, operating experience, to to reach reach MODEMODE 4 from from full full power power conditions conditions inin an an orderly manner orderly manner and and without without challenging challenging plant plant systems.
| |
| systems.
| |
| SURVEILLANCE SURVEILLANCE SR 3.4.11.1 SR 3.4.1 1.I REQUIREMENTS REQUIREMENTS Block valve Block valve cycling cycling verifies verifies that that itit can can bebe closed closed ifif needed.lThe needed. basis for the Frequency the Frequency of 92 days of 92 days isis the the ASME Code (Ref. 3). Bloc'r'~alve Code (Ref.
| |
| cycling, as cycling, as stated stated in in the the Note, Note, is is not not required required to to be be performed when it is closed for closed for isolation; isolation; cycling cycling could could increase increase thethe hazard hazard of of an an existin::a.-_.L--_-...
| |
| degraded flow degraded flow path.
| |
| path.
| |
| SR 3.4.11.2 PORV cycling PORV cycling demonstrates demonstrates its its function.
| |
| function. [heE h e Frequency Frequency of 18 months of 18 months isis based on based on a a typical typical refueling refueling cyclecycle and and industry industry accepted accepted p ractice3 practi~
| |
| erID BWOG STS SWaG STS B 3.4.11-4 83.4.11-4 Rev. 3.1, Rev. 12/01/05 3.1, 12/01/05
| |
| | |
| TSTF-425, Rev. 3 PORV Pressurizer PORV Pressurizer B 3.4.11 B 3.4.1 1 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)
| |
| (continued)
| |
| SR 3.4.11.3 This Surveillance This Surveillance is is not not required required for for plants plants with with permanent permanent 1E 1E power power supplies to supplies to the the valves.
| |
| valves.
| |
| This SR demonstrates This SR demonstrates thatthat emergency emergency powerpower can can be be provided provided andand is is performed by performed by transferring transferring pow1f.
| |
| powe fromfrom the the normal normal supply supply to to the the emergency emergency supply and supply and cycling cycling the valves.&he the valves. Frequency of LIhe Frequency months is of 18 months is based based on on a typical a typical refueling refueling cycle cycle and and industry industry accepted accepted practice.
| |
| practice.
| |
| REFERENCES REFERENCES 1.
| |
| : 1. NUREG-0737, Paragraph NUREG-0737, Ill, G.1, Paragraph III, G.l, November November 1980.
| |
| 1980. ______I_C 2.
| |
| : 2. NRC IE NRC IE Bulletin Bulletin 79-05B, 79-056, April 21, 1979.
| |
| April 21, 1979.
| |
| 3.
| |
| : 3. ASME Code for ASME Code for Operation Operation and and Maintenance Maintenance ofof Nuclear Nuclear Power Power Plants.
| |
| Plants.
| |
| BWOG STS BWOG STS B 3.4.11-5 Rev. 3.1,12/01/05 Rev. 3.1, 12/01/05
| |
| | |
| TSTF-425, Rev. 3 Low Temperature Low Temperature Overpressure Overpressure Protection Protection (LTOP)
| |
| (LTOP) SystemSystem B 3.4.12 B3.4.12 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued) 11 With the With the pressurizer pressurizer level level above 12201 inches above [220} inches and and the the PORV PORV inoperable inoperable or the or the LTOP LTOP System System inoperable inoperable for for any any reason reason otherother than than cited cited inin Condition A Condition A through through H, H, Required Required Action Action 1.1 requires the 1.1 requires the RCS RCS depressurized and depressurized and vented vented within within 1212 hours hours from from thethe time time either either Condition Condition started.
| |
| started.
| |
| One or One or more more vents vents maymay be be used.
| |
| used. A A vent vent size size of;::: [0.75] square of 2 [0.751 square inches inches is is specified. This specified. This vent vent size size assumes assumes 100 100 psig psig backpressure.
| |
| backpressure. BecauseBecause makeup may makeup may be be required, required, the the vent vent size size accommodates accommodates inadvertentinadvertent full full makeup system makeup system operation.
| |
| operation. Such Such a a vent vent keeps keeps the the pressure pressure fromfrom fullfull flow flow of [one]
| |
| of [one] makeup makeup pump pump with with aa wide open makeup wide open makeup control control valve valve within within thethe L C 0 limit.
| |
| LCO limit.
| |
| PORV has The PORV The has a a larger larger areaarea andand may may be be used used for venting by for venting by opening opening and and open.
| |
| locking itit open.
| |
| locking This size This RCS vent size RCS vent or or the the PORVs PORVs a a vent vent cannot cannot ma'intain mahtain RCS RCS pressure pressure below LTOP below LTOP limits limits if the HPJ jf the HPI and CFT systems and CFT systems are are inadvertently inadvertently actuated.
| |
| actuated.
| |
| Therefore, verification Therefore, verification of of the the deactivation deactivation of of two two HPI HPI pumps, pumps, HPJHPI injection, injection, and the and CFTs must the CFTs must accompany accompany the the depressurizing depressurizing and and venting.
| |
| venting. SinceSince these systems these systems are required deactivated are required deactivated by by the LCO, SR the LCO, 3.4.12.1, SR 3.4.12.1, SR 3.4.12.2, SR 3.4.12.2, and and SRSR 3.4.12.3 3.4.12.3 require require verification verification of of their their deactivated deactivated status every status every 12 12 hours.
| |
| hours.
| |
| The Completion The Completion Time Time is is based based on operating operating experience experience that that this this activity activity can be can be accomplished accomplished in in this this time time period period andand on engineering evaluations on engineering evaluations indicating that indicating that a a limiting limiting LTOPLTOP transient transient is is not not likely likely inin this this time.
| |
| time.
| |
| SURVEILLANCE SURVEILLANCE SR 3.4.12.1, SR 3.4.12.1, SR SR 3.4.12.2, 3.4.12.2, and and SRSR 3.4.12.3 3.4.12.3 REQUIREMENTS REQUIREMENTS Verifications must Verifications must be be performed performed that that only only [one]
| |
| [one] makeup makeup pump pump is is capable capable of injecting of injecting into into the RCS, the the RCS, the HPI HPI isis deactivated, deactivated, and and thethe CFT CFT discharge discharge isolation valves isolation valves are are closed closed and and immobilized.
| |
| immobilized. These These Surveillances Surveillances ensure ensure the minimum the minimum coolant coolant input input capability capability willwill not not create create anan RCS RCS over overpressure ressure condition to condition to challenge challenge the hopf Inter)t81S) ho,w!' 1nterMs.J LTOP System.
| |
| the LTOP System. @he$h6eillancware he veillanc¢re re~ed r e w E h e 12
| |
| (!he 12 hour hour intervals intervals are are shown shown by by operating operating practice practice to to be be sufficient sufficient to to regularly assess regularly assess conditions conditions for for potential potential degradation degradation and and verify verify operation operation within the within the safety safety analysis.
| |
| analysis.
| |
| BWOG STS BWOG STS B 3.4.12-9 B 3.4.12-9 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Low Temperature Low Temperature Overpressure Overpressure Protection Protection (LTOP)
| |
| (LTOP) System System B 3.4.12 B3.4.12 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| SR 3.4.12.4 Verification of Verification of the the pressurizer pressurizer level level at at 5 [220] inches
| |
| ~ [220} inches byby observing observing control control room or room or other other indications indications ensures ensures a a cushion cushion of of sufficient sufficient size size is is available available to reduce to reduce the the rate rate ofof pressure pressure increase increase from from potential potential transients.
| |
| transients.
| |
| The 30 The 30 minute minute Surveillance Surveillance Frequency Frequency during during heatup heatup and and cooldown cooldown mustmust be performed be performed for for the the LCOL C 0 Applicability period when Applicability period when temperature temperature changes changes can cause can cause pressurizer pressurizer level level variations.
| |
| variations. This This Frequency Frequency may may bebe discontinued when discontinued when thethe endsends of these conditions of these conditions are are satisfied, satisfied, asas defined defined in plant in procedures.Ehereafter, the plant procedures.l!hereafter, the Surveillance Surveillance is is required required at 12 hour at 12 hour intervals3 intervals]
| |
| Ehese Frequencies
| |
| [hese Frequencies are are shown shown by by operating operating practice practice sufficient sufficient to to regularly regularly assess indications assess indications of of potential potential degradation degradation and and verify operation within verify operation within the the safety analysis.
| |
| safety analysis. ~V15e""f ~
| |
| SR 3.4.12.5 Verification that Verification that the the PORV PORV block block valve valve is is open open ensures ensures a a flow flow path path toto the the PORV. crhi~Siuired;rl2 PORV. Qhiw~E~uirecLat"T2 hour in~ls) hour intpmls3 f i c u r ~ & n t e r v a lhas G--'l-:-"':h-O-u.,-l'"-)'--O-T-h:!rnterval has been been shownshown by by operating operating practice practice sufficient sufficient to to regularly regularly assess conditions assess conditions for for potential potential degradation degradation and and verify verify operation operation is is within within the safety analysis.
| |
| the safety analysis. ~n.5e2i)
| |
| SR 3.4.12.6 RCS vent The RCS The vent of of at at least [0.75] square least [O.l5} square inches inches mustmust bebe verified verified open open forfor relief protection relief protection onlyonly if if the the vent is being vent is being used used to to satisfy satisfy the the requirements requirements of this of this LCO. Fora LCO. (for a vent vent valve valve not not locked locked open, open, thethe Frequency Frequency is is every every 12 hours.
| |
| 12 hours. Valves Valves thatthat areare sealed sealed oror secured secured in in the the open open position position areare considered "locked" considered "locked" in in this this context.
| |
| context. For For other other vent path(s) (e.g.,
| |
| vent path(s) (e.g., aa vent vent valve that valve is locked, that is locked, sealed, sealed, or or secured secured in position, a in position, a removed removed pressurizer pressurizer safety valve, safety valve, oror open manway), the open manway), the required required Frequency Frequency is is every every 31 31 days.
| |
| days.
| |
| Again, the Frequency Again, the Frequency intervals intervals consider consider operating operating practice practice toto determine determine adequacy to regularly assess conditions for adequacy to regularly assess conditions for potential degradation and verify operation verify operation within within thethe safety safety analysis.
| |
| analysis. ~ ~ n5er'i: ;{)
| |
| BWOG STS BWOG STS B 3.4.12-10 Rev. 3.0, Rev. 3.0. 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 Low Temperature Low Temperature Overpressure Overpressure Protection Protection (LTOP)
| |
| (LTOP) System System B 3.4.12 B3.4.12 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| The passive The passive ventvent path arrangement must path arrangement must onlyonly be open to be open be OPERABLE.
| |
| to be OPERABLE.
| |
| SR 3.4.12.7 A CHANNEL FUNCTIONAL A CHANNEL FUNCTIONAL TEST TEST is is required required withinwithin [12]
| |
| [12],!1ours after ours after decreasing RCS decreasing RCS temperature temperature to to S [283IoFand
| |
| ~ [283]OF and @VJiMY Gysry ~1 geyqthereafter to 31 @ySjthereafter to ensure the ensure setpoint is the setpoint is proper proper for for using using the the PORVPORV for for LTOP.
| |
| LTOP. A successful A successful test of test of the the required contact(s) of required contact(s) of a a channel channel relay relay may may be be performed performed by by the the verification of verification of the the change change of of state state of of aa single single contact contact of of the the relay.
| |
| relay. This This clarifies what clarifies what is is an an acceptable acceptable CHANNELCHANNEL FUNCTIONAL FUNCTIONAL TEST TEST ofof a a relay.
| |
| relay.
| |
| This is This is acceptable acceptable because because all all ofof thethe other other required required contacts contacts of of the the relay relay are verified are verified by by other other Technical Technical Specifications Specifications and and non-Technical non-Technical Specifications tests Specifications tests atat least least once once per per refueling refueling interval interval with with applicable applicable extensions. PORV extensions. PORV actuation actuation is is not not needed, needed, as as it could depressurize it could depressurize the the RCS.
| |
| RCS.
| |
| [I21 hour The [12]
| |
| The hour Frequency Frequency considers considers the the unlikelihood unlikelihood of a low of a low temperature temperature overpressure event overpressure event during during the the time.
| |
| time. ahe E h e 3131 day day Frequency Frequency is is based based on on industry accepted industry accepted practice practice andand is is acceptable acceptable by by experience experience with with equipment reliability.~c::c,_._~.
| |
| equipment reliability.
| |
| " XJ~.="; . .~,tZ> r"__."._.,*..,,
| |
| """",, . .'?
| |
| SR 3.4.12.8 he p~mance 0 NNEL CALlBR . . ve
| |
| [1 ~onths. he CHANNEL CALIBRATION for the LTOP setpoint ensures at the he PORV PORV will will be be actuated actuated at at thethe appropriate appropriate RCS RCS pressure pressure by verifying by verifying thethe accuracy accuracy of of the instrument string.
| |
| the instrument string. TheThe calibration calibration can can (j-zzg=--
| |
| @ only (The be e
| |
| performed in r{)<>~tt,)__O_n_l~ be performed in shutdown.
| |
| r ~ h Frequency Frequency shutdown.
| |
| considers a considers a typical typical refueling refueling cycle cycle andand industry industry accepted accepted practice.
| |
| practice. (!tf :: ~ ::OJ
| |
| -l REFERENCES REFERENCES 1.
| |
| : 1. CFR 50, 10 CFR 10 50, Appendix Appendix G. G. ~~ errY 2.
| |
| : 2. Generic Letter Generic Letter 88-11.
| |
| 88-11 3.
| |
| : 3. Section 15.
| |
| FSAR, Section FSAR, 15.
| |
| 4.
| |
| : 4. 10 CFR 10 50.46.
| |
| CFR 50.46.
| |
| 5.
| |
| : 5. CFR 50, 10 CFR 10 50, Appendix Appendix K. K.
| |
| BWOG STS BWOG STS B 3.4.12-11 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Operational RCS Operational LEAKAGE LEAKAGE B 3.4.13 B3.4.13 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued) injection and injection and return return flows]).
| |
| flows]). The The Surveillance Surveillance is is modified modified by by two two Notes.
| |
| Notes.
| |
| Note 1 Note 1 states states that that this this SR SR is is not not required required to to be be performed performed until until 12 12 hours hours after establishing after establishing steady steady statestate operation.
| |
| operation. The The 12 12 hour hour allowance allowance providesprovides sufficient time sufficient time to to collect collect and and process process allall necessary necessary data data after after stable stable plant plant conditions are conditions are established.
| |
| established.
| |
| Steady state Steady state operation operation is is required required to to perform perform a a proper proper water water inventory inventory balance since balance since calculations calculations duringduring maneuvering maneuvering are are not not useful.
| |
| useful. For For RCSRCS operational LEAKAGE operational LEAKAGE determination determination by by water water inventory inventory balance, balance, steady steady state is state is defined defined as as stable stable RCSRCS pressure, pressure, temperature, temperature, power power level, level, pressurizer and pressurizer and makeup makeup tank tank levels, levels, makeup makeup and and letdown, letdown, and and RCP RCP pump seal pump seal injection injection and and return return flows.
| |
| flows.
| |
| An early An early warning warning of of pressure pressure boundary boundary LEAKAGE LEAKAGE or or unidentified unidentified LEAKAGE is LEAKAGE is provided provided by by thethe automatic automatic systems systems thatthat monitor monitor the the containment atmosphere containment atmosphere radioactivity radioactivity and and the the containment containment sump sump level.level.
| |
| These leakage These leakage detection detection systems systems are are specified specified in in LCO 3.4.15, "RCS L C 0 3.4.15, "RCS Leakage Detection Leakage Detection Instrumentation."
| |
| Instrumentation."
| |
| Note 2 Note 2 states states that that this this SR SR is is not not applicable applicable to to primary primary to to secondary secondary LEAKAGE because LEAKAGE because LEAKAGE LEAKAGE of of 150 150 gallons gallons perper day day cannot cannot be be measured accurately measured accurately by by anan RCSRCS water inventory balance.
| |
| water inventory balance.
| |
| E h e 72
| |
| {jhe 72 hourhour Frequency Frequency is is aa reasonable reasonable interval interval to to trend trend LEAKAGE LEAKAGE and and recognizes the recognizes the importance importance of of early early leakage leakage detection detection in in the the prevention prevention of of
| |
| ~ E 7I D accidents.
| |
| accidents. ~S~r
| |
| -i-i SR 3.4.13.2 This SR This SR verifies verifies that that primary primary to to secondary secondary LEAKAGE LEAKAGE is is less less than than or or equal equal to 150 to 150 gallons gallons per per day day through through anyone any one SG.SG. Satisfying Satisfying the the primary primary to to secondary LEAKAGE secondary LEAKAGE limit limit ensures ensures thatthat the the operational operational LEAKAGE LEAKAGE performance criterion performance criterion in in the the Steam Steam Generator Generator Program Program is is met.
| |
| met. If If this this SR SR is not is not met, met, compliance compliance with with LCO L C 0 3.4.17, "Steam Generator 3.4.17, "Steam Generator Tube Tube Integrity," should Integrity," should be be evaluated.
| |
| evaluated. The The 150 150 gallons gallons per per day day limit limit isis measured at measured at room room temperature temperature as as described described in in Reference Reference 5. The
| |
| : 5. The operational LEAKAGE operational LEAKAGE rate rate limit limit applies applies toto LEAKAGE LEAKAGE through through anyoneany one SG. If SG. If itit is is not not practical practical toto assign assign thethe LEAKAGE LEAKAGE to to anan individual individual SG, SG, allall the primary the primary to to secondary secondary LEAKAGE LEAKAGE should should be be conservatively conservatively assumed assumed to to be from be from one one SG.SG.
| |
| BWOG STS BWOG STS B 3.4.1 3-5 B 3.4.13-5 Rev. 3.1, Rev. 3.1, 12/01/05 12/01/05
| |
| | |
| TSTF-425, Rev. 3 RCS Operational RCS Operational LEAKAGE LEAKAGE B 3.4.13 B3.4.13 BASES BASES p~
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)
| |
| (continued)
| |
| The Surveillance The Surveillance is is modified modified by by aa Note Note which which states states that that the the Surveillance Surveillance is not is not required required to to be be performed performed until until 12 12 hours hours after after establishment establishment of of steady state steady state operation.
| |
| operation. ForFor RCS RCS primary primary to to secondary secondary LEAKAGE LEAKAGE determination, steady determination, steady state state is is defined defined as as stable RCS pressure, stable RCS pressure, temperature, power temperature, power level, level, pressurizer pressurizer and and makeup makeup tanktank levels, levels, makeup makeup and letdown, and letdown, and and RCP RCP seal seal injection injection and and return return flows.
| |
| flows.
| |
| c ~ h Surveillance
| |
| [The Surveillance e Frequency of Frequency of 72 72 hours hours is is a a reasonable reasonable interval interval to to trend trend primary to secondary LEAKAGE and recognizes the importance <;>f early leakage detection in the prevention of accidents.flThe primary to ---...:...-
| |
| secondary LEAKAGE is determined using continuous process radiation monitors or radiochemical grab sampling in accordance with the EPRI guidelines (Ref. 5).
| |
| REFERENCES REFERENCES 1.
| |
| : 1. 10 CFR 50, 10 CFR 50, Appendix Appendix A, A, GOC 30.
| |
| GDC 30.
| |
| 2.
| |
| : 2. Regulatory Guide Regulatory Guide 1.45, May 1973.
| |
| 1.45, May 1973.
| |
| 3.
| |
| : 3. FSAR, Chapter FSAR, [ I 51.
| |
| Chapter [15].
| |
| 4.
| |
| : 4. 97-06, "Steam NEI 97-06, NEJ "Steam Generator Generator Program Program Guidelines."
| |
| Guidelines."
| |
| 5.
| |
| : 5. EPRI, "Pressurized EPRI, "Pressurized Water Water Reactor Reactor Primary-to-Secondary Primary-to-Secondary Leak Leak Guidelines."
| |
| Guidelines."
| |
| BWOG STS BWOG STS B 3.4.13-6 3.1, 12101105 Rev. 3.1,12/01/05 Rev.
| |
| | |
| TSTF-425, Rev. 3 RCS PIV Leakage B 3.4.14 BASES SURVEILLANCE SR 3.4.14.1 REQUIREMENTS Performance of leakage testing on each RCS PIV or isolation valve used to satisfy Required Action A.1 or A.2 is required to verify that leakage is below the specified limit and to identify each leaking valve. The leakage limit of 0.5 gpm per inch of nominal valve diameter up to 5 gpm maximum applies to each valve. Leakage testing requires a stable pressure condition.
| |
| For the two PIVs in series, the leakage requirement applies to each valve individually and not to the combined leakage across both valves. If the PIVs are not individually leakage tested, one valve may have failed completely and not detected if the other valve in series meets the leakage valves would be lost. .w
| |
| .ffi requirement. In this situation, the protection provided bred Testing is to be performed every@months,_
| |
| ~1Y1Cl.
| |
| b re everymonths*.. *- cal refueli e,..1~.,.deJ..
| |
| be. e",1e...d 1\1a. be d c de if the plant does not go into MODE 5 for at least 7 days. The [18 month]
| |
| Frequency is consistent with 10 CFR 50.55a(g) (Ref. 8) as contained in the Inservice Testing Program, is within frequency allowed by the American Society of Mechanical Engineers (ASME) Code (Ref. 7), and is based on the need to perform such surveillances under conditions that apply during an outage and the potential for an unplanned transient if the
| |
| <c(J:n:se,f>> .
| |
| Surveillance were performed with the plant at power. <<-~nse,(J)
| |
| [ In addition, testing must be performed once after the valve has been opened by flow or exercised to ensure tight reseating. PIVs disturbed in the performance of this Surveillance should also be tested unless documentation shows that an infinite testing loop cannot practically be avoided. Testing must be performed within 24 hours after the valve has been reseated. Within 24 hours is a reasonable and practical time limit for performing this test after opening or reseating a valve. ]
| |
| The leakage limit is to be met at the RCS pressure associated with MODES 1 and 2. This permits leakage testing at high differential pressures with stable conditions not possible in the MODES with lower pressures.
| |
| Entry into MODES 3 and 4 is allowed to establish the necessary differential pressures and stable conditions to allow for performance of this Surveillance. The Note that allows this provision is complimentary to the Frequency of prior to entry into MODE 2 whenever the unit has been BWOG STS B 3.4.14-5 Rev. 3.1,12/01/05
| |
| | |
| TSTF-425, Rev. 3 RCS PIV RCS PIV Leakage Leakage B 3.4.14 B 3.4.14 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| MODE 5 in MODE in 5 for for 7 7 days days or or more, more, ifif leakage leakage testing testing has has notnot been been performed performed in the in the previous previous 9 9 months.
| |
| months. In In addition, addition, this this Surveillance Surveillance is is not not required required to to be performed be performed on on the the DHR DHR System System when when the the DHR DHR System System is is aligned aligned to to the RCS the RCS in in the the decaydecay heat heat removalremoval mode mode of of operation.
| |
| operation. PIVs PlVs contained contained in in the DHR the DHR flow flow path path must must be be leakage leakage rate rate tested tested after DHR is after DHR is secured secured and and stable unit stable unit conditions conditions and and the the necessary necessary differential differential pressures pressures are are established.
| |
| established.
| |
| -----------------------------------REVI REV1EWER'S NOTE-----------..----
| |
| EWER'S NOTE----------------------------.------ ------ --.....--------
| |
| The "24 The hour..." Frequency "24 hour..... Frequency of of performance performance for for Surveillance Surveillance Requirement 3.4.14.1 Requirement 3.4.14.1 is is not not required required for for B&W B&W Owner'sOwner's GroupGroup plants plants licensed prior licensed prior to 1980. These to 1980. These plants plants were were licensedlicensed prior prior to to the the NRCNRC establishing formal Technical Specification establishing formal Technical Specification controls for pressure isolation controls for pressure isolation valves. Subsequently, valves. Subsequently, these these earlier earlier plants plants had had their their licenses licenses modified modified by by NRC Order NRC Order to to require require certain certain PIV PIV testing testing Frequencies Frequencies (excluding (excluding the the "24 hour.
| |
| "24 hour..." Frequency) be
| |
| .." Frequency) be included included in in that that plant's plant's Technical Technical Specifications. Based Specifications. Based upon upon the the information information available available to to the the Staff Staff at at the the time, the time, the content content of of those those Orders Orders was considered acceptable.
| |
| was considered acceptable. Since Since 11980, 980, the the NRC NRC Staff Staff has has determined determined an an additional additional PIV PIV leakage leakage rate rate determination is determination is required required within within 24 24 hours hours followingfollowing actuation actuation of of the the valve valve and flow and flow through through the the valve.
| |
| valve. This This is is necessary necessary in in order order to to ensure ensure the PIV's the PIV's ability to ability to support support the the integrity integrity of of the the reactor reactor coolant coolant pressure pressure boundary.
| |
| boundary.
| |
| The Revised The Revised Standard Standard Technical Technical Specifications Specifications include include the the "24 hours..."
| |
| "24 hours.....
| |
| Frequency to Frequency to reflect reflect current current NRC NRC Staff Staff position position on on the the need need to to include include this this test requirement test requirement within Technical Specifications.
| |
| within Technical Specifications.
| |
| --------------------------*--------*---*-+++*--**------------------------------------------------
| |
| [ SR 3.4.14.2
| |
| [SR 3.4.14.2 and and SR SR 3.4.14.3 3.4.14.3 Verifying that Verifying that the the DHR DHR autoclosure autoclosure interlocks interlocks are are OPERABLE OPERABLE ensures ensures that RCS that RCS pressure pressure will will not not pressurize pressurize the the DHR DHR systemsystem beyond beyond 125% 125% of of its design its design pressure pressure of of [600]
| |
| [600] psig. psig. The The interlock interlock setpointsetpoint thatthat prevents prevents the the valves from valves from being being opened opened is is set set so so the the actual actual RCS RCS pressure pressure must must be be
| |
| [425] psig
| |
| < [425]
| |
| < psig to to open open the the valves.
| |
| valves. This This setpoint setpoint ensures ensures the the DHR DHR design design pressure will pressure will notnot be be exceeded exceeded and and the the DHR DHR relief relief valves valves will will not not lift.
| |
| lift. [he Ehe 18 month 18 month Frequency Frequency is is based based on on the the need need to to perform perform thisthis Surveillance Surveillance under the under the conditions conditions that that apply apply during during a a plant plant outage outage andand the the potential potential for for an unplanned an unplanned transient transient if the Surveillance ifthe Surveillance was performed with was performed the reactor with the reactor at power.
| |
| at power. The The 18 18 month month Frequency Frequency is is also also acceptable acceptable basedbased on on consideration of consideration of thethe design design reliability reliability (and (and confirming confirming operating operating experience) of experience) of thethe equipment.
| |
| equipment. ~
| |
| -Lnserf-l)
| |
| BWOG STS BWOG STS B 3.4.14-6 B 3.4.14-6 Rev. 3.1, Rev. 3.1, 12/01/05 12/01/05
| |
| | |
| TSTF-425, Rev. 3 RCS Leakage RCS Leakage Detection Detection Instrumentation Instrumentation BB 3.4.15 3.4.15 BASES BASES SURVEILLANCE SURVEILLANCE SR 3.4.15.1 SR 3.4.15.1 REQUIREMENTS REQUIREMENTS SR 3.4.15.1 SR 3.4.15.1 requires requires the the performance performance of of aa CHANNEL CHANNEL CHECK CHECK of of the the required containment required containment atmosphere atmosphere radioactivity radioactivity monitor.
| |
| monitor. TheThe check check gives gives reasonable confidence reasonable confidence that that each each channel channel is is operating properly.Ehe operating properly.[f.he Frequencyof of 1212 hours hours is is based based on on instrument instrument reliability reliability and and isis reasonable reasonable Frequency for detecting off normal conditions.
| |
| for detecting off normal conditions. ~
| |
| +----@5=~
| |
| s:e r::t; .~
| |
| SR 3.4.15.2 SR 3.4.15.2 SR 3.4.15.2 requires requires thethe performance performance of of aa CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TEST of TEST of the the required required containment containment atmosphere atmosphere radioactivity radioactivity monitor.
| |
| monitor. A A successful test successful test of of the the required required contact(s) contact(s) of of aa channel channel relay relay may may be be performed by performed by thethe verification verification of of the the change change of of state state of of aa single single contact contact of of the relay.
| |
| the relay. This This clarifies clarifies what what is is an an acceptable acceptable CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL TEST of TEST of aa relay.
| |
| relay. ThisThis is is acceptable acceptable because because all all of of the the other other required required contacts of contacts of the the relay relay are are verified verified byby other other Technical Technical Specifications Specifications and and non-Technical Specifications non-Technical Specifications tests tests at at least least once once perper refueling refueling interval interval with with applicable extensions.
| |
| applicable extensions. The The test test ensures ensures that that the the monitor monitor can can perform perform itsits function in function in the the desired desired manner.
| |
| manner. The The test test verifies verifies the the alarm setpoint and alarm setpoint and relative accuracy relative accuracy of of the the instrument string.Ehe instrument string. Frequency of rrhe Frequency of 92 days 92 days considers instrument instrument reliability, reliability, and and operating operating experience experience has has shown shown itit
| |
| +--t ~
| |
| considers proper for for detecting detecting degradation.
| |
| degradation. ~~:- - - - : - - C%~~;r proper
| |
| -E2GJzl SR 3.4.15.3 SR 3.4.15.3 and and SR 3.4.15.4 SR 3.4.15.4 These SRs These SRs require require the the performance performance of of aa CHANNEL CHANNEL CALIBRATION CALIBRATION for for each of each of the the required required RCS RCS leakage leakage detection detection instrumentation instrumentation channels.
| |
| channels.
| |
| The calibration The calibration verifies verifies thethe accuracy accuracy of of the the instrument instrument string, string, including including thethe instruments located instruments located inside containment.Ehe Frequency inside containment.[fhe Frequency of [I81 months of [18] months is is a typical refueling cycle and considers channel reliability. Again, _ - ' __
| |
| operating experience has proven this Frequency is acceptable.
| |
| REFERENCES REFERENCES 1.
| |
| : 1. 10 CFR 10 CFR 50, 50, Appendix Appendix A, A, Section Section IV, GDC 30.
| |
| IV, GOC 30.
| |
| 2.
| |
| : 2. Regulatory Guide Regulatory Guide 1.45.
| |
| 1.45.
| |
| 3.
| |
| : 3. FSAR, Section FSAR, Section (( ]1 .,
| |
| BWOG STS BWOG STS B 3.4.15-5 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Specific RCS Specific Activity Activity BB 3.4.16 3.4.16 BASES BASES ACTIONS (continued)
| |
| ACTIONS (continued)
| |
| With the With the gross gross specific specific activity activity in excess of in excess of the the allowed allowed limit, limit, the the unit unit must must be placed be placed in in a a MODE MODE in in which which the the requirement requirement does does not not apply.
| |
| apply.
| |
| The allowed The allowed Completion Completion Time Time of of 66 hours hours toto reach reach MODEMODE 3 3 and and RCSRCS average temperature average temperature < 500°F lowers
| |
| < 500°F lowers the the saturation saturation pressure pressure of of the the reactor coolant reactor coolant below below thethe setpoints setpoints of of the the main main steam steam safety safety valves, valves, and and prevents venting prevents venting the the SG SG to to the the environment environment in in an an SGTR SGTR event.
| |
| event. The The Completion Time Completion Time of 6 hours of 6 hours is is required required to to reach reach MODE MODE 3 3 from from full full power power conditions in conditions in an an orderly orderly manner manner and and without without challenging challenging reactor reactor emergency systems.
| |
| emergency systems.
| |
| SURVEILLANCE SURVEILLANCE 3.4.16.1 SR 3.4.16.1 SR REQUIREMENTS REQUIREMENTS 3.4.16.1 requires SR 3.4.16.1 SR requires performing performing a a gamma gamma isotopic isotopic anal~SiS sis as as a a measure measure of the of the gross gross specific specific activity activity ofof thethe reactor coolantQWst reactor coolant@ m e r st #e'i§ID
| |
| .&-7(~. While While basically basically a a quantitative quantitative measure measure of a of radionuclides h half with half lives longer lives longer thanthan 15 15 minutes, minutes, excluding excluding iodines, iodines, thisthis measurement measurement is is the the sum of sum the degassed of the degassed gamma gamma activities activities and and thethe gaseous gaseous gammagamma activities activities in the in the sample sample taken.taken. ThisThis Surveillance Surveillance provides provides an an indication indication of of any any increase in increase in gross gross specific specific activity.
| |
| activity.
| |
| Trending the Trending the results results of of this this Surveillance Surveillance allows allows proper proper remedial remedial action action toto be taken be taken before before reaching reaching the the LCOL C 0 limit limit under under normal normal operating operating conditions. The The Surveillance Surveillance is is applicable applicable in in MODES MODES 1 1 and and 2,2, and and in in F
| |
| conditions.
| |
| MODE 3 MODE 3 with with RCS RCS average average temperature temperature at at least least 500°F.rThe 500°F. The 7 7 day day Frequency considers Frequency considers the the unlikelihood unlikelihood of of a gross fuel a gross fuel failUre fai ure during during thatthat time period.
| |
| time period. ~
| |
| 1: f\.S e 1,,1: 2
| |
| . 2)
| |
| SR 3.4.16.2 SR 3.4.16.2 This Surveillance This Surveillance is is performed performed in in MODE MODE 1 Ionly only to to ensure ensure the the iodine iodine remains within remains within limitlimit during during normal normal operation operation and and following following fast power fast power changes when changes when fuel fuel failure failure isis more more apt apt toto occur. r h e 14 occur. [The 14 day day Frequency Frequency is is adequate to adequate to trend changes in trend changes in the the iodine iodine activity activity71evel considering gross level considering gross IV\5erl*l specific activity specific activity IS is monitored monitored every every 7 days?/~he 7 days. Frequency, between The Frequency, between and 6 2-and 2 hours-after 6 hours after a power change a power change of r of 2= 15%
| |
| 15% RTP RTP within within aa 11 hour hour period, period, is established is established becausebecause the the iodine iodine levelslevels peak peak during during this this time time following following fuel failure; fuel failure; samples samples at at other other times times would would provide provide inaccurate inaccurate results.
| |
| results.
| |
| BWOG STS BWOG STS B 3.4.16-4 B 3.4.16-4 Rev. 3.0, Rev. 3.0, 03/31/04 03/31/04
| |
| | |
| TSTF-425, Rev. 3 RCS Specific Res Specific Activity Activity B 3.4.16 B 3.4.16 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued) (continued)
| |
| SR 3.4.16.3 SR 3.4.16.3 requires radiochemical r.:-;.~~"-=,~=u~ir;-;;e:.;.s radiochemical analysis analysis for for E determinatior(m]
| |
| determinatio~
| |
| ( 1 8 4 ~ ('s6 ~ s s~ with w ithe thet plant plant h operating operating in in MODE equilibr~um MODE 11 equilibrium condifions.
| |
| co-n""'I.... ihe determination directly
| |
| 'o.:..n-s...:..-"ih'-e--;!!:E-d':""etermination directly relates relates to to the the LCO and is LC0 and is required to verify plant operation within required to verify plant operation within the specific gross activity LCO the specific gross activity LC0 limit. The limit. The analysis analysis for for E E isis a measurement of a measurement of the the average average energies energies per per disintegration for disintegration for isotopes isotopes with with half half lives lives longer longer than than 15 15 minutes, minutes, excluding iodines.I!.he excluding rapidly. +_-----
| |
| change rapidly.
| |
| change E EK&eW) iodines. The Frequency tc=-------Q.
| |
| Frequency of
| |
| ::r-.~.
| |
| *.J..
| |
| of 184
| |
| ]'SeJ A-184 days days recognizes
| |
| . 'J recognizes E does not E does not
| |
| _ ~ _ .................."r' This SR This SR has has been modified by been modified by a Note that a Note that requires requires sampling sampling toto be be performed 31 performed 31 daysdays after after a a minimum minimum of of 2 2 EFPD EFPD andand 20 20 days days of MODE 1I of MODE operation have operation have elapsed elapsed since since the the reactor reactor was last subcritical was last subcritical for for at at least least hours. This 48 hours.
| |
| 48 This ensures ensures the the radioactive radioactive materials materials are are at at equilibrium equilibrium so the so the analysis for analysis for E is is representative representative and and notnot skewed skewed by by a a crud crud burst burst or or other other similar abnormal similar abnormal event. event.
| |
| REFERENCES REFERENCES 1.
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| : 1. 10 CFR 10 CFR 100.11.100.11.
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| 2.
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| : 2. FSAR, Section FSAR, Section [15.6.31.[15.6.3].
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| BWOG STS BWOG STS B 3.4.16-5 3.0, 03/31/04 Rev. 3.0, Rev. 03/31/04
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| TSTF-425, Rev. 3 CFTs CFTs B 3.5.1 6 3.5.1 BASES BASES ACTIONS (continued)
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| ACTIONS (continued)
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| If one If one CFT CFT is is inoperable inoperable for for aa reason reason other other than than boron boron concentration, concentration, the the CFT must CFT must be be returned returned to to OPERABLE OPERABLE status status within within 11 hour.
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| hour. In In this this condition itit cannot condition cannot be be assumed assumed that that the the CFT CFT will will perform perform itsits required required function during function during a a LOCA.
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| LOCA. Due Due to to the the severity severity of of the the consequences consequences should should aa LOCA LOCA occuroccur in in these these conditions, conditions, the the 1Ihourhour Completion Completion Time Time to to open open the valve, the valve, remove remove powerpower to to the the valve, valve, or or restore restore the the proper proper water}}
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