ML110690023
| ML110690023 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/03/2011 |
| From: | Sawatzke B Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GO2-11047 | |
| Download: ML110690023 (53) | |
Text
{{#Wiki_filter:Bradley J. Sawatzke ENERGYP.O. NORT WESTRichland, Columbia Generating Station WA Box99352-0968 968, PE08 NORTHW EST Ph. 509.377.4300 F. 509.377.4150 bjsawatzke @energy-northwest.com March 3, 2011 G02-11-047 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS
Dear Sir or Madam:
Pursuant to 10 CFR 50.90, Energy Northwest hereby requests changes to Facility Operating License NPF-21 for the Columbia Generating Station (Columbia). The proposed administrative changes either delete or modify existing license conditions which have been completed or are otherwise no longer in effect. Energy Northwest has evaluated the proposed changes and has determined that a finding of "no significant hazards consideration" is justified based on the considerations herein: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation with the proposed changes to the Operating License and (2) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. The enclosure to this letter provides the basis for the each proposed license change and contains the following attachments:
" Attachment 1 provides the Operating License pages marked up to show the proposed changes. " Attachment 2 provides the proposed Operating License changes in the final typed format.
Approval of the proposed changes to the Operating License is requested within one year from the date of this submittal to support the Columbia license renewal effort. Once approved, the amendment will be implemented within 30 days. This letter and its enclosure contain no regulatory commitments. 1-2,
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Page 2 In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated Washington State Official. If you should have any questions regarding this submittal, please contact Mr. K. D. Christianson, Licensing Supervisor, at (509) 377-4315. I declare under penalty of perjury that the foregoing is true and correct. Executed on the date of this letter. Respectfully, B. J. Sawatzke Vice President, Nuclear Generation & Chief Nuclear Officer
Enclosure:
Evaluation of Proposed Changes Attachments to the
Enclosure:
- 1. Proposed Operating License Changes (mark-up)
- 2. Proposed Operating License Changes (retyped) cc: NRC Regional IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector/988C RN Sherman - BPA/1 399 WA Horin - Winston & Strawn JO Luce - EFSEC RR Cowley - WDOH AD Cunanan - NRC NRR
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 1 of 21 Evaluation of Proposed Change
Subject:
License Amendment Request to Delete Obsolete License Conditions 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedents 4.3 Significant Hazards Consideration 4.4 Conclusion
5.0 ENVIRONMENTAL CONSIDERATION
6.0 REFERENCES
ATTACHMENTS:
- 1. Proposed Operating License Changes (mark-up)
- 2. Proposed Operating License Changes (retyped)
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 2 of 21 1.0
SUMMARY
DESCRIPTION This evaluation supports an NRC request to amend Operating License NPF-21 in support of the License Renewal Application for Columbia Generating Station (Columbia). The proposed changes are administrative in nature and either delete or modify existing license conditions that have been completed or are otherwise no longer in effect. Approval of the proposed changes to the Operating License is requested within one year from the date of this submittal to support the Columbia license renewal effort. 2.0 DETAILED DESCRIPTION Operating License NPF-21 was issued on December 20, 1983, to Washington Public Power Supply System (WPPSS) for the WPPSS Nuclear Project No. 2. WPPSS subsequently changed its name to Energy Northwest and changed the name of the plant to Columbia Generating Station. Many conditional requirements were placed on the Operating License for Columbia to address outstanding licensing issues and facilitate issuance of the original Operating License. Since the original issuance of the Columbia Operating License, several additional requirements (license conditions) have been incorporated into the license via the license amendment process pursuant to 10 CFR 50.90. In some cases, subsequent license amendments have removed certain license conditions when they were no longer applicable. However, the majority of the license conditions have been left intact even though they are no longer required. Energy Northwest is proposing an administrative change to the Columbia Operating License to remove those license conditions that no longer apply. This proposed Operating License "clean-up" activity also includes minor editorial changes for consistency. Revision of the Columbia Operating License is being proposed to retain only those license conditions that remain pertinent to current station operations. The intent is to provide a license document for license renewal that does not contain unnecessary or obsolete requirements and that is directly applicable to the current plant design and licensing basis.
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 3 of 21
3.0 TECHNICAL EVALUATION
Each proposed change to the Operating License is described below including the justification for the change. Proposed Change to Revise License Condition 2.C.(1) and Delete Attachment 1 License condition 2.C.(1) requires completion of items in Attachment 1 to the license. This attachment contains three types of items: 1) completion of preoperational/acceptance tests, 2) installation of hangers, supports, and restraints, and 3) construction completion (master completion list schedule). The reference to Attachment 1 in this license condition should be deleted along with the Attachment itself. Justification for Deletion: Item 1a requires completion of the System 36 preoperational testing prior to fuel load. System 36 (process radiation monitoring) testing was completed as required. Inspection Report 50-397-84-07 (Reference 1) discussed the completion of the required testing of System 36 prior to fuel load and identified this item as "Closed". Thus, this item has been satisfied and can be deleted. Item 1b requires completion of 16 preoperational/acceptance tests prior to exceeding 5% rated power. By letter dated April 12, 1984 (Reference 2), Energy Northwest confirmed that all but two of the tests listed in Attachment 1 item lb have been completed. The other two tests (PT 33.0-B and PT 92.0-A) were not required to be completed as described below. The Columbia Final Safety Analysis Report (FSAR) addresses the status of the two systems with incomplete testing. As such, Item lb can be deleted. PT 33.0-B: By letter dated January 17, 1984 (Reference 3), Energy Northwest reported that the portions of the chemical waste system to be tested by PT 33.0-B have been suspended indefinitely and requested that test PT 33.0-B be removed from the list of preoperational/acceptance tests. A portable skid system was provided by Chemical Nuclear System Inc. to process wet, solid radioactive waste. The system was described in FSAR Amendment No. 33 and was approved by the NRC staff as documented in Supplement 4 to NUREG-0892 (Reference 4). By letter dated April 13, 1984 (Reference 5), the NRC provided their agreement with Energy Northwest's position of indefinitely suspending test PT 33.0-B but stated that prior to placing the permanent system into operation, this test must be completed. As such, this requirement is contained in section 11.2.2 of the Columbia FSAR which states that the chemical waste subsystem has been installed but will not be used until plant operating experience indicates a need and system testing is accomplished.
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 4 of 21
- PT 92.0-A: By letter dated April 12, 1984 (Reference 2), Energy Northwest described the status of the testing of the system stating that the test had been completed utilizing one of two redundant chillers. Subsequently, the off-gas charcoal adsorber vault refrigeration system was permanently deactivated, which has been documented in section 9.4.5 of the Columbia FSAR.
Item 1c requires completion of PT 22.0-B, Nitrogen Inerting System, prior to six months after initial criticality. By letter dated July 18, 1984 (Reference 6), Energy Northwest confirmed completion of the required testing. Thus, this item has been satisfied and can be deleted. Item 2 requires completion of all hangers, supports, and restraints needing installation or modification prior to exceeding 5% rated power. By letter dated March 16, 1984 (Reference 7), Energy Northwest confirmed the completion of the required modifications. Inspection Report 50-397-84-04 (Reference 8) evaluated the installation of hangers, supports and restraints required prior to exceeding 5% rated power and identified no deviations or items of noncompliance. Thus, this license condition has been satisfied. Item 3 requires completion of items on the Master Completion List (MCL) schedule dated December 19, 1983. The MCL identifies the various individual work items which were necessary for plant completion. The various items were categorized and scheduled for completion as follows: prior to fuel load, prior to initial pressurization with steam generated by nuclear heat, prior to 5% rated power, prior to commercial operation, or prior to completion of first refueling. A condition was inserted into the Operating License to assure NRC review of any planned reclassification of these items. Such reviews were conducted prior to fuel load, plant pressurization, 5% rated power level, commercial operation (defined as July 1, 1984), and at the first refueling outage as documented in NRC Inspection Reports 50-397-83-60, 50-397-84-18 and 50-397-86-18 (References 9-11, respectively). The NRC concluded that the actions required by this license condition have been satisfactorily completed. Thus, this item can be deleted. Proposed Change to Delete License Condition 2.C.(3) This license condition specifies that the Initial Test Program, as described in Section 14 of the FSAR, is to be conducted without making any modifications of this program unless such modifications are in accordance with 10 CFR 50.59. Furthermore, no major modifications to the test program are to be made without prior NRC approval. Justification for Deletion: Startup testing of Columbia was completed in 1985. By letter dated April 17, 1985 (Reference 12), Energy Northwest submitted the final startup report. Inspection Reports 50-397-84-38 and 50-397-85-27 (References 13 and 14) documented the NRC review of the startup testing program. This license condition has been satisfied.
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 5 of 21 Proposed Change to Delete License Condition 2.C.(4) This license condition requires completion of seismic qualification for all equipment that was approved by the NRC staff for interim operation. This qualification was required to be completed prior to startup following the first refueling outage. Justification for Deletion: By letter dated June 3, 1986 (Reference 15), Energy Northwest confirmed that the seismic qualification of equipment required by this license condition is complete and this license condition has been satisfied. Proposed Change to Delete License Condition 2.C.(5) This license condition requires NRC review and approval of two items relating to equipment qualification: a) assurance that certain equipment is either environmentally qualified or justified for interim operation, and b) assurance that the "g" values for the as-installed configuration of pipe-mounted safety-related equipment do not exceed the "g" values established in the equipment qualification information documentation files or provide justification for continued operation. This qualification was required to be completed prior to exceeding 5% rated power. Justification for Deletion: By letter dated September 16, 1983 (Reference 16), Energy Northwest submitted the environmental qualification report for safety-related equipment. By letter dated January 18, 1984 (Reference 17), Energy Northwest confirmed that the requirements of license condition 2.C.(5)(a) are satisfied. By letter dated January 23, 1984 (Reference 18), Energy Northwest confirmed the completion of the pipeline mounted equipment "g" value comparison program and that all differences are reconciled either by qualification documentation upgrade, piping analysis refinement, or plans for physical plant modifications. By letter dated March 16, 1984 (Reference 7), Energy Northwest confirmed the completion of required modifications. In Supplement 5 to NUREG-0892 (Reference 19), the NRC stated that license conditions 2.C.(5)(a) and (b) are satisfied. Proposed Change to Delete License Condition 2.C.(6) This license condition requires testing of the ultimate heat sink (UHS) spray ponds and NRC review and approval of the test results and conclusions. This testing was required to be completed prior to startup following the first refueling outage. Justification for Deletion: By letter dated September 27, 1985 (Reference 20), Energy Northwest submitted the test results and conclusions to the NRC. By letter dated December 11, 1985 (Reference 21), the NRC provided their approval and stated that license condition 2.C.(6) is satisfied.
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 6 of 21 Proposed Change to Delete License Condition 2.C.(7) This license condition requires development of a turbine system maintenance program based on the manufacturer's calculations of missile generation probabilities or a recurring inspection of the low pressure turbine rotors. NRC review and approval of the program is required. This condition was required to be satisfied within three years of the date of issuance of the license. Justification for Deletion: By letter dated November 20, 1986 (Reference 22), Energy Northwest submitted the turbine system inspection schedule to the NRC, which was based upon the turbine manufacturer's (Westinghouse) criteria and topical report for estimating the probability of turbine disc rupture from stress corrosion cracking. It was noted that the inspection schedule and the time interval between inspections are subject to change depending on previous inspection results, existence or lack of flaws, equipment availability, and inspection refinements or techniques yet to be developed. By letter dated March 27, 1987 (Reference 23), the NRC stated that license condition 2.C.(7) is satisfied by 1) use of the Westinghouse methodology and procedures and 2) an existing commitment in FSAR section 3.5.1.3.4.3 in which Energy Northwest committed to reduce the inspection intervals for subsequent inspections if cracks are detected and measured at any inspection. In April 1992, the original Westinghouse shrunk-on-disc type low pressure (LP) rotors were removed and new Westinghouse Fully Integral LP rotors were installed. The current LP turbine missile analysis is based on Fully Integral rotors using the probabilistic method in WSTG-4NP. FSAR section 3.5.1.3.4.1 describes the current turbine inspection and testing intervals. Thus, this license condition has been satisfied. Proposed Change to Delete License Condition 2.C.(8) This license condition requires NRC review and approval of a revised analysis showing the effects of high burnup fission gas release on loss of coolant accidents (LOCA). This condition was required to be satisfied prior to startup following the first refueling outage. Justification for Deletion: By letters dated February 4, 1986 (Reference 24) and May 9, 1986 (Reference 25), Energy Northwest submitted information supporting closure of license condition 2.C.(8). By letter dated May 23, 1986 (Reference 26), the NRC concluded that license condition 2.C.(8) is satisfactorily resolved. Thus, this license condition has been satisfied. The current approved LOCA models for Columbia are documented in FSAR sections 4.2.1.3 and 4.2.3.3 and Technical Specification (TS) 5.6.3.b. Proposed Change to Delete License Condition 2.C.(9) This license condition requires implementation of NRC requirements regarding additional instrumentation for detection of inadequate core cooling. Any required modifications were to be completed on a schedule acceptable to the NRC.
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 7 of 21 Justification for Deletion: As discussed in NUREG-0892 (Reference 66) the instrument in question is for measurement of reactor vessel water level. By letter dated November 27, 1984 (Reference 27), Energy Northwest submitted information supporting closure of license condition 2.C.(9). No modifications were deemed necessary. Inspection Report 50-397-84-38 (Reference 13) evaluated Energy Northwest's response to NUREG-0737 Item II.F.2 regarding inadequate core cooling and reactor vessel level instrumentation and identified this item as "Closed." Thus, this license condition has been satisfied. The instrumentation to measure reactor vessel water level is described in FSAR sections 7.2.1.1.3, 7.3.1.1.2.1, 7.5.1.1.1, and 7.7.1.1.2.2 Proposed Change to Delete License Condition 2.C.(10) This license condition requires NRC review and approval of a revised stability analysis. This condition was required to be satisfied prior to startup following the first refueling outage. Justification for Deletion: By letter dated January 27, 1986 (Reference 28), Energy Northwest submitted information supporting closure of license condition 2.C.(10) based upon NRC approval of Amendment 16. The TS changes authorized by this amendment satisfied the intent of the license condition. By letter dated March 21, 1986 (Reference 29), the NRC provided their concurrence. Thus, this license condition has been satisfied. The current approved stability analysis for Columbia is documented in FSAR sections 4.1.4.3 and 4.4.4.2 and TS 5.6.3.b. License Condition 2.C.(11) and Proposed Changes to Portions of Attachment 3 Attachment 3 is referenced by license condition 2.C.(1 1) which requires completion of the construction of shield walls and a shield window. This attachment describes where the walls are to be located and when they are required to be installed. No changes are proposed to the actual license condition 2.C.(1 1). Portions of Attachment 3 are proposed to be deleted. Justification for Change: Items 1 through 4 have been installed. Therefore, the first four items and the Note (*) are proposed for deletion. The installation of remaining items is conditional upon local area radiation levels and no change is requested for these items. (Note that references 67 and 68 provide the basis for deferral of installation of these shield walls. Those walls not yet installed are associated with the permanent radwaste solidification system, which is not utilized as documented in FSAR Figures 11.2-4 and 11.4-1. Also, FSAR section 11.4.2 describes the portable solid waste management system which is used in lieu of the permanent solidification system.) The FSAR figure numbers are proposed to be corrected to align with the current FSAR.
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 8 of 21 Proposed Change to Delete License Condition 2.C.(12) This license condition requires installation of an alternate remote shutdown system. The installation was required to be completed prior to startup following the first refueling outage. Justification for Deletion: By letters dated June 2, 1986 (Reference 30) and August 6, 1986 (Reference 31), Energy Northwest confirmed completion of the installation of the alternate remote shutdown system and provided a description of the as-installed system. Inspection Report 50-397-86-18 (Reference 32) documented the NRC observation of installation of the alternate remote shutdown system. This license condition has been satisfied. The alternate remote shutdown system is described in FSAR section 7.4.1.4. TS 3.3.3.2 and Licensee Controlled Specification (LCS) 1.3.3.3 address the remote shutdown system, which includes the alternate remote shutdown system as documented in the TSBases and LCS Bases. Proposed Change to Delete License Condition 2.C.(15) This license condition requires that during the startup test program each shift have a licensed individual or advisor with previous startup or operating experience on a comparable boiling water reactor (BWR). Justification for Deletion: By letter dated November 11, 1983 (Reference 33), Energy Northwest submitted the resumes of individuals with previous startup or licensed operating experience. In Supplement 4 to NUREG-0892 (Reference 4), the NRC noted that this condition was considered closed. By letter dated October 16, 1984 (Reference 34), Energy Northwest subsequently updated the list of individuals to be utilized to meet this requirement. Startup testing of Columbia was completed in 1985. Proposed Change to Delete License Condition 2.C.(16) and Attachment 2 This license condition requires correction of control room design deficiencies and completion of emergency response capabilities as required by Attachment 2 to the license. Justification for Deletion: All items in Attachment 2 have been completed as discussed below. In Supplement 5 to NUREG-0892 (Reference 19), the NRC stated that license conditions 2.C.(16) is satisfied. Item 1 requires submittal of a program plan for a detailed control room design review (DCRDR) within 2 months after issuance of the Operating License and a summary report not later than 6 months prior to the first refueling outage. By letter dated February 17, 1984 (Reference 35), EnergyNorthwest submitted the program plan for the DCRDR. By letter dated November 1, 1985 (Reference 36), Energy Northwest submitted the DCRDR Summary Report. By letter dated July 9, 1990 (Reference 37), the NRC issued a Safety
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 9 of 21 Evaluation Report documenting the review of the DCRDR Summary Report. By letter dated November 13, 1991 (Reference 37a), the NRC stated that the status of the DCRDR is considered closed. FSAR 7.5.1.22 references the DCRDR analysis which is discussed in FSAR Appendix B Item I.D.1.
- Item 2 identifies 13 human engineering deficiencies which must be corrected and implemented to the NRC's satisfaction prior to exceeding 5% rated power. By letter dated March 19, 1984 (Reference 38), Energy Northwest confirmed that these human engineering deficiencies have been corrected.
Item 2 also identifies an additional 7 human engineering deficiencies which must be corrected and implemented to the NRC's satisfaction within 4 months after the issuance of the Operating License. By letter dated April 17, 1984 (Reference 39), Energy Northwest confirmed that these human engineering deficiencies have been corrected. Inspection Report 50-397-84-23 (Reference 40) evaluated Energy Northwest's response to TMI Action 1.D.1 regarding control room design reviews and states that the 20 human engineering deficiencies have been addressed. This item was identified as "Closed".
- Item 3(a) requires implementation of Regulatory Guide (RG) 1.97 Revision 2 requirements (with the exception of the wide range suppression pool level monitoring system) prior to startup following the first refueling outage. By letter dated June 4, 1986 (Reference 41), Energy Northwest confirmed the installation or upgrade of all identified equipment required to meet the recommendations of RG 1.97 Rev. 2, with the exception of the wide range suppression pool level monitoring system. FSAR sections 7.5.1.1 and 7.5.2.1 describe Columbia's compliance with RG 1.97 Rev. 2. Table 7.5-1 lists variables monitored, which have been selected using the methodology established in RG 1.97, NUREG-0737 and the Emergency Procedure Guidelines (EPG).
- Item 3(c) requires implementation of a wide range suppression pool level monitoring system prior to startup following the second refueling outage. By letter dated June 15, 1987 (Reference 42), Energy Northwest confirmed the installation of this equipment. The wide range suppression pool water level instrumentation is described in FSAR section 7.5.1.5.7.
- Item 4 requires submittal of an addendum to the Procedures Generation Package describing the function and task analysis as identified in Supplement 1 to NUREG-0737 within 3 months after issuance of the license. By letter dated February 17, 1984 (Reference 35), Energy Northwest submitted the addendum to the Procedures Generation Package. FSAR 7.5.1.22.1 discusses the interrelationship between the control room instrumentation and the EPG.
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 10 of 21 Item 5 requires fully functional emergency response facilities prior to exceeding 5% rated power. By letter dated March 22, 1984 (Reference 43), Energy Northwest notified the NRC that the required emergency response facilities were functional. The emergency response facilities are described in the Emergency Plan. Proposed Change to Delete License Condition 2.C.(17) This license condition prohibits operation with partial feedwater heating for the purpose of extending the normal fuel cycle unless justification' is provided to and approved by the NRC staff. Justification for Deletion: By letter dated March 1, 1990 (Reference 44), the NRC issued Amendment 77 approving operation with reduced feedwater heating for the purpose of cycle extension. The issuance of this amendment by the NRC satisfies license condition 2.C.(17). LCS 1.1.6 currently governs operation with feedwater temperature reduction for the purpose of cycle extension. Proposed Change to Delete License Condition 2.C.(18) This license condition requires installation of modifications to the automatic depressurization system (ADS) which are acceptable to the NRC and incorporation of the use of the inhibit switch into emergency procedures. This condition was required to be satisfied prior to startup following the first refueling outage. Justification for Deletion: By letter dated July 26, 1983 (Reference 45), Energy Northwest submitted the proposed modification of the ADS to the NRC. EN committed to modify the ADS logic to bypass the high drywell pressure trip portion of the existing ADS logic and add a manually operated inhibit switch. In Supplement 4 to NUREG-0892 (Reference 4), the NRC noted the acceptability of the proposed modification. By letter dated January 29, 1988 (Reference 46), Energy Northwest stated that the ADS inhibit switches were installed in 1985 and the appropriate emergency procedures were revised. Inspection Report 50-397-88-45 (Reference 47) confirmed that the necessary procedures were revised as required. Thus, this license condition has been satisfied. The ADS logic is described in FSAR section 7.3.1.2.1, Table 7.3-2 and Figure 7.3-5. The ADS inhibit is described in FSAR section 7.3.1.1.1.2. Proposed Change to Delete License Condition 2.C.(19) This license condition requires installation of the controls and monitoring instrumentation for the high pressure core spray (HPCS) diesel engine in a freestanding floor mounted panel separate from the engine skid with a location in a vibration-free floor area or qualification of the instrumentation for vibration that will occur during engine operation. This condition was required to be satisfied prior to startup following the first refueling outage.
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 11 of 21 Justification for Deletion: By letter dated June 3, 1986 (Reference 48), Energy Northwest described the modification that was completed along with the qualification of the controls and instrumentation for vibration levels that occur during engine operation and stated that license condition 2.C.(19) is satisfied. FSAR 8.3.1.1.7.2.10 discusses the qualification of HPCS diesel generator control and monitoring instruments located on the diesel generator skid. Proposed Change to Delete License Condition 2.C.(20) This license condition requires installation of air dryers in the diesel engine air starting system. This installation was required to be completed prior to startup following the first refueling outage. Justification for Deletion: By letter dated June 3, 1986 (Reference 49), Energy Northwest confirmed completion of the installation of the air dryers. Inspection Report 50-397-86-11 (Reference 50) documented the NRC review of the design change package for addition of diesel starting air system air dryers. This license condition has been satisfied. The diesel starting air system air dryers are described in FSAR section 9.5.6.2. Proposed Change to Delete License Condition 2.C.(21) This license condition requires redundant, seismic Category I environmentally qualified chillers for control room HVAC be operable. This condition was required to be satisfied prior to May 31, 1984. Justification for Deletion: By letter dated May 31, 1984 (Reference 51), Energy Northwest confirmed that this license condition has been satisfied. Inspection Report 50-397-90-05 (Reference 52) documented that the chillers had been installed as required. This license condition has been satisfied. The control room chillers are described in FSAR sections 9.4.1.2.1 and 9.4.1.3.1. Proposed Change to Delete License Condition 2.C.(22) This license condition requires NRC review and approval of analysis or modifications needed to address the following items related to control system failures: (a) capability to attain a safe shutdown condition following the loss of any Class 1E instrument bus, (b) the impact of control system failures resulting from high energy line breaks (HELB) on the transient and accident analysis, and (c) the impact of control system failures due to the failure of common power sources, sensors, or instrument sensing lines on the transient analysis. This condition was required to be satisfied prior to startup following the first refueling outage. Justification for Deletion: By letters dated June 24, 1983 (Reference 69) and November 10, 1983 (Reference 70), Energy Northwest submitted the required reports. For item (a) the analysis concluded there were no situations where a single bus power failure would prevent plant personnel from achieving a reactor
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 12 of 21 cold shutdown condition. For item (b) the analysis concluded that the consequences of the worst case combination of control system failures due to a HELB were a small fraction of 10 CFR 100 guidelines. For item (c) the analysis concluded there were no new transient category events postulated as a result of common sensor failures. By letter dated January 6, 1986 (Reference 53), the NRC documented that the required items have been resolved, the resolution is acceptable and this license condition is satisfied. Proposed Chanae to Delete License Condition 2.C.(23) This license condition requires NRC review and approval of the results of the reconciliation of the hydrodynamic loads for all the safety-related piping, equipment and their supports. This qualification was required to be completed prior to exceeding 5% rated power. Justification for Deletion: By letters dated March 28, 1983 (Reference 54), June 16, 1983 (Reference 55), and January 24, 1984 (Reference 56), Energy Northwest provided the results of the reconciliation of the hydrodynamic loads for all affected safety-related piping components and equipment and their supports. In Supplement 5 to NUREG-0892 (Reference 19), the NRC stated that based upon the information submitted this license condition is satisfied. FSAR Appendix 3A contains the Plant Design Assessment Report (DAR) which describes the Columbia load definition, load application, load combination, and design margins for hydrodynamic loading conditions. The DAR specifies the Columbia position for each of the pool dynamic loads. The Columbia positions were discussed, reviewed and approved by the NRC. Proposed Change to Delete License Condition 2.C.(24) This license condition requires emergency response duty training be provided to the remaining members of the emergency organization staff who were not included in previous training. This training was required to be completed prior to exceeding 5% rated power. Justification for Deletion: By letter dated March 19, 1984 (Reference 57), Energy Northwest confirmed the completion of the required training. In Supplement 5 to NUREG-0892 (Reference 19), the NRC stated that based upon the information submitted this license condition is satisfied. Proposed Change to Delete License Condition 2.C.(25) This license condition requires certification to the NRC that the distribution of tone alert radios and public information brochures has been completed. This distribution was to be completed prior to exceeding 5% rated power. Justification for Deletion: By letter dated February 3, 1984 (Reference 58), Energy Northwest confirmed the distribution of tone alert radios and brochures was complete. Inspection Report 50-397-84-05 (Reference 59) reviewed the
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 13 of 21 Benton County distribution records and identifies this item as "Closed". In Supplement 5 to NUREG-0892 (Reference 19), the NRC stated that this license condition is satisfied. Proposed Change to Delete License Condition 2.C.(26) This license condition states that in the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's (FEMA) final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of preparedness, the provisions of 10 CFR 50.54(s)(2) will apply. Justification for Deletion: This license condition is historical. In Supplement 4 to NUREG-0892 (Reference 4), the NRC concluded that the state of onsite and offsite emergency preparedness provides reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. The provisions of 10 CFR 50.54(s)(2) continue to remain applicable in the event that the NRC finds that the state of emergency preparedness does not provide reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. The requirements in 10 CFR 50.54 are conditions applicable to every nuclear power reactor operating license issued under 10 CFR Part
- 50. Therefore, this license condition can be deleted.
Proposed Change to Delete License Condition 2.C.(27) This license condition requires NRC review and approval of information related to the effluent radiation monitors. This condition was required to be satisfied prior to exceeding 5% rated power. Justification for Deletion: By letter dated June 29, 1984 (Reference 60), Energy Northwest submitted the required information. Inspection Report 50-397-84-20 (Reference 61) discussed the NRC review of the information and confirmed that there were no items of noncompliance. Proposed Change to Delete License Condition 2.C.(28) This license condition requires the environmental qualification of all electrical equipment in accordance with 10 CFR 50.49. This qualification was required to be completed prior to November 30, 1985. Justification for Deletion: By letter dated December 30, 1985 (Reference 62), Energy Northwest confirmed the environmental qualification Of required equipment was completed by November 30, 1985. In Supplement 5 to NUREG-0892 (Reference 19), the NRC stated that license condition 2.C.(28) is satisfied. FSAR 3.11 documents the Columbia environmental qualification program.
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 14 of 21 Proposed Change to Delete License Condition 2.C.(30) and Appendix C This license condition references the Additional Concerns contained in Appendix C and requires operation of the facility in accordance with these Additional Concerns. All items listed in Appendix C have been completed Justification for Deletion:
" The first Additional Condition, which is associated Amendment 149, requires the relocation of certain TS requirements to licensee controlled documents (e.g., FSAR) as a result of Columbia's conversion to the Improved Technical Specifications (ITS). This action was required to be completed by June 30, 1997. Licensing documents, programs and procedures were revised as required to implement the ITS and meet this license condition. Inspection Report 50-397-97-05 (Reference 63) documented that the ITS has been implemented. This condition has been satisfied.
- The second Additional Condition, which is also associated with Amendment 149, requires implementation of Regulatory Guide 1.160 commitments. This action was required to be completed 90 days from issuance of Amendment 149, which was issued on March 4, 1997. Specifically, as part of the change to remove the provisions for accelerated testing of diesel generators from the TS, Energy Northwest committed to implement a maintenance program for monitoring and maintaining diesel generator performance in accordance with the provisions of the maintenance rule and consistent with the guidance of RG 1.160. Inspection Report 50-397-96-18 (Reference 64) evaluated Columbia's implementation of the maintenance rule. This condition has been satisfied.
" The third Additional Condition, which is associated with Amendment 151, requires that the calculation of delta-CPR include the application of a conservative adder. This action was required to be completed prior to exceeding 25% rated power for Cycle 13. This action has been completed as required and is no longer applicable since Columbia is currently operating in Cycle 20. Inspection Report 50-397-98-01 (Reference 65) addresses the required conservative adder applied for Cycle 13. This condition has been satisfied.
- The fourth Additional Condition, which is associated with Amendment 153, requires the incorporation of information into the FSAR resulting from the issuance of Amendment 153 regarding suppression pool strainer screen material. This action was required to be completed 90 days from issuance of Amendment 153, which was issued on May 21, 1998. This action has been completed and the license condition has been satisfied. The relevant discussion is contained in FSAR section 6.1.1.1.3(c).
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 15 of 21
- The final Additional Condition, which is also associated with Amendment 153, requires inspection of the suppression pool screen material coupons. This action was required to be completed during refueling outage 14. This action was completed in R14, and the license condition has been satisfied.
Proposed Change to Appendix B The Environmental Protection Plan for Columbia contains a reference to 10 CFR 51.5(b)(2) that is outdated. This reference is proposed for deletion from Appendix B. Justification for Change: 10 CFR Part 51 was revised effective June 7, 1984, to implement section 102(2) of the National Environmental Policy Act of 1969 as amended, and section 51.5(b)(2) was deleted as part of the revision.
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria 10 CFR 50.90 In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Energy Northwest is requesting an amendment to Operating License NPF-21 for Columbia. The proposed amendment provides for the administrative removal of time, cycle or modification-related items from the Operating License. 4.2 Precedents The NRC has approved similar license amendment requests related to the deletion of historical license conditions that have been met. Specifically, the NRC issued Amendments 194 and 181 for LaSalle County Station, Units 1 and 2, respectively (ML092450404), Amendment 155 for the Fermi 2 facility (ML030170371), Amendment 211 for the North Anna Power Station, Unit No. 2 (ML020800601), Amendments 227 and 227 for the Surry Power Station, Unit Nos. 1 and 2, respectively (ML012470337), and Amendments 152 and 144 for the Joseph M. Farley Nuclear Plant, Units 1 and 2, respectively (ML013410430). The above amendments approved changes to the respective facilities' Operating Licenses to remove license conditions that were completed or otherwise no longer in effect. Similarly, Energy Northwest is submitting this license amendment request to remove license conditions that no longer apply. 4.3 Significant Hazards Consideration The proposed amendment provides for the administrative removal of time, cycle or modification-related items from the Operating License. These items have been implemented or superseded, are no longer applicable, and therefore, no longer need to be maintained in the Operating License.
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 16 of 21 Columbia has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of Amendment" as discussed below.
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No. The proposed amendment deletes license conditions which are completed or are otherwise obsolete. As such, the changes are strictly administrative in nature. The changes do not affect the manner by which the facility is operated and do not change any facility design feature, structure, system, or component. The proposed changes do not alter the design assumptions for the systems or components used to mitigate the consequences of an accident. Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No. The proposed amendment deletes license conditions which are completed or are otherwise obsolete. As such, the changes are strictly administrative in nature. The changes do not affect the manner by which the facility is operated and do not change any facility design feature, structure, system, or component. No new or different type of equipment will be installed. Therefore, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No. The proposed amendment to the Operating License is administrative in nature and has no impact on the margin of safety. The changes do not affect any plant safety parameters or setpoints. The license conditions have been satisfied as required. Therefore, the proposed change does not involve a significant reduction in a margin of safety. Based on the above, Energy Northwest concludes that the proposed changes do not involve a 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.
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 17 of 21 4.4 Conclusions 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 with the proposed changes to the Operating License and (2) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
The proposed amendment is confined to (i) changes to surety, insurance, and/or indemnity requirements, or (ii) changes to recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 REFERENCES
- 1. Inspection Report 50-397-84-07, dated April 18, 1984
- 2. Letter from J. D. Martin (Licensee) to J. B. Martin (NRC), "Nuclear Plant No. 2 Operating License NPF-21 Attachment 1 Status," dated April 12, 1984
- 3. Letter from G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Project No. 2 Chemical Waste Processing Preoperational Test," dated January 17, 1984
- 4. SSER #4 (NUREG-0892), "Safety Evaluation Report Related to the Operation of WPPSS Nuclear Project No. 2, Supplement 4," dated December 1983
- 5. Letter from A. Schwencer (NRC) to G. C. Sorensen (Licensee), "Chemical Waste Processing Preoperational Test," dated April 13, 1984
- 6. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Plant No. 2 Operating License NPF-21, Amendment No. 1, Licensing Condition 2.C.(1),
Attachment 1, Paragraph 1.c, Preoperational/Acceptance Tests," dated July 18, 1984
- 7. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Project No.
2 Completion of Construction Modifications Piping/Pipe Supports," dated March 16, 1984
- 8. Inspection Report 50-397-84-04, dated March 21, 1984
- 9. Inspection Report 50-397-83-60, dated February 22, 1984
- 10. Inspection Report 50-397-84-18, dated August 7, 1984
- 11. Inspection Report 50-397-86-18, dated June 20, 1986
- 12. Letter from C. M. Powers (Licensee) to J. B. Martin (NRC), "Washington Nuclear Plant - Unit 2 Final Startup Report," dated April 17, 1985
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 18 of 21
- 13. Inspection Report 50-397-84-38, dated February 1, 1985
- 14. Inspection Report 50-397-85-27, dated August 9, 1985
- 15. Letter G. C. Sorensen (Licensee) to E. G. Adensam (NRC), "Nuclear Plant No.
2 Operating License NPF-21, License Condition 2.C.(4), Seismic Equipment Qualification," dated June 3, 1986
- 16. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Project No.
2 Environmental Qualification Report for Safety-Related Equipment, September 1983," dated September 16, 1983
- 17. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Project No.
2 Environmental Qualification Assurance," dated January 18, 1984
- 18. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Project No.
2 Qualification of Pipeline Mounted Equipment," dated January 23, 1984
- 19. SSER #5 (NUREG-0892), "Safety Evaluation Report Related to the Operation of WPPSS Nuclear Project No. 2, Supplement 5," dated April 1984
- 20. Letter from G. C. Sorensen (Licensee) to W. R. Butler (NRC), "Nuclear Plant No. 2 Operating License NPF-21, License Condition 2.C.(6), Ultimate Heat Sink," dated September 27, 1985
- 21. Letter E. G. Adensam (NRC) to G. C. Sorensen (Licensee), "License Condition 2.C.(6) Ultimate Heat Sink," dated December 11, 1985
- 22. Letter G. C. Sorensen (Licensee) to E. G. Adensam (NRC), "Nuclear Plant No.
2 Operating License NPF-21, License Condition (7) Turbine Missiles," dated November 20, 1986
- 23. Letter E. G. Adensam (NRC) to G. C. Sorensen (Licensee), "WNP-2: License Condition on Turbine Missiles," dated March 27, 1987
- 24. Letter G. C. Sorensen (Licensee) to E. G. Adensam (NRC), "Nuclear Plant No.
2 Operating License NPF-21, Satisfaction of License Condition 2.C.(8)," dated February 4, 1986
- 25. Letter from G. C. Sorensen (Licensee) to E. G. Adensam (NRC), "Nuclear Plant No. 2 Operating License NPF-21, Satisfaction of License Condition 2.C.(8),
Supplemental Information," dated May 9, 1986
- 26. Letter E. G. Adensam (NRC) to G. C. Sorensen (Licensee), "WNP-2 License Condition 2.C.(8) - High Burnup Fission Gas Release," dated May 23, 1986
- 27. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Plant No. 2 Reactor Vessel Water Level Instrumentation, License Condition (9) and Response to Generic Letter 84-23," dated November 27, 1984
- 28. Letter G. C. Sorensen (Licensee) to E. G. Adensam (NRC), "Nuclear Plant No.
2 Operating License NPF-21, License Condition 2.C.(10)," dated January 27, 1986
- 29. Letter E. G. Adensam (NRC) to G. C. Sorensen (Licensee), "WNP-2 Operating License NPF-21 License Condition 2.C.(10)," dated March 21, 1986
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 19 of 21
- 30. Letter G. C. Sorensen (Licensee) to E. G. Adensam (NRC), "Nuclear Plant No.
2 Operating License NPF-21, License Condition 2.C.(12), Alternate Remote Shutdown System," dated June 2, 1986
- 31. Letter G. C. Sorensen (Licensee) to E. G. Adensam (NRC), "Nuclear Plant No.
2 Operating License NPF-21, Alternate Remote Shutdown System," dated August 6, 1986
- 32. Inspection Report 50-397-86-18, dated June 20, 1986
- 33. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Plant No. 2 Safety Evaluation Report, NUREG-0892, Closure of License Condition 10, BWR Startup or Operating Experience," dated November 11, 1983
- 34. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Plant No. 2 Termination of Need for Shift Advisor," dated October 16, 1984
- 35. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Plant No. 2 Detailed Control Room Design Review Program Plan and Addendum to the Procedures Generation Package," dated February 17, 1984
- 36. Letter G. C. Sorensen (Licensee) to W. R. Butler (NRC), "Nuclear Plant No. 2 Submittal of Detailed Control Room Design Review (DCRDR) Summary Report," dated November 1, 1985
- 37. Letter R. B. Samworth (NRC) to G. C. Sorensen (Licensee), "Detailed Control Room Design Review," dated July 9,1990 37a. Letter P. L. Eng (NRC) to G. C. Sorensen (Licensee), "Status of TMI Item I.D.1.2, 'Detailed Control Room Design Review' (DCRDR) at Washington Public Power Supply System Nuclear Project No. 2 (WNP-2)," dated November 13, 1991
- 38. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Plant No. 2 Licensing Condition (16)," dated March 19, 1984
- 39. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Project No.
2 Operating License NPF-21, Licensing Condition (16)," dated April 17, 1984
- 40. Inspection Report 50-397-84-23, dated September 18, 1984
- 41. Letter G. C. Sorensen (Licensee) to E. G. Adensam (NRC), "Nuclear Plant No.
2 Operating License NPF-21, Satisfaction of License Condition 2.C.(16), Attachment 2, Item 3(a)," dated June 4, 1986
- 42. Letter G. C. Sorensen (Licensee) to Document Control Desk (NRC), "Nuclear Plant No. 2 Operating License NPF-21 Satisfaction of License Condition 2.C.(16), Attachment 2, Item 3(C), Wide Range Suppression Pool Level Monitoring System," dated June 15, 1987
- 43. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Plant No. 2 Facility Operating License NPF-21, Licensing Condition (16), Emergency Response Capability," dated March 22, 1984
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 20 of 21
- 44. Letter R. B. Samworth (NRC) to G. C. Sorensen (Licensee), "Issuance of Amendment No. 77 to Facility Operating License No. NPF WPPSS Nuclear Project No. 2," dated March 1, 1990
- 45. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Project No.
2 Safety Evaluation Report - NUREG-0892, Outstanding Issue 1.7(9), Modifications to ADS System Logic," dated July 26, 1983
- 46. Letter J. D. Arbuckle (Licensee) to Document Control Desk (NRC), "Nuclear Plant No. 2 License No. NPF-21 NRC Inspection Report 87-19," dated January 29, 1988
- 47. Inspection Report 50-397-88-45, dated February 14, 1989
- 48. Letter G. C. Sorensen (Licensee) to E. G. Adensam (NRC), "Nuclear Plant No.
2 Operating License 2.C.(19), Relocation of Engine-Mounted Controls," dated June 3, 1986
- 49. Letter G. C. Sorensen (Licensee) to E. G. Adensam (NRC), "Nuclear Plant No.
2 Operating License NPF-21, Satisfaction of License Condition 2.C.(20)," dated June 3, 1986
- 50. Inspection Report 50-397-86-11, dated August 5, 1986
- 51. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Plant No. 2 Operating License NPF-21, Licensing Condition 2.C.(21), Control Room Chillers," dated May 31, 1984
- 52. Inspection Report 50-397-90-05, dated August 9, 1990
- 53. E. G. Adensam (NRC) to G. C. Sorensen (Licensee), "License Condition 2.C.(22) Control System Failures," dated January 6, 1986
- 54. Letter G. D. Bouchey (Licensee) to A. Schwencer (NRC), "Nuclear Project No.
2 Hydrodynamic Loads Outside Containment," dated March 28, 1983
- 55. Letter G. D. Bouchey (Licensee) to A. Schwencer (NRC), "Nuclear Project No.
2 Hydrodynamic Loads Outside Containment," dated June 16, 1983
- 56. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Plant No. 2 Design Assessment for Hydrodynamic Loads," dated January 24, 1984
- 57. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Plant No. 2 Status of Emergency Preparedness License Requirements for Operation in Excess of Five Percent," dated March 19, 1984
- 58. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Plant No. 2 Status of Emergency Preparedness License Requirements for Operation in Excess of Five Percent," dated February 3, 1984
- 59. Inspection Report 50-397-84-05, dated March 16, 1984
- 60. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Plant No. 2 Operating License NPF-21, Licensing Condition 2.C.(27), Effluent Radiation Monitors," dated June 29, 1984
- 61. Inspection Report 50-397-84-20, dated August 24, 1984
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Enclosure Page 21 of 21
- 62. Letter G. C. Sorensen (Licensee) to E. G. Adensam (NRC), "Nuclear Plant No.
2 Equipment Qualification," dated December 30, 1985
- 63. Inspection Report 50-397-97-05, dated May 6, 1997
- 64. Inspection Report 50-397-96-18, dated January 29, 1997
- 65. Inspection Report 50-397-98-01, dated May 8, 1998
- 66. NUREG-0892, "Safety Evaluation Report Related to the Operation of WPPSS Nuclear Project No. 2, dated March 1982
- 67. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Plant No. 2 Operating License NPF-21; Request for Amendment to Licensing Condition 2.C(11 ), Shield Wall Deferral," dated August 15, 1984
- 68. Letter A. Schwencer (NRC) to G. C. Sorensen (Licensee), "Issuance of Amendment No. 7 to Facility Operating License NPF-21, WPPSS Nuclear Project No. 2," date December 10, 1984
- 69. Letter G. D. Bouchey (Licensee) to A. Schwencer (NRC), "Nuclear Project No.
2 Control System Failures Questions, WNP-2 SER #3, Outstanding Issue #13, Final Submittal," dated June 24, 1983
- 70. Letter G. C. Sorensen (Licensee) to A. Schwencer (NRC), "Nuclear Project No.
2 Supply System Response to FSAR Questions 031.143 - 031.159," dated November 10, 1983
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 1 of 16 (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. (6) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to store byproduct, source and special nuclear materials not intended for use at Columbia Generating Station. The materials shall be no more than 9 sealed neutron radiation sources designed for insertion into pressurized water reactors and no more than 40 sealed beta radiation sources designed for use in area radiation monitors. The total inventory shall not exceed 24 microcuries of strontium-90, 20 microcuries of uranium-235, 30 curies of plutonium-238, and 3 curies of americium-241. C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3486 megawatts thermal). Itemfs in At4t~aclhmlent 1 shall be eefmpletedd ass specified. A-t-a-h-- (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendmentk __and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- a. For Surveillance Requirements (SRs) not previously performed by existing SRs or other plant tests, the requirement will be considered met on the implementation date and the next required test will be at the interval specified in the Technical Specifications as revised in Amendment No. 149.
Amendment No. X
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Attachment 1 to Enclosure Page 2 of 16 (3) in.i.t ia T es.t *.. ... ( . ....... . A. .... Deleted. The lionsce. ,hall eendut the initial tet pr.gram. (set ferth in S ,,tien 14 of the licfnsco's, Final Safety Analysis Report, as
... cnd*d) without "akingany medifications of this program uni ....s su ii..U,di ie t.ions i areIUi~..t. . ini ae eoa e with the. ppiv.i~ig.4 e tv hrm SLLt ie 595--9.- in addition, the liccnscc shall not mfakc anyj m-jor iiUý A IC 4-4H IIMC 4-A 4-b4 i Iel i 14111 U~iL4 mit~A4 I 4 t A-II ii V , i .U
ý I, iL ik FI, i I../ v ýj. i I i U,1
. iii'. iI *L I i i a! . M ji V...gl r .. ii,* t. .
UI L ii U. I I LU U. iU !!, V` I,, I V Lu F I It-i~ 0101,rvu7Fppi.T are defined a5. E14linatien of any test 4idntified in Scotion 14 *fthe liccnscc's Final Safety Analysis Rcpert, as amclnded, as being csscntial; Modification of tcst objcctivcs, imothods or acccptanc
.rit.r.a fee any test id.ntf.ecd in Sectin 14 of the Pericnsces Fifal Safety Analysis Rcpe.t, as amicndd, as being cosontial; Pcrfarinmenc of any tcst at a pawcr level diffcrcnt fromf that 1
iii UiiU. p U~i 'iii,' I -. 4 I. . . 4 - . . . . ^^ .^ ;----1-i .. I -. , U I Lii U. UULUHIi I LUL UIIJ UL.4U.4 H ilL UULU
. .. . . itI i .
I V riP "UVV i*lr . r 0 v. v
=M U.
l F4 Hplvj autherized poweir levclý- ui XF 1 i J m M ýUFPU UP .......... U (4) Cr' 4zm 4 iin~'r Ij ifieatien ,See+ien 3.1. & 4H Deleted.
,,4,- * *^ 4-6^ 1 4 UI U I U F4~ ij ii V I iP U I PH .U iL L I Itf~ -U V L UPH i PLI i L shall .... pletc 5se5im qualifications for all equipment approved by thr' 'tff 5R£ fer in^terimfne.....ai^n (5) F ,:iiRm 'n-,t n-i-] irf I P.;*i t A i iin'iIA r inA3P! . . Deleted.
UP LU L~LLLU H iP~ i i VL ~ 4~ ~.JLg ULPiL UP H UULU ~UVVLi , UISL i P LU.HP.4U.L Jl l ICI./IU V I .J'C. bInI' TjI VUICI I Z I ta=..II n I vIr VT r i rU O.WU**I~r tVUI shall pavidcethe staff for their r.vi.w and appreval:
+(-a-- assurancc that all cquipffcnt listed in Appendix 3B is cithcr i... U...
..... U...... LUU...
.U.. . . UL..U.. i Ii LU..
.. U HU PUP i ni LI ig U. .... ........
opo ration.
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
jAmendment No. xxx I
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 3 of 16 5-tor- all aicmonsatcty relatedl cquipmclnt, proviac assura... thet th.g values for the as installed eenfiguration dei^nt .....cd the "g" values established in the.uc c .uipmnt qualifieati-n infeofrmati.n dc*" mcntatio,' (*-9) filp1 " p rnw'imT m il-t ti ' fE int'pim -r'-ii-n I1 .I-I4' -{- ^ LJ - -ý / - 4' (6) '4 -I1 C' - 2..5 ER- Deleted. to startup ,,lwingthe tirst Pefucling utage, the i..ens.. shall pcraform apcratienal testing of the ultimfatc heat sink spr-ay pond to verify . araly..d parameters of drift loss, seepage and operational capae* y.. The liccnee shall inform the *of NR staff s.hcdu.l.d testiing at least 30 days in advance of such testing and shall providc the test results and conclusions fer NRC review an approval. (7) Tw ',,,, H s soe, ( ,,, . 1.3, ,, ,ER#4) Deleted. The li,,mse shall submiI' t for NRC staff approval, within thrcc years of date of issuamcc of this licensc, a turbinc systcmf
'.aint.nan program
. based on the f*nufacturer's calculations of mfissilc gcnceratien proebabilities acceptable to the NRC staff or volum.etrically in.sp.t all low prossur turbine rotors at the sccnd refueling autagl , and at every other refueling outage thereafter until a mfaintcniancc programf is approvcd by the NRC staff.
(8) rdt 1 bUdidblontV k tyttt-, 1 fir! d+ . ', . Z5 . 6 k + ) , -1 ý- K t Deleted. P*rior t startup foll*wi*g the first Frfucling outagc, the licensee shall provide for NRC staff review and approval revised analyses-showing the cffccts of high burnup fission gas release on loss of coolant accidcnt. (9)
..... ...R. Deleted.
The 1iccnscc shall imfplcmclnt staff's requiremfents rcgarding additieonal in.tru..ntatian for deetion of inadeH.ate core cooling which mfay rcsuilt fromf the staff's rcvicw of the BWR Owner's Croup# Rcperts (SLI 8211 and SLI 8218) and the licenscc's plant spccifice cvaluiation rcpor-t addrcssing the subjects. Any eq-u-4-ed moldifications shall be comfplctcd on a schcduilc acccptablc to h N1RG staff. Amendment No. xxx I
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 4 of 16 (10) The-fflal aulie S b i eei.e* A4 (,S A. A Scr) Deleted. Prir tI startup fIll4wing the firs¥t rfuoling iutage, the liiinseo shall1 previ de for NRC staff roevi ow and- approval a rovi sod 5tabiliity (11) Shield Wall Deferral (Section 12.3.2. SSER #4, Licensee Amendment #7) The licensee shall complete construction of the deferred shield walls and window as identified in Attachment 3, as amended by this license amendment. ( 12 ) Al t . . r.n.et . . . .t .A S h t d. . w. S"S-E y t ef ie 7 .4 .2
* .3 R"# 1 ) D e lete d .
Pior to stotup fo!o*wing the fipst rofuel g .. .utag, theo li..nso,
,hall install, test, and .p.rablo have the alternate rmoet. shutdown systefm.
(13) Deleted. (14) Fire Protection Proaram (Generic Letter 86-10) The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in Section 9.5.1 and Appendix F of the Final Safety Analysis Report (FSAR) for the facility thru Amendment #39 and as described in subsequent letters to the staff through November 30, 1988, referenced in the May 22, 1989 safety evaluation and in other pertinent sections of the FSAR referenced in either Section 9.5.1 or Appendix F and as approved in the Safety Evaluation Report issued in March 1982 (NUREG 0892) and in Supplements 3, issued in May 1983, and 4, issued in December 1983, and in safety evaluations issued with letters dated November 11, 1987 and May 22, 1989 subject to the following provision: The license may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Amendment No. 1,7,91w
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 5 of 16
- 6a -
(15) .. . . Stap B e , ,ee ,t ,,,i E ........ g, ..... e ,, 13. 1. 2. im,,* , Deleted, During the startup test programn, the iiconsoc shall have en eacht shift a licensed individual with previous staratup or- operating
. . a Expmcri .mpar.ble BWR, r an advis" r wh; m.eets these (16) Effep-meyResens Gaabiit (S-eetien- 180. SER SScRfl44 T411 item 1.D.1 and Section 13.5.2. SER, SSER #4) Deleted.
The li,.n... shall, orre+t the design defi.ien.ies for the contr.l resm and complete the other related tapabilities emergency response as rnequir-ed- by Attachmfent 2 to this license. IAmendment No. xxx I
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 6 of 16 r% 1 A (17) waHet, vith la HEH-H=uwattr Heating tSeet-jen t5.=z:z= , vIt:a . The 1*icnsee shall mot .perate with partial feedwater heating for the pupose- of extending the nm....al fuel .y.le unless acceptabl. jbistification i's pro~vided to and approved by NRC staff (18) ... ... .. ,,e, . ..... fl ti... D e ....
- s u. ,zatie .... o t,*, t,,,
L eq (114.3.18°6.3.5 C , 5SER
. S t #o44 Deleted.
Prio to star.t..p following the fir.st refuelin.g outage, .iee.. the ... shal l:
+~-a4 linstall moiidi ficateions to the AutomfaticeDepr-e5uri zatien Systemf acceptable to the NRC;,
+b4~) .. Inhoporate into the Plant Emergeney Procedures the usage of the inqhibit switch.
I (19) Re-ieat*en ef Engine U....r e (SeCtie. es...,- 9... t C CCCr SS &A
#44 Deleted.
Prior to startup following the first refueling outage, the controls and moneitoring instrumfentation on the HPGS diesel enggine skid shall be installed inl a freestanding floor mouented panel separate fro the enlgine skid. The controls and molnitering instrumfentation shall be located in a vibration free floor area er shall be qualified for the vibpations that will occur during engine operation (20) Efflepq...... 94*e Enqimm StrigSsefS-ection 9.5.6 SER SSn Ee
# Deleted.
Prior to startup following the first refueling outage, air dryers I I - . llj, - .I.. , ,. .. i\,ý:j i_ i\. - (21) Deleted. The licensee shall have operable beforne May 31, 1984, redundanit, seismic~ Category I environmffentally qualified water- chillers for control roomf HVAC. Amendment No. 4-4-qXXX
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 7 of 16 (22) G nre... Sy'stems Failures (Seetlens 7 ,7.7.2.2. 7.5.2.3. SR -
-Deleted.
Prior to startup following the fir-st rcfucling o~utage, the liccnscc shall previdc to NRC staff for review and approeval anly angalysis er-odififcatin .n. edcd to rcsolv' the foll'wing itc.s.
+~a4 capability t8 attain a safe shutdownq condition fe))owing the less of any Class 1E instrumclnt bus
-.. ,4 of cntrol 5yste...s failures rcsulting from high the im.pa.t cnergy 1i,, b**aks on, the transint and a,,id*mt analyses
+c4 the imfpact of control systecms failurcs due to the failurc of commonlef pewcr sourccs, 5ensers, or instrumclnt sensing lines on the transient anlalyse5.
(23) ir. y L A Iaff - 1 SE. S- E 4 Deleted. Prior to cxccceding five (5) pcrccnt of rated thermfal pewcr, the li..nsc. shall pr.vid. for NRC staff review and approval the rcsults of the rcconciliation of the hydrodynamic loads for all the safcty related piping, cqui .. pnt and their supports. (24) Efleqne lam'l Peraf (Sete 13.3 SER SE #44 Deleted. Prior te exedn fiv (5) perccnt of rated thermfal pewcr, functionally spccific tr-aining in cmcreigcncy rcs~ponsc duties mfust be prvdcd to the rcmfain~ing mcmffbcrs of the cmcregcncy organization tafwhon were iot ýinclutdd 4inprcvieus cmcergcncey prcparcdncess training spccificd in the flminimumf staffin rcurmct f Tabl B 1 of NUREC 0654 (including on shift and 30ad60 mfinutc augmclntatien capability). (25) Gfst Empee'Peaeme5(ete 33 Deleted. Prior to cxcccding five (5) pcrccnt of rated thermal pewcr, thce liccnscc shall ccrtify to the NRC that:
-W4 The distribuitioni of tonc aleicrt radios, which arc part of the alcrt and notificatio~n systcmf, has been comfplctcd to residents volthin the plumcl exposure pathway Emclrgcncey Planning Zone (EPZ).-
+-24) The distribution of public informfation brochurcs has been complctcd to the population within the plumcfl expesurc pathw,,ay EPZ.
jAmendment No. xxx
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 8 of 16 9-(26) Pr qr 5 . a..Gf s t f. ... Ef-^ ...ne ...... .. .9
.A nes . ee. di .r SER4, Deleted.
in the event that the PIR*f*nds that the lack of progr.s. in comfpletion of the preccdurcs in the Fcdcral Emcregcncy Managcmclnt Ag.ncy.s final iub*l, 44 C.F.R. Part 350, is an indication that a m..jor. substantive problam exi sts in aehieving or maintaining an adequate state of pr.par.dn.ss, the provisions of 10 C.F.R. Secti 59.54(s)(2) will apply-. (27) E Radiation P (Seetien 11.5 cER #4) Deleted. Pri.r to July 1, 1984, the lien.ee shall previde the followinE inform...atin to the PIR staff for thci r.. .vi.w and approval: o-
- 1. Sensitivity of the effluent moeneitor.
- 2. Evaluation o f responsc timf.es of these i"strumcnts.
- 3. Evaluation of the instrumcnts pcr criteria sct f*rth 4in Scti,
.47 of ANSI 13.10.
- 4. Compliancc with Scctien 5.4.9 of ANSI 13.10.
S. Evaluation of capability to provid a calibratcd el ctrical signal to verify circeuit aligflnmnt and, if uiscd, a eeommfitment, that they be qualifieod-. Deleted. Prior to Novefmber 30, 1985, the liccnscc shall environmolntally qualify all elcotrieal cquipmcint accor-ding to the provisions of 1 CFR 50.49. (29) Protection of the Environment (FES) Before engaging in additional construction or operational activities which may result in a significant adverse environmental impact that was not evaluated or that is significantly greater than the evaluation in the Final Environmental Statement the licensee shall provide a written notification to the Director of the Office of Nuclear Reactor Regulation and receive written approval from that office before proceeding with such activities. (30) Additional Corc..rr. Deleted. The Additional GCen..rns. ntaincd in Appendix C, as revised through Amiiendm.ent No. 153, arc hereby
, iinrpJratcd into thIi liccn.* .
Energy Northwcst shall opcratc the faeility in accord-ancc withth Additional Conccrns. Amendment No. 149 11, 1 5 , ,XX
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 9 of 16 ATTACHMENT 1 TO OPERATING LICENSE NPF-21 I i i i i Li 1 1 I The etednse snail complete the tolowing requircmcnts witnin the sencaule ncat be-lew-, Deleted. ili-eeeeratienal4eeeetanee Tests The liccnscc shall, priair to loading of fuel in the corc, eefmplete the Systcmf 36 prcopcrational tcsting to assure that thosc ffoniters required for fucl lead fully meet the Teehnia pcf i rcguir.......
"ithut" rcliancc an action 5tate..nt5:
The lieensee shall sueeessfully eemplete the follewig prcoper~atienal/laeeeptancce tests befere exeeing 5% power:, P4T-_3_3 9 B Ch e*ic l Wast , e Pr... .ing PT 7. Misccllancou~s Radiation,,. MoAnitoring Equipmclnt P--49 Off Gas Systcmf A-T--659A Scaling St*F*, Syst"cfm A4~-6-&-8 Condcnscr Air Rcmolval4 P-T--669-.A C.nd.nsat iSyt. .. PT 79.. A C .nde.-sat- St.-agc Transfer
-PT 7.-01-9A Condcnsatc Filter Dcmfincralizer Systeom PRTt 72.0 A ,. .oeter F,.dwat.r Turbi.. and Pum.ps P4-74-4-&- Rcactor Fccdwater Controls AT.A Heater Vents andDrains AT82.*,,A Turbine Building Heating and Ventilating PT- 92-2--A Off Gas Vault HVAC AT 119.9-A Loosc Part5 Bctcctin P* 9-T.-1--I--A Primary .. tainm..t inte.gatcd .cakag, Rat. T**t AT- rA integrated
.392. Condn.sr inLeakage Toot The liccnscc shall ,iplcti PT 22.0 B, Nitrogen incrting Systcm prior to 5i)( molnths after initial critieality.
ilanqeps Supoerts. and Restraints.
... ..
- T I
- TT
- T A1l QI S! and Ol S! nanggI*crs, suppo*r1, and rIstraints Iin1ing installation andlor mo I edif i cati on wi 14be,.mpl et. d"g pri,or to eIx,.din 5% pwe"r .
v, , i e , - , 1 u fi beffip I eti an t p9a5teF baw) ' etj en i=j s:E beReab ie 9 The liecnscc shall rcstrain fuel loading, primary systefm 5tcamfl prcssuri......, x.
... 5% powcr,
.ding ,
and ommcr,,,cal. operatio,, bY prcrcgusitc coplction of the a55eciatcd catcgorics of itcmsl in accordanc with. the 5echcdulc shown on the Projcct Plastcr Comfplctien List dated Dcccmfber 19,-~983. The liccnscc shall not extend the comfplctien catcgorics for 4inrl ki 4'1tml itr-m-5 ef the' 14 'R# Wth 4t i minrnnti fi r.-tiAn RAOl i ndri wi Fi--i I
- - I - -- - -- --
cnU, I -tt by d 1 npfet!Ntdt1Vc tnc rfieu 040b gianal 0rricc. .Cocrc....ial opcration is dcfincd as the 100% p.w.. warranty run or July 1, 1984, whi"ehvr occurs.. first. Amendment No.1 x l
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 10 of 16 ATTACHMENT 2 T1^ 1i ^ -&^^ k al eamfplIete the to I owing ,cui-rgmentsan the schedulu notz b~e!-6W!~ Deleted. R*PAI PARm ppqiAm ppwipl, (Prpr)p) 4-- 4 -- Ge e shall subm" t a program plan for nnRDR for NRC staff rOview WVi . I VVE)ii nn )lE. iii;tii i t i,,,i.I e the i.iT L. Ini .. II* ; ;iee.s. aInd a summary r.po.t not later than six (6) mo.nths prior to the first r*fueling eutagc. The lie.ns.. shall eorrct and i...pl.nt to the NRC staff's satisfati.on, the following humfan ngncngdefeiemicnis prier to execcding five (5) p .r nt of.. thtrtotal p'wtr. .at.d A 5.1.* Inopcrativc Syst,, Status Panels
-A4-. 1 inoperativc T9AS and C0S eemputer systcmfs 9 .5 Multiple mcanaing abbrcviatiens, lack o~f abbrceviatien control 4 Hard to.p.rat. pushbuttons on tr.llcrr ...
B 549 Non standard fuel zenc moneitor mcltcr scaic, P 601 5.44 idntal push butt"... bt status lights, P 820 4-- Id*,,ntial push button.push button indicator lights, Rod Worth Mqinfimizcr, Rod Monitor control! subpancls, P 603 S.2191 Inadcguatc labeling, Isolation Control, P60 9 8.348 Non idcntical RFW mcltcr, groupings fair Systcmfs A & 8, P 840 S..... 4i....ist.nt scalc, CW Inlet Plenumu Levee, Indicator and C.ntr.llcr, P 840 E 5.-61 Rccordcr pointcrs ebscurc scalc numoreals/graduation mfark~s E .6 RPV dcpprcsurization proccdurcs call for grcatcr rcad-ing accuracy than is previdcd by pr.ssu.. indicators F 4.37 Switch handlcs obscur.. pointcrs./labls, P 890 The liccnscc shall corrcct and imnplcmclnt to the NRC staff's satisfaction, the following hum,,,an . ngin,..,ing dcfi.icncics within four (4) months after the issuancc of this apcrating liccnsc:,-- A,,Audio alar. signal detc*tien and intensity levels 9-42 [xtcnsien handles for throttlablc valve controls, P 820 9-.4-9 Propcr chart paper for Ccncrater Monitor Tcmfpcraturcm Rccordcr, P 820 E .... ist.nt
... push.button . olor coding E.4. Extcnsin
.. handlc for RPS r.s.t switch, P 603
-F-6- inconsistcnt fonts, switch cscutchcon legends
,F.- In.n .... t5in*,,,pushbuttn* color coding
- tED finding id.ntificati.n as giv*n in NRC letter to 9. W. Mazur dated IAmendment No. xxx I
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 11 of 16 Attaelifhlent (a) The licensee shall implement (installation or upgrade) rquiem,.ents of Regulatory Guide 1.97, Revision 2 with the exeeption of iteffs (b) and (e) below prier to startup falltoing the first raefueling .utage. (b) 9e ete.*"" (e) The licensee shall iflplement (install and haye operational) a wide range
-- level m,,,nitoring system. whih satisfies the Category 1 suppres.ioan peal equipmfent specifications in aeeordanee with Regulatory Guide1.7 Revision 2, prinir to startup following the second refueling outage.
The licensee shall pro~vide within two(2) molnths after- the issuiance of this5 operating icenfse, an addendumf to the Procedures Generation Package describing the function and task( analysis as identified in Supplement 1 to NUREG 0737. The licensee shall have fully funcetional emfergency response facilities (Technical Support Center, Operational Support Center, and Emfergency Oper~ations Facility) prior to exceeding five (5) percent of rated power. Amendment No. 25, Io,
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 12 of 16 ATTACHMENT 3 LIST OF SHIELD WALLS
+/-1. FSAR Fi*u.. 12.3 32. Zen^ H 9 The partial height wall ,utoide the
.p..rt roa .. "t r..m Deleted.
FSAR Fiquro 12.3 26. Zore G 12 The tube aeeefs5 wall to the mfaint ea-n5 .ir1. Deleted n
- . FS^R Fi ... p . `.3 27, Z*^n*e . 11 Safl as..abe... e,k .ly ether end of e )nd g5er-.Deleted.
+/-4 11 ki i k dominolra lizor. ubi..*e !e. Deleted.
heaccess blockout to*
-- *duplicate c..
FSAR Fiq rure( Zone G-9 centrifuge room.
- 6. FSAR Figure PZone F-9 Same as above for the duplicate centrifuge.
- 7. FSAR Figure
- Zone J-5 The blockout for one of the two decon concentrators.
- 8 FSAR Figure Zone D-8 The two block walls at the north end of the truck loading bay.
- *9. FSAR Fi ajrp 7nnp F-P The leaded glass viewing window in the radwaste area.
iteoms +/-, e, oaig will be ýirsatlled prioir to one yea- aftter the i55buanee et the WNP 2 9perating Lieemszo. Shield walls and window identified in items @-3-- 5
- , 6, 7, 8, and 9 will be installed if the associated radiation levels at these locations exceed 2.5mR/hr as dictated by the ongoing ALARA reviews.
Amendment No. x
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 13 of 16 APPENDIX B TO FACILITY OPERATING LICENSE NO. NPF-21 ENERGY NORTHWEST COLUMBIA GENERATING STATION I DOCKET NO. 50-397 ENVIRONMENTAL PROTECTION PLAN (NONRADIOLOGICAL) Amendment No. ,5 x
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 14 of 16 significant increase in any adverse environmental impact previously evaluated in the FES-OL, environmental impact appraisals, or in any decisions of the Atomic Safety and Licensing Board; or (2) a significant change in effluents or power levell[in aeeardarmc with 10 C.R Part 51.5(b)(244 or (3) a matter, not previously reviewed and evaluated in the documents specified in (1) of this Subsection, which may have a significant adverse environmental impact. The licensee shall maintain records of changes in facility design or operation and of tests and experiments carried out pursuant to this Subsection. These records shall include written evaluations which provide bases for the determination that the change, test, or experiment does not involve an unreviewed environmental question or constitute a decrease in the effectiveness of this EPP to meet the objectives specified in Section 1.0. The licensee shall include as part of its Annual Environmental Operating Report (per Subsection 5.4.1) brief descriptions, analyses, interpretations, and evaluations of such changes, tests and experiments. 3.2 Reporting Related to the NPDES Permit and State Certification Changes to, or renewals of, the NPDES Permit or the State certification shall be reported to the NRC within 30 days following the date the change or renewal is approved. If a permit or certification, in part or in its entirety, is appealed and stayed, the NRC shall be notified within 30 days following the date the stay is granted. 3-2
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 15 of 16 APPENDIX C AD*9TIONAL CO*,ITIONS Deleted FACILITY nPERATIN, T* ICENSE G. NPF 21 Lngerigy ;'15tniWest 51nail ewmpiy witn tnce rol lwring e()il~iti;Eqel 6H tflO 5senoules roted belew. Amendmfent*ll Imp .em.+entation
*Wumber-
--4-9 The licensee shall relecate certain Impl em.entatieon technical specification. re.uirfemint5 shall be comfpleted te lieern'r'r rrntpelir'l 1'-i -r~t~.v by June 39, 1997. described beleow. The l-e-eati '-'n 'r rn"'zr' requirefmen.t. 51gan. .e retai. sy tnc licensee.
-a-. This license condlition approves thle relocation of certai technical specificati.n requiremients to, licensee controlled documents&
A -- k- - - A 4 4-- --- 1 -- 4L, licensee's letter dated January 14, 4-19--. The approval is decumented in the staffs . afety evaluation dated March 4, 1997. Regulatory Guide 1.160 commffitmfents- imfpl ementati on as de..ribed in Atta^*ment 1 to the shall be completed licensee's letter dated January 14-, 90 days fromf the 1997. date of issuance of Amlendment 149. To, en*He sufficiently ,,onervative ipl eFmentati on SPC 9X9 9 ,LMCPR5, the calculation of shall be eomfpletcd
.. PR will include a conservative adder prior to xc'eeeding based on the variability observed 4i 25% power fop Gy.e1e 13.
eerrelatien This5 adder will1 be a-t Sini .. um, the greater of two times the standard deviation in the m..ean err of the predictions relative to the ealeu 1A pit~-M;4*tr'i w~l- A 0 A:AP* i tn PR .Af A i7 ; applied to the tPR n alculation, and , Ill, be independent of the 9.975 fact orin
ý I -u I .. -a- U-11 U0 U eefl5eevative
*VIIV* ..... i* b4a,, #R
*m #hp '=A.47 Rppo4ir t i onsjafG LE - Frt Her N K. rueI.
Amendment No. 1"', 151,
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS to Enclosure Page 16 of 16 Amc*endfcl,+t imfpi omoentati on
*~Uffbcr-.
This affcndmclnt autherizes the liconsoc to 90 days fromf the incorperate in the Final Safety Analysi date of issuanco. Rcport (FSAR) ccrtain changgos te the description of the facility-. imfplcmclntation of this amclndmclnt is the incorporation of these
,hangs as dcscrib, d in the lcc.,se'5 applieatiefn dated April 16, 1998, a5 5upplecmcntecd by letters dated April 28, 1998, and May 8, 1998, and evaluated in the staffs5 Safety Evaluationl dated May 21, 1998-.
This amle.Ldmnt is e.nditiened en the 1in Refueling Outage eefmplcting the eefmmfitments rcgarding inspcctien ef EGGS supprc~ssin peol 5crccn mfateri-a4 eoupons as dcscribcd in the liccnsccs5 supplcmclntal letter dated April 28, 1998, and evaluated in the staff's Safety Evaluation dated My21, 19 98. Amendment No.{
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS of Enclosure Page 1 of 14 (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. (6) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to store byproduct, source and special nuclear materials not intended for use at Columbia Generating Station. The materials shall be no more than 9 sealed neutron radiation sources designed for insertion into pressurized water reactors and no more than 40 sealed beta radiation sources designed for use in area radiation monitors. The total inventory shall not exceed 24 microcuries of strontium-90, 20 microcuries of uranium-235, 30 curies of plutonium-238, and 3 curies of americium-241. C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3486 megawatts thermal). (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment *** and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- a. For Surveillance Requirements (SRs) not previously performed by existing SRs or other plant tests, the requirement will be considered met on the implementation date and the next required test will be at the interval specified in the Technical Specifications as revised in Amendment No. 149.
Amendment No. **-*
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Attachment 2 of Enclosure Page 2 of 14 4-(3) Deleted. (4) Deleted. (5) Deleted.
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
I
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS of Enclosure Page 3 of 14 5-(6) Deleted. (7) Deleted. (8) Deleted. (9) Deleted.
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Aftachment 2 of Enclosure Page 4 of 14 6-(10) Deleted. (11) Shield Wall Deferral (Section 12.3.2. SSER #4, Licensee Amendment #7) The licensee shall complete construction of the deferred shield walls and window as identified in Attachment 3, as amended by this license amendment. (12) Deleted. (13) Deleted. (14) Fire Protection Proqram (Generic Letter 86-10) The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in Section 9.5.1 and Appendix F of the Final Safety Analysis Report (FSAR) for the facility thru Amendment #39 and as described in subsequent letters to the staff through November 30, 1988, referenced in the May 22, 1989 safety evaluation and in other pertinent sections of the FSAR referenced in either Section 9.5.1 or Appendix F and as approved in the Safety Evaluation Report issued in March 1982 (NUREG 0892) and in Supplements 3, issued in May 1983, and 4, issued in December 1983, and in safety evaluations issued with letters dated November 11, 1987 and May 22, 1989 subject to the following provision: The license may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Amendment No. 1.7.5 1-484
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS of Enclosure Page 5 of 14 6a - (15) Deleted. (16) Deleted.
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS of Enclosure Page 6 of 14 7-(17) Deleted. (18) Deleted. (19) Deleted. (20) Deleted. (21) Deleted. Amendment No. -149
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS of Enclosure Page 7 of 14 8-(22) Deleted. (23) Deleted. (24) Deleted. (25) Deleted. I
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS Aftachment 2 of Enclosure Page 8 of 14 9-(26) Deleted. (27) Deleted. (28) Deleted. (29) Protection of the Environment (FES) Before engaging in additional construction or operational activities which may result in a significant adverse environmental impact that was not evaluated or that is significantly greater than the evaluation in the Final Environmental Statement the licensee shall provide a written notification to the Director of the Office of Nuclear Reactor Regulation and receive written approval from that office before proceeding with such activities. (30) Deleted. Amendment No. 149,151,153, 157 XXX
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS of Enclosure Page 9 of 14 Attachment 1 Deleted Amendment No. 157
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS of Enclosure Page 10 of 14 Attachment 2 Deleted
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS of Enclosure ATTACHMENT 3 Page 11 of 14 LIST OF SHIELD WALLS
- 1. Deleted.
- 2. Deleted.
- 3. Deleted.
- 4. Deleted.
FSAR Figure 12.3-12, Zone G-9 The access blockout to the duplicate centrifuge room.
- '6. FSAR Figure 12.3-12, Zone F-9 Same as above for the duplicate centrifuge.
- '7. FSAR Figure 12.3-13, Zone J-5 The blockout for one of the two decon concentrators.
FSAR Figure 12.3-11, Zone D-8 The two block walls at the north end of the truck loading bay.
- '9. FSAR Figure 12.3-11, Zone E-8 The leaded glass viewing window in the radwaste area.
- Shield walls and window identified in items 5, 6, 7, 8, and 9 will be installed if the associated radiation levels at these locations exceed 2.5mR/hr as dictated by the ongoing ALARA reviews.
Amendment No. XXX
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS of Enclosure Page 12 of 14 APPENDIX B TO FACILITY OPERATING LICENSE NO. NPF-21 ENERGY NORTHWEST COLUMBIA GENERATING STATION I DOCKET NO. 50-397 ENVIRONMENTAL PROTECTION PLAN (NONRADIOLOGICAL)
-69 Amendment No. !S,
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS-Aftachment 2 of Enclosure Page 13 of 14 significant increase in any adverse environmental impact previously evaluated in the FES-OL, environmental impact appraisals, or in any decisions of the Atomic Safety and Licensing Board; or (2) a significant change in effluents or power level or (3) a matter, not previously reviewed and evaluated in the documents specified in (1) of this Subsection, which may have a significant adverse environmental impact. The licensee shall maintain records of changes in facility design or operation and of tests and experiments carried out pursuant to this Subsection. These records shall include written evaluations which provide bases for the determination that the change, test, or experiment does not involve an unreviewed environmental question or constitute a decrease in the effectiveness of this EPP to meet the objectives specified in Section 1.0. The licensee shall include as part of its Annual Environmental Operating Report (per Subsection 5.4.1) brief descriptions, analyses, interpretations, and evaluations of such changes, tests and experiments. 3.2 Reporting Related to the NPDES Permit and State Certification Changes to, or renewals of, the NPDES Permit or the State certification shall be reported to the NRC within 30 days following the date the change or renewal is approved. If a permit or certification, in part or in its entirety, is appealed and stayed, the NRC shall be notified within 30 days following the date the stay is granted. 3-2
LICENSE AMENDMENT REQUEST TO DELETE OBSOLETE LICENSE CONDITIONS of Enclosure Page 14 of 14 Appendix C Deleted Amendment No. 149.41 147}}