LR-N18-0129, License Amendment Request to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements.

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License Amendment Request to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements.
ML19035A620
Person / Time
Site: Salem  PSEG icon.png
Issue date: 02/04/2019
From: Mcfeaters C
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LAR S18-06, LR-N18-0129
Download: ML19035A620 (27)
v • d • e


Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0PSEG NuclearLLC 10 CFR 50.90 LR-N18-0129 LAR S18-06 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos. 50-272 and 50-311

Subject:

License Amendment Request to Revise Technical Specifications to Adopt TSTF-547, "Clarification of Rod Position Requirements" In accordance with the provisions of 10 CFR 50.90, PSEG Nuclear LLC (PSEG) is submitting a request for an amendment to the Technical Specifications (TS) for Salem Generating Station (Salem) Units 1 and 2.

The proposed amendment revises the requirements on control and shutdown rods, and rod and bank position indication. Enclosure 1 provides a description and assessment of the proposed changes. Attachment 1 provides the existing TS pages marked up to show the proposed changes.

PSEG requests approval of the proposed amendment in accordance with the standard NRC approval process and schedule. Once approved, the amendment shall be implemented within 60 days.

In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated State of New Jersey Official.

There are no regulatory commitments contained in this letter.

If you have any questions or require additional information, please contact Mr. Brian Thomas at 856-339-2022.

LR-N18-0129 10 CFR 50.90 Page 2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on 2.. / Y /I q.

(Date)

Respectfully, Charles V. McFeaters Site Vice President Salem Generating Station

Enclosure:

Evaluation of the Proposed Changes Mark-up of Proposed Technical Specification Pages cc: Mr. D. Lew, Administrator, Region I, NRC Mr. J. Kim, Project Manager, NRC NRC Senior Resident Inspector, Salem Mr. P. Mulligan, Chief, NJBNE PSEG Corporate Commitment Tracking Coordinator Salem Commitment Tracking Coordinator

LR-N18-0129 LAR 518-06 Enclosure Evaluation of the Proposed Changes Table of Contents

1.0 DESCRIPTION

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 ASSESSMENT ................................................................................................................ 1 2.1 Applicability of Safety Evaluation ............................................................................... 1 2.2 Variations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

3.0 REGULATORY ANALYSIS

............................................................................................. 4 3.1 No Significant Hazards Consideration ....................................................................... 4 3.2 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 4.0 ENVIRONMENTAL EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7

LRN180129 LAR 81806 DESCRIPTION AND ASSESSMENT

1.0 DESCRIPTION

The proposed amendment revises the requirements on control and shutdown rods, and rod and bank position indication in Salem Technical Specification (TS) 3.1.3.1, "Movable Control Assemblies," Salem TS 3.1.3.4, "Shutdown Rod Insertion Limit," Salem TS 3.1.3.5, "Control Rod Insertion Limits," and Salem TS 3.1.3.2.1, "Position Indication Systems- Operating" to provide time to repair rod movement failures that do not affect rod operability, to provide an alternative to frequent use of the movable incore detector system when position indication for a rod is inoperable, to provide time for analog position indication instruments to read accurately after rod movement, and to correct conflicts between the TS.

2.0 ASSESSMENT 2.1 Applicability of Safety Evaluation PSEG Nuclear LLC (PSEG) has reviewed the safety evaluation for TSTF-547 provided to the Technical Specifications Task Force in a letter dated March 4, 2016. This review included a review of the NRC staff's evaluation, as well as the information provided in TSTF-547. As described in the subsequent paragraphs, PSEG has concluded that the justifications presented in the TSTF-547 proposal and the safety evaluation prepared by the NRC staff are applicable to Salem Units 1 and 2 and justify this amendment for the incorporation of the changes to the Salem TS.

2.2 Variations The Salem TS utilize different numbering and titles than the Standard Technical Specifications (NUREG- 1431) on which TSTF-547 was based. Specifically,

  • NUREG- 1431 TS 3.1.4, "Rod Group Alignment Limits" aligns to Salem TS 3.1.3.1, "Movable Control Assemblies"
  • NUREG-1431 TS 3.1.7, "Rod Position Indication" aligns to Salem TS 3.1.3.2.1, "Position Indication Systems- Operating" The following table provides the comparison of the Salem Unit 1 and 2 TS to the TSTF-547 changes to NUREG-1431:

TSTF-547 Change to NUREG-1431 Equivalent Salem Unit 1 and 2 TS 3.1.4 Required Action B.1 3.1.3.1 Action c.1 3.1.4 Required Actions B.2.4 and B.2.5 3.1.3.1 Action c.3.c SR 3.1.4.1 SR 4.1.3.1.1 SR 3.1.4.2 SR 4.1.3.1.2 3.1.5 Actions 3.1.3.4 Actions SR 3.1.5.1 SR 4.1.3.4 1

LR-N18-0129 LAR 518-06 3.1.6 Actions 3.1.3.5 Actions SR 3.1.6.2 SR 4.1.3.5 SR 3.1.6.3 Not in Salem TS 3.1.7 Condition A 3.1.3.2.1 Action a 3.1.7 Condition 8 3.1.3.2.1 Action b 3.1.7 Condition C 3.1.3.2.1 Action c 3.1.7 Condition D 3.1.3.2.1 Action d SR 3.1.7.1 SR 4.1.3.2.1.1 PSEG is proposing the following variations from the TS changes described in TSTF-547 or the applicable parts of the NRC Staff's Safety Evaluation dated March 4, 2016. These differences are administrative and do not affect the applicability of TSTF-547 to the Salem TS.

  • NUREG-1431 TS 3.1.4 Required Actions 8.2.4 and 8.2.5 are combined into new Required Action 8.4. New Required Action 8.4 is equivalent to the Salem TS 3.1.3.1 Action c.3.c. An editorial change is being made to Salem Unit 1 TS 3.1.3.1 Action c.3.c to insert the word 'and' between F0(Z) and FN L\H to make consistent with the Salem Unit 2 TS 3.1.3.1 Action c.3.c.
  • NUREG-1431 SR 3.1.4.1 adds two new notes. The allowance of Note 2 is already contained in Salem SR 4.1.3.1.1 and will remain unchanged. Note 1 is added as footnote
  • NUREG-1431 TS 3.1.5 new Condition A is incorporated into Salem TS 3.1.3.4 as new Action 1 and the existing action is numbered as 2. The insertion limits for the Salem shutdown banks in TS 3.1.3.4 are referenced to Salem TS definition 1.13a FULLY WITHDRAWN instead of the COLR. New Required Action A.2.1 refers to the shutdown margin (SDM) limits being in the COLR whereas the Salem SDM limits are contained in Salem TS 3.1.1.1. The existing Salem TS actions direct the operators to determine the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied, this language will be used in new Action 1 to be consistent with the existing Salem TS versus the TSTF-547 wording of "Verify SDM is within the limits...." New Required Action A.2.2 to initiate boration to restore SDM within limits is implemented by applying the action of Salem TS 3.1.1.1. The existing plant shutdown requirement in STS 3.1.5 Condition C is incorporated into new Salem Action 1 to align with the current format of the Salem TS.
  • NUREG-1431 TS 3.1.6 new Condition A is incorporated into Salem TS 3.1.3.5 as new Action 1 and the existing action is numbered as 2. Salem TS 3.1.3.5 only has requirements for insertion limits; therefore new Action 1 does not contain sequence or overlap limits. New Required Action A.1 refers to the shutdown bank insertion limits being in the COLR; the insertion limits for the Salem shutdown banks in TS 3.1.3.4 are referenced to Salem TS definition 1.13a FULLY WITHDRAWN. New Required Action A.2.1 refers to SDM limits being in the COLR whereas the Salem SDM limits are contained in Salem TS 3.1.1.1. The existing Salem TS actions direct the operators to determine the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied, this language will be used in new Action 1 to be consistent with the existing Salem TS versus the TSTF-547 wording of "Verify SDM is within the limits...." New Required 2

LR-N18-0129 LAR 518-06 Action A.2.2 to initiate boration to restore SDM within limits is implemented by applying the action of Salem TS 3.1.1.1. The existing plant shutdown requirement in NUREG-1431 TS 3.1.6 Condition C is incorporated into new Salem action 1 to align with the current format of the Salem TS. Salem TS 3.1.3.5 only has requirements for insertion limits and therefore does not have a separate surveillance for sequence and overlap limits.

  • NUREG-1431 TS 3.1.7 new Required Action A.2 is incorporated into Salem TS 3.1.3.2.1 Action a.2. Existing Salem TS 3.1.3.2.1 Action a.2 is renumbered Action a.3. New Salem TS 3.1.3.2.1 Action a.2 will use the terminology 'non-indicating rod(s)' instead of "inoperable [D]RPI" contained in TSTF-547 to remain consistent with the language in existing Salem TS 3.1.3.2.1 Action a.1. NUREG-1431 TS 3.1.7 new Required Action a.2 is modified to allow use of the movable incore detectors or the power distribution monitoring system (PDMS). The proposed change deviates from TSTF-547 in retaining the current allowance in the Salem TS to use the PDMS (TS 3.3.3.14) as an alternative to the movable incore detectors for indirectly verifying rod position. The NRC approved use of the PDMS (BEACON system) to determine the position of non-indicating rods in Salem Unit 1 and Unit 2 TS Amendments 237 and 218, respectively. Due to the format of the Salem TS, the unnecessary (redundant) NUREG-1431 TS 3.1.7 Required Action B.3 contained as Salem TS 3.1.3.2.1 Action b.3 will not be deleted. The editorial changes of NUREG-1431 Condition A, Required Action A.1, Condition B, Required Action B.4, Condition C, Required Action C.1 and Condition D are not incorporated due to the format of the Salem TS. The note for NUREG-1431 SR 3.1.7.1 is added as footnote *to SR 4.1.3.2.1.1.

[D]RPI to OPERABLE status, " with a Completion Time of "Prior to entering MODE 2 from MODE 3." This required Action was included in TSTF-547 in error. Because Required Actions A.1 and A.3 permit continued operation in the Applicability of TS 3.1.7 for an unlimited period of time, LCO 3.0.4.a may be used to enter Mode 2 from Mode 3.

As Required Actions A.1, A.2, and A.3 are joined by a logical OR, a licensee may choose to follow Required Action A.2 (which includes A.2.1 and A.2.2) after entering Mode 2. TSTF-54 7 did not add a Note requiring the Action to be followed as an "otherwise stated" allowance in LCO 3.0.2, so Required Action A.2.2 does not apply in Mode 3 and is not restrictive after Mode 2 is entered. For all these reasons, Required Action A.2.2 is moot. Further, the requirement is not needed to protect plant safety. The staff's Safety Evaluation for TSTF-547 noted that the monitoring method in Required Action A.2.1 is more appropriate than the existing method in Required Action A.1.

Therefore, its use should not be restricted. This variation has been previously approved in Watts Bar Amendments 120/20 (ADAMS Accession No. ML18079A029) and Braidwood/Byron Amendments 196/202 (ADAMS Accession No. ML18065A529).

  • Based on the content of the Salem TS Bases, none of the identified NUREG-1431 bases changes in TSTF-547 are applicable to the Salem TS Bases.
  • Finally the Model Application contained in TSTF-547 contains the final, "camera ready",

version of the revised TS change along with a markup of the affected TS. PSEG has elected to withhold this final version of the TS pages to avoid any potential implementation conflicts.

The Traveler and safety evaluation discuss the applicable regulatory requirements and guidance, including the 10 CFR 50, Appendix A, General Design Criteria (GDC). Salem was not licensed to the 10 CFR 50, Appendix A, GDC. Salem was designed and constructed in 3

LR-N18-0129 LAR 518-06 accordance with Atomic Energy Commission (AEC) proposed General Design Criteria published in July 1967. The applicable AEC proposed criteria, as document in Salem UFSAR Section 3.1, were compared to 10 CFR 50 Appendix A General Design Criteria (GDC) as discussed below.

The applicable GDC criteria are GDC 13, 26, and 28.

Criterion 13-lnstrumentation and control. Instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems. Appropriate controls shall be provided to maintain these variables and systems within prescribed operating ranges.

GDC Criterion 13 is similar to AEC Criterion 12.

Criterion 26-Reactivity control system redundancy and capability. Two independent reactivity control systems of different design principles shall be provided. One of the systems shall use control rods, preferably including a positive means for inserting the rods, and shall be capable of reliably controlling reactivity changes to assure that under conditions of normal operation, including anticipated operational occurrences, and with appropriate margin for malfunctions such as stuck rods, specified acceptable fuel design limits are not exceeded. The second reactivity control system shall be capable of reliably controlling the rate of reactivity changes resulting from planned, normal power changes (including xenon burnout) to assure acceptable fuel design limits are not exceeded. One of the systems shall be capable of holding the reactor core subcritical under cold conditions.

GDC Criterion 26 is similar to AEC Criterion 27, 28, 29, 30 and 31.

Criterion 28-Reactivity limits. The reactivity control systems shall be designed with appropriate limits on the potential amount and rate of reactivity increase to assure that the effects of postulated reactivity accidents can neither (1) result in damage to the reactor coolant pressure boundary greater than limited local yielding nor (2) sufficiently disturb the core, its support structures or other reactor pressure vessel internals to impair significantly the capability to cool the core. These postulated reactivity accidents shall include consideration of rod ejection (unless prevented by positive means), rod dropout, steam line rupture, changes in reactor coolant temperature and pressure, and cold water addition.

GDC Criterion 28 is similar to AEC Criterion 32.

This difference does not alter the conclusion that the proposed change is applicable to Salem.

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Analysis PSEG requests adoption of TSTF-547, "Clarification of Rod Position Requirements," which is an approved change to the Standard Technical Specifications, into the Salem Unit 1 and 2 Technical Specifications (TS). The proposed change revises the requirements on control and shutdown rods, and rod and bank position indication to provide time to repair rod movement failures that do not affect rod operability, to provide an alternative to frequent use of the 4

LR-N18-0129 LAR 518-06 movable incore detector system when position indication for a rod is inoperable, to provide time for analog position indication instruments to read accurately after rod movement, and to correct conflicts between the TS.

PSEG has evaluated whether or not a significant hazards consideration is involved with the proposed amendments by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment, " as discussed below:

1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No Control and shutdown rods are assumed to insert into the core to shut down the reactor in evaluated accidents. Rod insertion limits ensure that adequate negative reactivity is available to provide the assumed shutdown margin (SDM). Rod alignment and overlap limits maintain an appropriate power distribution and reactivity insertion profile.

Control and shutdown rods are initiators to several accidents previously evaluated, such as rod ejection. The proposed change does not change the limiting conditions for operation for the rods or make any technical changes to the Surveillance Requirements (SRs) governing the rods. Therefore, the proposed change has no significant effect on the probability of any accident previously evaluated.

Revising the TS Actions to provide a limited time to repair rod movement control has no effect on the SDM assumed in the accident analysis as the proposed Actions require verification that SDM is maintained. The effects on power distribution will not cause a significant increase in the consequences of any accident previously evaluated as all TS requirements on power distribution continue to be applicable.

Revising the TS Actions to provide an alternative to frequent use of the moveable incore detector system to verify the position of rods with inoperable rod position indicators does not change the requirement for the rods to be aligned and within the insertion limits.

Therefore, the assumptions used in any accidents previously evaluated are unchanged and there is no significant increase in the consequences.

The consequences of an accident that might occur during the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period provided for the analog rod position indication to stabilize after rod movement are no different than the consequences of the accident under the existing actions with the rod declared inoperable.

The proposed change to resolve the conflicts in the TS ensure that the intended Actions are followed when equipment is inoperable. Actions taken with inoperable equipment are not assumptions in the accidents previously evaluated and have no significant effect on the consequences.

5

LR-N18-0129 LAR 518-06 Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed amendment create the possibility of a new or different kind of accident from any previously evaluated?

Response: No The proposed change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed). The change does not alter assumptions made in the safety analyses. The proposed change does not alter the limiting conditions for operation for the rods or make any technical changes to the SRs governing the rods. The proposed change to actions maintains or improves safety when equipment is inoperable and does not introduce new failure modes.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.

3. Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No The proposed change to allow time for rod position indication to stabilize after rod movement and to allow an alternative method of verifying rod position has no effect on the safety margin as actual rod position is not affected. The proposed change to provide time to repair rods that are operable but immovable does not result in a significant reduction in the margin of safety because all rods must be verified to be Operable, and all other banks must be within the insertion limits. The remaining proposed changes to make the requirements internally consistent do not affect the margin of safety as the changes do not affect the ability of the rods to perform their specified safety function.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Based on the above, PSEG 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.

3.2 Conclusions 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 Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6

LR-N18-0129 LAR 518-06 4.0 ENVIRONMENTAL EVALUATION 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 effluents 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.

7

LR-N18-0129 LAR 518-06 Attachment 1 Mark-up of Proposed Technical Specification Pages The following Technical Specifications pages for Renewed Facility Operating License DPR- 70 are affected by this change request:

Technical Specification 3.1.3.1, Movable Control Assemblies Group Height 3/4 1- 18, 1- 18a 3.1.3.2.1, Position Indication Systems - Operating 3/4 1-19, 1- 19a 3.1.3.4, Shutdown Rod Insertion Limit 3/4 1-22 3.1.3.5, Control Rod Insertion Limit 3/4 1-23 The following Technical Specifications pages for Renewed Facility Operating License DPR-75 are affected by this change request:

Technical Specification 3.1.3.1, Movable Control Assemblies Group Height 3/4 1- 13, 1- 14 3.1.3.2.1, Position Indication Systems - Operating 3/4 1-16, 1- 16a 3.1.3.4, Shutdown Rod Insertion Limit 3/4 1-19 3.1.3.5, Control Rod Insertion Limit 3/4 1-20 1

LR-N18-0129 LAR 518-06 Technical Specification Mark- Up Inserts for Salem Unit 1 and 2 INSERT #1 (3.1.3.4 Limiting Condition for Operation)

Note-------------------------------------------

Not applicable to shutdown banks inserted while performing SR 4. 1. 3. 1. 2 INSERT #2 (3.1.3.4 Actions)

1. With one shutdown bank inserted =:;; 10 steps from FULLY WITHDRAWN; within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> verify all control banks are within the insertion limits specified in the COLR and determine the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied; and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restore the shutdown bank to FULLY WITHDRAWN or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

INSERT #3 (3.1.3.5 Limiting Condition for Operation)

Note-------------------------------------------

Not applicable to control banks inserted while performing SR 4. 1. 3. 1. 2 INSERT #4 (3.1.3.5 Actions)

1. With control bank A, B, or C inserted =:;; 10 steps beyond the insertion limits specified in the COLR; within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> verify all shutdown banks are FULLY WITHDRAWN and determine the SHUTDOWN MARGIN requirement of 3.1.1.1 is satisfied; and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restore the control bank to within the insertion limits specified in the COLR or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

INSERT #5 (SR 4.1.3.5)

Note-------------------------------------------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after associated rod motion.

INSERT #6 (3.1.3.2.1 Limiting Condition for Operation)

Note---------------------------------------------------------------

Individual RPis are not required to be OPERABLE for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> following movement of the associated rods.

2

LR-N18-0129 LAR 518-06 INSERT #7 (3.1.3.2.1 Action a)

2. Verify the position of the non-indicating rod(s) indirectly using the power distribution monitoring system (if power is above 25% RTP) or using the movable incore detectors (if power is less than 25%> or the power distribution monitoring system is inoperable) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and once per 31 EFPD thereafter, and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after discovery of each unintended rod movement, and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after each movement of the non-indicating rod(s) greater than 12 steps, and prior to T HERMAL POWER exceeding 50°/o RTP, and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after reaching RTP, or INSERT #8 (SR 4. 1.3.2.1.1)
  • Not required to be met for RP/s associated with rods that do not meet LCO 3. 1. 3. 1 3

FOR INFORMATION ONLY- NO 3/4.1 REACTIVITY CONTROL SYSTEMS CHANGES 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN- Tayg > 200°F LIMITING CONDITIO.N FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be 1.3% L1k/k.

APPLICABILITY: MODES 1, 2*, 3, and 4.

ACTION:

With the SHUTDOWN MARGIN< 1.3% L1k/k, immediately initiate and continue boration at 33 gpm of a solution containing 6,560 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

.SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be 1.3% Llklk:

a. Within one hou r after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod(s) is inoperable. If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod(s) .
b. When in MODES 1 or 2 , in accordance with the Surveillance Frequency Control Program by verifying that control banks are within the l imits in the COLR per Specification 3.1.3.5.
c. When in MODE 2##, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits in the COLR per specification 3.1.3.5.
  • See Special Test Exception 3.1 0.1
  1. With Keff 1.0
    1. With Keff < 1.0 SALEM - UNIT 1 3/4 1-1 Amendment No. 299

RtACTIVlTY CONTOL SSTEMS 3/4.1.3 ML! CONTROL ASS!M!LIES GROUP HEIGHT LIMITING CONDITION- FOR OPETlOH J.l.J.l All full lenqth (shutdown and control) rod, sh&ll be OPtLt and positioned Within% 18 steps(indicated petition> when r*tor power iss B5 \,

RATED THERMAL fOW!, or : 12 1tep1 £indicated C3ition) when re*etor power i5

> 85i RATED THERMAL POWER, ot thei qroup step counter dem.nd poaition within one hou after rod motion APPLICABILITY: MODE! l* and 2*

ACTION:

    • With one or mo re full length roQI inop**ble aue to oeing immovable **
  • re3ule of exce11ive friction or mechanical interfer*nce or known to be untrippabl*, deten* that the SHUTDOWN GIH requiremant of specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STDBr within 6 hour**
b. With More than one full length rod inoperable or mi***li;n*d froM the qroup etep counter dem.nd po* ition by more th*n z 18 *t*p*<indicated position) at S 8 \ RATED THERMAL POWER o: % 12 *t*pe (indicated position) at > 15t RATED THERMAL P b* in HOT STANDBY within 6 hou**
e. With one full 1en9th od inoperable due to cause* other th*n *ddresed by ACTION a, above, or mit*aligned from it* ;oup *tep ccunte demand po
  • ition by mote th*n z 18 atepa(1nd1c*ted po1ition) at 85 I TED THE POWER or t 12 *t*p* (inc.ted poaition) at > est RATED TH POWER, rowza OPEION may continue provid*d that within one hcur eith*t:
1. Te ed 1* **to*d ee GP!RAILI ataeu* wiftift the ** al1tnm*at e*&'**a*** ** D eleted I
2. Tbe der of th* rods 1n the bank with the inope:&ble rod ere ali,_..
  • within z 18 *t*P*(indicated poaition) at S 85 I TEO IOIIfl1t o.r :I: 12 atep* (inclited poa1t1oa) at > 1St MT!t) tHIAHAL rowER o the inope&bl* rod whil* maiAca1n1ft9 the rod aequeace aftd insertion lt* in th* COLA pe apecification 3.1.3.5. The TH POWER level ahall be re*tricted pu*uant to Specification 3.1.3.5 during *Ub**ent operation, o
l. The rod i* decl*ed inoperable and tb* SHUTDOWN MARGIN require.ent of spec1f1cat1on 3.1.1.1 i* **tilfied. POWER OPZloM m.y then eont1n* provided tb*t:

SALEM

  • UNIT l 3/' 1-11 Revfsed by letter dtd [lhnlllry 19. 1998

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) a) A reevaluation of each accident analysis of table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions.

b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l afud I N

c) A core power distribution measurement is obtained and Fa(Z) F AH are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

d) The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to less than or equal to 85%

of RATED THERMAL POWER. THERMAL POWER shall be maintained l es s than or equal to 75% of RATED THERMAL POWER until compliance with ACTIONS 3.1. 3.1.c.3.a and 3.1.3 .1.c.3.c above are demonstrated.

SURVEILLANCE REQUIREMENTS

\1 4.1.3.1.1 The position of each full length rod shall be determined to be within the limits established in the l imiting condition for operation in accordance with the Surveillance Frequency Control Prog ram (al lowing for one hour thermal soak after rod motion) except during time interval s when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4. 1. 3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction in accordance with the Surveillance Frequency Control Program.
  • Not required to be performed for rods associated with inoperable rod position indicator or demand position indicator.

SALEM - UNIT 1 3/4 1-18a Amendment No. 299

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS - OPERATING L IMITING CONDITION FOR OPERATION 3.1.3.2.1 The shutdown and control rod position indication stems shall be OPERABLE and capable of determining the actual and demanded rod positions as follows:

a. Analog rod position indicatorS; within one hour after rod motion (allowance for thermal All Shutdown Banks: +/- 18 steps at s 85% reactor power or if reactor power is > 85o/o RATED THERMAL POWER +/- 12 steps of the group demand counters for withdrawal ranges of 0-30 steps and 200-230 steps.

Control Bank A: +/- 18 steps at s 85% reactor power or if reactor power is > 85°/o RATED THERMAL POWER +/- 12 steps of the group demand counters for withdrawal ranges of 0-30 steps and 200-230 steps.

Control Bank B: +/- 18 steps at s 85°/o reactor power or if reactor power is > 85%

RATED THERMAL POWER +/- 12 steps of the group demand counters for withdrawal ranges of 0-30 steps and 160-230 steps.

Control Bank C and D: +/- 18 steps at s 85% reactor power or if reactor power is > 85°/o RATED THERMAL POWER +/- 12 steps of the group demand counters for withdrawal rrnsert#6l ! anges of 0-230 steps.

roup demand counters; +/- 2 steps of the pulsed output of the Slave Cycler Circuit over the withdrawal range of 0-230 steps.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. With a maximum of one analog rod position indicator per group inoperable either:
1. Determine the position of the non-indicating rod(s) indirectly using the power distribution monitoring system (if power is above 25% RTP) or using the movable incore detectors (if power is less than 25% RTP or the power distribution monitoring system is inoperable) at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or l1nsert#7 Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SALEM - UNIT 1 3/4 1-19 Amendment No. 324

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

b. With two or more analog rod position indicators per group inoperable:
1. Immediately place the control rods in manual control, and
2. Monitor and record Reactor Coolant System Tavg once every hour, and I Deleted
3. Verify the position of the rods with inoperable position indicators indirectly using the power distribution monitoring system (if power is above 25% RTP) or using the movable incore detectors (if power is less than 25% RTP or the power distribution monitoring system is inoperable) at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and
4. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restore the inoperable rod position indicators to OPERABLE status such that a maximum of one rod position indicator per group is inoperable, or
5. Be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c. When one or more rods with inoperable position indicators have been moved in excess of 24 steps in one direction since the last determination of the rod's position:
1. Determine the position of the non-indicating rod(s) indirectly using the power distribution monitoring system (if power is above 25% RTP) or using the movable incore detectors (if power is less than 25% RTP or the power distribution monitoring system is inoperable) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or
2. Reduce THERMAL POWER to less than 50%, of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
d. With a maximum of one group demand position indicator per bank inoperable either:
1. Verify that all analog rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 18 steps when reactor power is s 85o/o RATED THERMAL POWER or if reactor power is > 85% RATED THERMAL POWER, 12 steps of each other at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or
2. Reduce THERMAL POWER to less than 50% of RATED POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE REQUIREMENTS EJ 4.1.3.2.1.1 Each analog rod position indicator all be determined to be OPERABLE by verifying that the demand position indication system and the rod position indication system agree within 18 steps when reactor power is s 85% RATED THERMAL POWER or if reactor power is > 85%

RATED THERMAL POWER, 12 steps (allowing for one hour thermal soak after rod motion) in accordance with the Surveillance Frequency Control Program except during time intervals when the Rod Position Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indication system at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.1.3.2.1.2 Each of the above required rod position indicator(s) shall be determined to be OPERABLE by performance of a CHANNEL calibration in accordance with the Surveillance

--:-:-Frequency Control Program.

l1nsert #8 1 SAlEM - UNIT 1 3/4 1-19a Amendment No. 324

R E ACTIVITY CONTROL SYSTEMS SHUTDOWN ROD INSERTION LIMIT N E L-=;

p nsert #21

IIt::o;::IPbe:- WITHDRAWN.

APPLICABILITY: MOD E S 1*, and 2*#@

ACTION:

/ for reasons other than Action 1 With a maximum of one shutdown rod not FULLY WITHDRAWN, except for surv*eillance testing pursuant to Specification 4 1 3 1 2 within one hour either:

a. FULLY WITHDRAW the rod, or,
b. Declare the rod to be inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQUIREMENTS 4.1.3.4 Each shutdown rod shall be determined to be FULLY WITHDRAWN by use of the group demand counters, and verified by the analog rod position indicators**:

a. Within 15 minutes prior to withdrawal of any rods in control banks A, B, C, or D during an approach to reactor criticality, and
b. In accordance with the Surveillance Frequency Control Program thereafter.

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after associated rod motion.

  • See Special Test Exceptions 3.1 0.2 and 3.1 0.3
    • For pov:er le\'els below 50% one hour thermal"soak time" is permitted. During this soal<

time, the absolute value of rod motion is limited to six steps.

  1. With Keff greater than or equal to 1.0

@ Surveillance 4.1.3.4.a is applicable prior to withdrawing control banks in preparation for startup (Mode 2).

SALEM - UNIT 1 3/4 1-22 Amendment No. 299

REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION

.1.3.5 The control banks shall be limited in physical insertion as specified in the CORE PERATING LIMITS REPORT (COLR).

APPLICABILITY: MODES 1\ and 2*# for reasons other than j lnsert #4 j ACTION:

Action 1 With the control banks inserted beyond the above insertion limits, /(xeept for surveillance testing pursuant to Specification 4 .1.3.1.2, either:

a. Restore the control banks t o within the limits within two hours, or
b. Reduce THERMAL POWER within two hours to less than or equal to that fraction of RATED T HERMAL POWER which is allowed by the bank position using the insertion limits s pecified in the COLR, or
c. Be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.3.5 The position of each control bank shall be determined to be within the insertion limits in accordance with the Surveillance Frequency Control Program by use of the group demand counters and verified by the analog rod position indicators ..... except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least once per 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s-.

See Special Test Exceptions 3.10.2 and 3.10.3 For povter levels below 5Qq one hour thermal "soak time" is p e rmitted . During this seal<

time, the absolute value of rod motion is limited to six steps.

  1. With Kert greater than or equal to 1.0 SALEM - U NIT 1 3/4 1-23 Amendment No. 299

3/4.1 REACTIVITY CONTROL SYSTEMS FOR INFORMATION ONLY- NO CHANGES 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - T2YQ > 200oF LIMITING CONDIT ION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.3%> delta k/k.

APPLICABILITY: MODES 1, 2*, 3, and 4.

ACTION:

With the SHUTDOWN MARGIN less than 1 . 3% delta k/k, immediately initiate and continue boration at 33 gpm of a solution containing 6,560 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal to 1.3%>

delta k/k:

a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod(s) is inoperable. If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod(s).
b. When in MODE 1 or MODE 2 with Kett greater than or equal to 1.0, in accordance with the Surveillance Frequency Control Program by verifying that control banks are within the limits in the COLR per Specification 3.1.3.5.
c. When in MODE 2 with Kett less than 1.0, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior t o achieving reactor criticality by verifying that the predicted critical control rod position is within the limits in the COLR per Specification 3.1.3.5.
  • See Special Test Exception 3.10.1 SALEM - UNIT 2 3/4 1-1 Amendment No. 282

3 .1. 3.1 All full length (ahut.dc"tm and CODt.tol) rod.8, aball be 0 and poaitioned td.t:hitl 11 atapa (indicated poaitioo) when nactor power .ia s as*

M.1'ZD 1'HINAL IOMEJt , or 12 atapa (indicat41Cl poaitioD) whea reactor powu ia

> 15' MUD >>CM&Jt , o group

  • counter ct-*nd poaitiou Wit:Ai.n ou bou t.z rod aot.icm.
a. Wl.t:.h. one or aor* ul.l lavth zcxb i.Doperuue due to.

u a r*ault. o exceaaive ,frictJ.cm or ..ch&DJ.cal t.e%'f:ereAae or moVIl to be \lDb:ippable,

  • that 'the IHU1'JXIWW MNU:DI requira.ut o,t Specttj.cat::i.oa 3 1 1 1 i.a aat:iatiecl witbJ.J) 1 hOU' d in HOT say within 6 ba .

. b. Wi t.h aore thaD one ull len rocl inop4trable or ai.a*a.ligned ,froa the group atep counter d.tla&nd. poaition by aore than t 18 a tepa

(.indicated poai'b.orl) at s as* 'l'HIJQAl. POWEJt or t 12 atepa (indicated poait.ion) at > 85t JtA't'll) ':HZRKJU. POWEJt , be iD HOT SY vi thin 6 bow: * .

c. With one ul.l lan;tb rod inoperable clue 1:0 cauaea otbu tban ac:lclreaaed by ACTION a, above , or a:i.a-allped ,troa ita Q:Ol:SP atep countar d.em*nd poaition tJy ac:e than .t 11 atepa (l.ncti.c:atec:l poait.ion) at s t!t MTI:D JOMIJt or :t 12 ** (indicated poait.ion) -at

> 8!5' RAftl) TK&JQIA.L PONUt, IOM&Jt. Oftu.!!ION aay CODt:.:i.Aue provided th.a t vi t:hi.D oa.e hour 4U..tAU:

1. '1'1\a eoel ia nat.oll'Ml OP&Jl*mz *=- withi = U.V.

&lp*a=t e*uu, ** D eleted I

2. !be ZIIPiDMZ' 0 J'OCU in bact nth the iftope:able rod.

an aliped to vi t:.h.iD :t 11 *tep* (iDCI:i.ca poait.ion) at s as' MDD fJIZJUGU, ftlW.IJl oz % 12 * (1rld.:Lcated poai t.iDD) at >15t MftD '!'HZJUCAl. POUlt, o the illc:JPU'abl* rod wb::Ll.e aaiDt.a.1Di.Q9 tbe rod *eqHDae &D4 i.UeJ:t.i.= Ua:i. u ill COl.lt per ap.cu.t.cat.101l 3 .1 . 3 .1. "fbe JICMD level ..UU. ..bl J reatrictecl pazll'Q&D to lpeeitioat.ioa. 3 .1 .. 3. 5 dm:.i.rag aul)a.cruen t openb.OD, .z

3. '!he Rd i* decluwd itloparable aDd the IHQ'ItJXIidi lCUGllt requi.r.-.nt o Specif'.icati011 3.1.1.1 :La aaU*fi-.cl.

onJtAT%011 ..l' than continue providad t:bat:

  • s.. Sptcial hat J:acept.iou. 3.10 .2 &Del 3.10 .l.

3/4 1-13

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) a) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previousl y analyzed results of these accidents remain valid for the duration of operation under these conditions.

b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c) A core power distribution measurement is obtained and Fa(Z) and N

F t>H are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

d) The THERMAL POWER level is reduced to less than or equa l to 75°/o of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER. THERMAL POWER shall be maintained less than or equal to 75% of RATED THERMAL POWER until compliance with ACTIONS 3.1. 3.1.c.3.a and 3.1. 3.1.c.3.c above are demonstrated.

SURVEILLACE REQUIREMENTS 9 4.1.3.1.1 The position of each ful l length rod etermined to be within the limits established in the limiting condition for operation in accordance with the Surveillance Frequency Control Program (al lowing for one hour thermal soak after rod motion) except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.1.3.1.2 Each ful l length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction in accordance with the Surveil lance Frequency Control Program.

  • Not required to be performed for rods associated with inoperable rod position indicator or demand position indicator.

SALEM - UNIT 2 3/4 1-14 Amendment No. 282

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2.1 The shutdown and control rod position indication systems shall be OPERABLE and capable of determining the actual and demanded rod positions as follows:

a. Analog rod position indicators, 'Nithin one hour after rod motion (allowance for thermal seakj; All Shutdown Banks: +/- 18steps at s 85% reactor power or if reactor power is > 85°/o RATED THERMAL POWER +/- 12 steps of the group demand counters for withdrawal ranges of 0-30 steps and 200-230 steps.

Control Bank A: +/- 18 steps at s 85% reactor power or if reactor power is > 85% RATED THERMAL POWER+/- 12 steps of the group demand counters for withdrawal ranges of 0-30 steps and 200-230 steps.

Control Bank 8: +/- 18steps at s 85% reactor power or if reactor power is > 85% RATED THERMAL POWER +/- 12 steps of the group demand counters for withdrawal ranges of 0-30 steps and 160-230 steps.

Control Banks C and D: +/- 18steps at s 85% reactor power or if reactor power is > 85%

RATED THERMAL POWER+/- 12 steps of the group demand counters for withdrawal ange of 0-230 steps.

b. Group demand counters; +/- 2 steps of the pulsed output of the Slave Cycler CircUit over the withdrawal range of 0-230 steps.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. With a maximum of one analog rod position indicator per group inoperable either:
1. Determine the position of the non-indicating rod(s) indirectly using the power distribution monitoring system (if power is above 25% RTP) or using the movable incore detectors (if power is less than 25% RTP or the power distribution monitoring system is inoperable) at least once per 8hours, or

. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8hours.

rtJ SALEM - UNIT 2 3/4 1-16 Amendment No. 305

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

b. With two or more analog rod position indicators per group inoperable:
1. Immediately place the control rods in manual control, and IDe:td I
2. Monitor and record Reactor Coolant System Tavg once every hour, and
3. Verify the position of the rods with inoperable position indicators indirectly using the power distribution monitoring system (if power is above 25°/o RTP) or using the movable incore detectors (if power is less than 25%> RTP or the power distribution monitoring system is inoperable) at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and
4. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restore the inoperable rod position indicators to OPERABLE status such that a maximum of one rod position indicator per group is inoperable, or
5. Be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c. When one or more rods with inoperable position indicators have been moved in excess of 24 steps in one direction since the last determination of the rod's position:
1. Determine the position of the non-indicating rod(s) indirectly using the power distribution monitoring system (if power is above 25% RTP) or using the movable incore detectors (if power is less than 25o/o RTP or the power distribution monitoring system is inoperable) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or
2. Reduce THERMAL POWER to less than 50°/o of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
d. With a maximum of one _group demand position indicator per bank inoperable either:
1. Verify that all analog rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 18 steps when reactor power iss; 85°/o RATED THERMAL POWER or if reactor power is > 85°/o RATED THERMAL POWER, 12 steps of each other at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or 4.1.3.2.1.2 Each of the above required rod position indicator(s) shall be determined to be OPERABLE by performance of a CHANNEL calibration in accordance with the Surveillance Frequency Control Program.

jlnsert #B rs ALEM - UNIT 2 3/4 1-16a Amendment No. 305

REACTIVITY CONTROL SYSTEMS S H UTDOWN ROD INSERTION LIM I T LIM I T I NG CON D ITION FOR OPERATION ll nse7 # 1 I 3 . 1 . 3 . 4 Al l shutdown rods s hal l be FULLY WITHDRAWN.

APPLI CAB I LITY: MODES 1 *, and 2*#@.

s o-th_e_r_____,

..-fo_r_r_e_a_s_o-n-than Action 1 p nsert #2 btCTION :

With a maximum of one shutdown rod not F U LLY WITH D RAWN, except fo r surveillance testing pursuant to S pe cificatio n 4 . 1 .3 . 1 . 2 , withi n one hour eit her:

l.:..:_f

a. FU L LY WITH D RAW the rod , or,
b. Declare the rod to be i noperable and apply Specification 3. 1 . 3 . 1 .

S U RVE I L LANCE REQU I RE M E NTS

4. 1 . 3 . 4 Each s hutdown rod sha l l be determined to be FULLY WITH DRAWN by use of the group demand counters, an d verified by the a n a log rod position indicators** :
a. Within 1 5 mi nutes prior to withdrawal of a ny rod s i n control banks A, B , C, a nd D during an a p proach to reactor criti cally , and
b. In accordan ce with the Survei llance Frequency Control Program thereafter.

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after associated rod motion.

  • See S pecial Test Exceptions 3 . 1 0 . 2 and 3. 1 0 . 3 .
    • For po'Ner levels belo*..v 50% one hour thermal "soak time is permitted. During this seal time, the absolute value of rod motion is limited to six steps.

@ Surveil l a nce 4 . 1 . 3 . 4 . a is a pplicable prior to withdrawing a n y control banks in preparation for startup (Mode 2).

  1. With Keff greater than or equ a l to 1 . 0 .

Note: Th is pag e effective prior to start u p from fifth refueling outage scheduled to begin M a rch 1 9 90. Letter dated J an. 1 1 , 1 990.

SALEM - U N IT 2 3/4 1 - 1 9 Amendment No. 282

R EACTIVITY CONTROL SYST EMS CO NTROL RO D I N S E RT I O N L I M ITS LI M I T I N G CON DITION FO R O P E RATI O N

3. 1 . 3 . 5 The control banks sha l l be l i m ited i n phys i ca l i nsertion as s pecified i n the CORE

- O P E RAT I NG L I M I TS RE PORT (COLR) .

jl nsert #3 for reasons other AP P L I CA B I L I TY: MODES 1 * , a n d 2*#

than Action 1 TI O N :

r::::--- ;71 With the control ban ks i n se rted beyo nd t h e above i n s e rtion l i m its , except for surveillance testing pursuant to Speeifieation 4. 1 .3. 1 . 2 , eith e r:

a. Restore t h e contro l banks t o wit h i n the l i m its with i n two h o u rs , or
b. Red uce T H E RMAL POWE R wit h i n two h o u rs to l ess than o r e q u a l to t h at fraction of RATED T H E RMAL POWE R which i s all owed by t h e ban k position using t h e i nsertion l i m its s pecified in the C L O R, o r
c. B e i n a t l east H O T STAN DBY wit h i n 6 h o u rs.

SURVE I LLANCE R EQ U I RE M E NTS

4. 1 . 3 . 5 The positio n of each co ntro l bank s h a l l be determ i n ed to be wit h i n the insertion l i m its i n accordance with t h e Surve i l l an ce Freq uency Contro l P rog ram b y u s e of t h e g ro u p d e m and counters and verified by t h e a n alog rod position indicato rs** exce pt d u ring time i nterva ls when the Rod 1 nsertion Li m it Mon ito r i s i noperable , then verify the individ u a l rod positions at least o n ce per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> .....
  • See S peci a l Test Exceptio n s 3 . 1 0.2 and 3. 1 0 . 3 Fo r povv'C r levels belo'N 50% one hour thermal soalx time" is permitted . During this soak time, the absolute value of rod motion is limited to six steps.
  1. With Keff g reater tha n or eq u a l to 1 . 0 SA LE M - U N IT 2 3/4 1 -20 Amendment N o. 282
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