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| {{#Wiki_filter:.-AC~CELERATED DI UTION DEMON TION SYSIKM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9002160067 DOC.DATE: 90/02/05 NOTARIZED: | | {{#Wiki_filter:.- |
| YES FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION SORENSEN,G.C. | | AC~CELERATED DI UTION DEMON TION SYSIKM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)DOCKET g 05000397 | | ACCESSION NBR:9002160067 DOC.DATE: 90/02/05 NOTARIZED: YES DOCKET g FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION SORENSEN,G.C. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application for amend to License NPF-21,requestin DG test schedule of Table 4.8.1.1.2-1 be revised,per GL 84-15.DISTRIBUTION CODE A050D COPIES RECEIVED LTR ENCL SIZE: TITLE: OR Submittal: | | Application for amend to License NPF-21,requestin DG test schedule of Table 4.8.1.1.2-1 be revised,per GL 84-15. |
| Station Blackout (USI A-44)10CFR50.63, MPA A-2 NOTES: D RECIPIENT ID CODE/NAME PD5 PD INTERNAL: ACRS NRR/DET/ESGB 8D/SRXB8E REG FIVE 0 1 EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME SAMWORTH,R'RR PD1-4PM TAM NRR/DST/SPLB8D1 NUDOCS-ABSTRACT NRC PDR COPIES , LTTR ENCL 1 1 1'2.2 1 1 1 1 A R'NOTE TO ALL"RIDS" RECIPIENIS: | | DISTRIBUTION CODE A050D COPIES RECEIVED LTR ENCL SIZE: D TITLE: OR Submittal: Station Blackout (USI A-44) 10CFR50.63, MPA A- 2 NOTES: |
| PLEASE HELP US TO REDUCE WASIZl CONTACI'HE. | | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME , LTTR ENCL A PD5 PD 1 1 SAMWORTH,R'RR 1 1 |
| DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISIRIBUTION LISIS FOR DOCUMENIS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 14 D D 0 ,<~~C't 1 I~U WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Richland, Washington 99352 February 5, 1990 G02-90-019 Docket No.50-397 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen: | | ' |
| | INTERNAL: ACRS 1 1 PD1-4PM TAM 1 NRR/DET/ESGB 8D 2 2 NRR/DST/SPLB8D1 2 2 |
| | / SRXB8E0 1 REG FIVE 1 |
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| | 1 NUDOCS-ABSTRACT 1 |
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| | 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 R |
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| | NOTE TO ALL "RIDS" RECIPIENIS: |
| | PLEASE HELP US TO REDUCE WASIZl CONTACI'HE.DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISIRIBUTION LISIS FOR DOCUMENIS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 14 |
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| | WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 February 5, 1990 G02-90-019 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen: |
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| ==Subject:== | | ==Subject:== |
| NUCLEAR PLANT NO.2, OPERATING LICENSE NPF-21 RE(VEST FOR AMENDMENT TO TECHNICAL SPECIFICATION TABLE 4.8.1.1.2-1, DIESEL GENERATOR TEST SCHEDULE PER GENERIC LETTER 84-15 | | NUCLEAR PLANT NO. 2, OPERATING LICENSE NPF-21 RE(VEST FOR AMENDMENT TO TECHNICAL SPECIFICATION TABLE 4.8.1.1.2-1, DIESEL GENERATOR TEST SCHEDULE PER GENERIC LETTER 84-15 |
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| ==Reference:== | | ==Reference:== |
| | Letter, GC Sorensen (SS) to NRC, "Response to Station Blackout Rule", dated April 17, 1989 In accordance with the Code of Federal Regulations, Title 10 Parts 50.90 and |
| | : 2. 101, the Supply System hereby submits a request for amendment to the WNP-2 Technical Specifications. Specifically, the Supply System is requesting the diesel generator (DG) test schedule of Table 4.8. 1. 1.2-1 be revised consistent with that recommended in Generic Letter (GL) 84-15. |
| | On July 2, 1984, the NRC issued Generic Letter 84-15 (Proposed Staff Action to Improve and Maintain Diesel Generator Reliability). This Generic Letter presented the conclusion that the frequency of diesel generator start surveil-lance tests should be reduced to prevent premature diesel engine degradation, and encouraged licensees to submit changes to their Technical Specifications to accomplish a reduction in the number of DG surveillance tests. The Staff provided an example surveillance testing frequency in proposed Table 4.8. 1 Diesel Generator Test Schedule, attached to the Generic Letter. This proposed example test frequency table has been approved by the NRC on many recent docket actions. |
| | Diesel Generators are assumed to be available to respond to analyzed accidents. |
| | To ensure that DGs are capable to perform as they were designed, they must be tested on a routine basis. However, when the testing becomes excessive the tests themselves can lead to excessive wear and excessive periods when a DG is not in its normal standby ready status, and therefore, be a significant source of reduced reliability and availability. The proposed changes to the WNP-2 Technical Specifications provide for an increased number of valid test failures before increasing the test frequency, yet support, and are consistent with the Supply System DG target reliability goal of 0.95 (Reference). These changes are also consistent with the reliability goal stated in GL 84-15 and NUMARC 87-00. |
| | 67 90020397 900216p9 OCK 050 PGC |
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| | Page .Two 0 |
| | REQUEST FOR AMEND. TO TS TABLE 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE PER GL 84-15 The Supply System has made changes to improve the reliability and minimize mechanical stress and wear on the DGs. A slow start capability has been added so that the DGs can be started slowly and warmed up in accordance with the manufacturer's recommended procedures prior to loading. A recent design modification replaced coil relays with solid state relays in the voltage sensing/regulator circuitry and output breaker closing logic circuitry to improve the reliability of these circuits. And with the slow start capability described above, based on a state of the art electrical governor replacement, the governor control was changed to reverse acting so that on" failure of the electrical governor the mechanical governor assumes control. In keeping with the goal to minimize mechanical stress and wear on the DGs the following changes are requested to further enhance DG reliability and availability. |
| | The first proposed change is to view the reliability goal on a per-DG basis as opposed to a per-nuclear-unit-basis. The primary purpose is to avoid increased testing of all DGs due to failures experienced on only one DG, and to increase testing on a DG whose reliability, may be degrading based on its performance rather than waiting for the overall facility reliability to decrease. This ensures that DGs experiencing failures receive attention and remedial than those DGs with high reliability and that those with high reliability actions'ooner are not tested to excess. |
| | The second change is to add test frequency criteria based on the number of failures in the last 20 valid tests. The test interval is proposed to be 31 days when less than or equal to 1 DG failure occurred in the last 20 valid tests. |
| | The 7 day test interval is proposed to be based on greater than 1 failure in the last 20 valid tests. This supports the above mentioned reliability goal of 0.95. |
| | Two failures in 20 demands is a failure rate of 0. 1 which is at the threshold of acceptable diesel generator performance, and may be an early indication of degradation of the reliability, of a DG. However, when considered in a long run of demands, two failures in the last 20 demands may only be a statistically probable distribution of two random events. Hence two failures invoke a 7 day test frequency until the reliability is proven to be greater than or equal to 0.95 and the 31 day test frequency can be resumed. Consistent with this, the criteria for increased testing based on the last 100 valid tests is changed to less than or equal to 4 failures for the 31 day interval, and greater than 4 failures for the 7 day interval. Again, this supports the 0.95 target reliability goal. |
| | The next change is to delete the DG test frequency intervals of 14 days and 3 days invoked at 2 or 3 failures in 100 demands. Both of these represent failure rates more conservative than the target reliability goal of the Supply System, the Generic Letter, and NUMARC 87-00. As such they would cause excessive testing that is not justified. The 14 day test interval is not necessary due to the additional testing required on a 7 day interval if the failures exceed 1 in the last 20 valid starts. The 3 day test interval represents potentially excessive testing which could lead to premature DG degradation. |
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| | RE(UEST FOR AMEND TO TS TABLE 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE PER GL 84-15 The final change will require that once two or more failures in the last 20 starts occur the 7 day test interval is required. Seven consecutive failure free valid tests will be required prior to returning to the 31 day test interval (in addition to meeting the other requirements for returning to the 31 day test interval). This maintains an acceptable level of reliability. |
| | These revised test frequencies are in accordance with GL 84-15 (which includes the 20 valid test criteria based on a reliability goal of 0.95), and are consistent with recent changes approved on other dockets (i.e., Grand Gulf-8/1/88). |
| | The Supply System has evaluated this amendment request per 10CFR 50.92 and determined that it does not represent an unreviewed safety question or a significant hazard because it does not: |
| | : 1) Involve a significant increase in the probability or consequences of an accident previously evaluated. |
| | The DGs are not assumed to be involved in the initiation of any accident previously analyzed. The requirements for DG operability, their mode of operation and design, remain unchanged by this amendment request such that the assumptions made in accident analyses for the DG response are maintained. Therefore this change, which affects only the frequency of routine testing of the DGs, can not involve an increase in the probability or consequences of an accident previously evaluated. |
| | : 2) Create the possibility of a new or different kind of accident from any accident previously evaluated. |
| | Since the DGs design, intended function and mode of operation remain unchanged, this request cannot create the possibility of a new and different kind of accident from any accident previously evaluated. |
| | : 3) Involve a significant reduction in a margin of safety. |
| | The NRC concluded in GL 84-15 that excessive testing results in degradation of DGs. Any potential adverse affect of reduced testing at a time when a DG failure may occur is judged to be offset by the improvement in reliability gained from reduced testing, and consistent with the GL 84-15 recommendation conclusions, these changes will not involve a significant reduction in a margin of safety. |
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| | Page Four REQUEST FOR AMEND TO TS TABLE 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE PER GL 84-15 As discussed above, the Supply System considers that this change does not involve a significant hazards consideration, nor is there a potential for significant change in the types or significant increase in the amount of any effluents that may be released offsite, nor does it involve a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 1OCFR 51.22(c)(9) and therefore, per lOCFR 51.22(b), an environmental assessment of the change is not required. |
| | This Technical Specification change has been reviewed and approved by the WNP-2 Plant Operations Committee (POC) and the Supply System Corporate Nuclear Safety Review Board (CNSRB). In accordance with lOCFR 50.91, the State of Washington has been provided a copy of this letter. |
| | Very truly yours, 4 |
| | G. C. Sorensen, Manager Regulatory Programs PLP/bk Attachments cc: JB Martin - NRC RV NS Reynolds - BCP&R RB Samworth - NRC DL Williams - BPA/399 NRC Site Inspector - 901A C Eschels - EFSEC |
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| Letter, GC Sorensen (SS)to NRC,"Response to Station Blackout Rule", dated April 17, 1989 In accordance with the Code of Federal Regulations, Title 10 Parts 50.90 and 2.101, the Supply System hereby submits a request for amendment to the WNP-2 Technical Specifications.
| | Request for Amend to TS 4.8.1.1.2-1 STATE OF WASHINGTON ) |
| Specifically, the Supply System is requesting the diesel generator (DG)test schedule of Table 4.8.1.1.2-1 be revised consistent with that recommended in Generic Letter (GL)84-15.On July 2, 1984, the NRC issued Generic Letter 84-15 (Proposed Staff Action to Improve and Maintain Diesel Generator Reliability).
| |
| This Generic Letter presented the conclusion that the frequency of diesel generator start surveil-lance tests should be reduced to prevent premature diesel engine degradation, and encouraged licensees to submit changes to their Technical Specifications to accomplish a reduction in the number of DG surveillance tests.The Staff provided an example surveillance testing frequency in proposed Table 4.8.1 Diesel Generator Test Schedule, attached to the Generic Letter.This proposed example test frequency table has been approved by the NRC on many recent docket actions.Diesel Generators are assumed to be available to respond to analyzed accidents.
| |
| To ensure that DGs are capable to perform as they were designed, they must be tested on a routine basis.However, when the testing becomes excessive the tests themselves can lead to excessive wear and excessive periods when a DG is not in its normal standby ready status, and therefore, be a significant source of reduced reliability and availability.
| |
| The proposed changes to the WNP-2 Technical Specifications provide for an increased number of valid test failures before increasing the test frequency, yet support, and are consistent with the Supply System DG target reliability goal of 0.95 (Reference).
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| These changes are also consistent with the reliability goal stated in GL 84-15 and NUMARC 87-00.67 90020397 900216 OCK 050 PGC p9
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| ~~j h Page.Two REQUEST FOR AMEND.TO TS TABLE 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE PER GL 84-15 0 The Supply System has made changes to improve the reliability and minimize mechanical stress and wear on the DGs.A slow start capability has been added so that the DGs can be started slowly and warmed up in accordance with the manufacturer's recommended procedures prior to loading.A recent design modification replaced coil relays with solid state relays in the voltage sensing/regulator circuitry and output breaker closing logic circuitry to improve the reliability of these circuits.And with the slow start capability described above, based on a state of the art electrical governor replacement, the governor control was changed to reverse acting so that on" failure of the electrical governor the mechanical governor assumes control.In keeping with the goal to minimize mechanical stress and wear on the DGs the following changes are requested to further enhance DG reliability and availability.
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| The first proposed change is to view the reliability goal on a per-DG basis as opposed to a per-nuclear-unit-basis.
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| The primary purpose is to avoid increased testing of all DGs due to failures experienced on only one DG, and to increase testing on a DG whose reliability, may be degrading based on its performance rather than waiting for the overall facility reliability to decrease.This ensures that DGs experiencing failures receive attention and remedial actions'ooner than those DGs with high reliability and that those with high reliability are not tested to excess.The second change is to add test frequency criteria based on the number of failures in the last 20 valid tests.The test interval is proposed to be 31 days when less than or equal to 1 DG failure occurred in the last 20 valid tests.The 7 day test interval is proposed to be based on greater than 1 failure in the last 20 valid tests.This supports the above mentioned reliability goal of 0.95.Two failures in 20 demands is a failure rate of 0.1 which is at the threshold of acceptable diesel generator performance, and may be an early indication of degradation of the reliability, of a DG.However, when considered in a long run of demands, two failures in the last 20 demands may only be a statistically probable distribution of two random events.Hence two failures invoke a 7 day test frequency until the reliability is proven to be greater than or equal to 0.95 and the 31 day test frequency can be resumed.Consistent with this, the criteria for increased testing based on the last 100 valid tests is changed to less than or equal to 4 failures for the 31 day interval, and greater than 4 failures for the 7 day interval.Again, this supports the 0.95 target reliability goal.The next change is to delete the DG test frequency intervals of 14 days and 3 days invoked at 2 or 3 failures in 100 demands.Both of these represent failure rates more conservative than the target reliability goal of the Supply System, the Generic Letter, and NUMARC 87-00.As such they would cause excessive testing that is not justified.
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| The 14 day test interval is not necessary due to the additional testing required on a 7 day interval if the failures exceed 1 in the last 20 valid starts.The 3 day test interval represents potentially excessive testing which could lead to premature DG degradation.
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| ~~P t Page Three.RE(UEST FOR AMEND TO TS TABLE 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE PER GL 84-15 The final change will require that once two or more failures in the last 20 starts occur the 7 day test interval is required.Seven consecutive failure free valid tests will be required prior to returning to the 31 day test interval (in addition to meeting the other requirements for returning to the 31 day test interval).
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| This maintains an acceptable level of reliability.
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| These revised test frequencies are in accordance with GL 84-15 (which includes the 20 valid test criteria based on a reliability goal of 0.95), and are consistent with recent changes approved on other dockets (i.e., Grand Gulf-8/1/88).The Supply System has evaluated this amendment request per 10CFR 50.92 and determined that it does not represent an unreviewed safety question or a significant hazard because it does not: 1)Involve a significant increase in the probability or consequences of an accident previously evaluated.
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| The DGs are not assumed to be involved in the initi ation of any accident previously analyzed.The requirements for DG operability, their mode of operation and design, remain unchanged by this amendment request such that the assumptions made in accident analyses for the DG response are maintained.
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| Therefore this change, which affects only the frequency of routine testing of the DGs, can not involve an increase in the probability or consequences of an accident previously evaluated.
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| 2)Create the possibility of a new or different kind of accident from any accident previously evaluated.
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| Since the DGs design, intended function and mode of operation remain unchanged, this request cannot create the possibility of a new and different kind of accident from any accident previously evaluated.
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| 3)Involve a significant reduction in a margin of safety.The NRC concluded in GL 84-15 that excessive testing results in degradation of DGs.Any potential adverse affect of reduced testing at a time when a DG failure may occur is judged to be offset by the improvement in reliability gained from reduced testing, and consistent with the GL 84-15 recommendation conclusions, these changes will not involve a significant reduction in a margin of safety.
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| Page Four REQUEST FOR AMEND TO TS TABLE 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE PER GL 84-15 As discussed above, the Supply System considers that this change does not involve a significant hazards consideration, nor is there a potential for significant change in the types or significant increase in the amount of any effluents that may be released offsite, nor does it involve a significant increase in individual or cumulative occupational radiation exposure.Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 1OCFR 51.22(c)(9) and therefore, per lOCFR 51.22(b), an environmental assessment of the change is not required.This Technical Specification change has been reviewed and approved by the WNP-2 Plant Operations Committee (POC)and the Supply System Corporate Nuclear Safety Review Board (CNSRB).In accordance with lOCFR 50.91, the State of Washington has been provided a copy of this letter.Very truly yours, 4 G.C.Sorensen, Manager Regulatory Programs PLP/bk Attachments cc: JB Martin-NRC RV NS Reynolds-BCP&R RB Samworth-NRC DL Williams-BPA/399 NRC Site Inspector-901A C Eschels-EFSEC
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| ~E l J' STATE OF WASHINGTON
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| ))COUNTY OF BENTON)Request for Amend to TS 4.8.1.1.2-1 | |
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| ==Subject:== | | ==Subject:== |
| DG T Sch dule I, G.C.SORENSEN, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein;that I have full authority to execute this oath;that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.DATE , 1990 G.C.SO N, Manager Regulatory Programs On this day personally appeared before me G.C.SORENSEN to me known to be the individual who executed the foregoing instr ument and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned. | | DG T Sch dule |
| GIVEN under my hand and seal this day of ,1990.o ary Pu ic in and or t e State of Washington Residing at 1 C-/J}} | | ) |
| | COUNTY OF BENTON ) |
| | I, G. C. SORENSEN, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true. |
| | DATE , 1990 G. C. SO N, Manager Regulatory Programs On this day personally appeared before me G. C. SORENSEN to me known to be the individual who executed the foregoing instr ument and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned. |
| | GIVEN under my hand and seal this day of ,1990. |
| | o ary Pu ic in and or t e State of Washington Residing at |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17284A9101999-10-13013 October 1999 Application for Amend to License NPF-21,revising TS 3.3.6.1, Table 3.3.6.1-1, Primary Containment Isolation Instrumentation. Footnote (D) Is Removed Since Both Inboard & Outboard Trip Sys Are Now Functional in All Modes ML17284A8501999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17284A8471999-07-29029 July 1999 Application for Amend to License NPF-21,revising Tech Specs SR 3.5.2.2, Condensate Storage Tank Water Level. ML17284A8441999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a. ML17284A8431999-07-29029 July 1999 Application for Amend to License NPF-21,removing License Condition 2.C.(16),Attachment 2,Item 3(b) Re post-accident Neutron Flux Monitoring ML17284A8401999-07-29029 July 1999 Application for Amend to License NPF-21,amending Tech Specs SR 3.8.4.6 of TS 3.8.5, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17292B6891999-06-0303 June 1999 Application for Amend to License NPF-21,reflecting Change in Name of Washington Public Power Supply Sys to Energy Northwest.Marked-up Copy of Affected Pages of OL for Plant, Encl ML17292B6441999-04-20020 April 1999 Application for Amend to License NPF-21,revising TS 3.4.11 to Replace Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6321999-04-0707 April 1999 Application for Amend to License NPF-21,requesting Mod to MCPR Safety Limits by 990930 to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B4861998-12-17017 December 1998 Application for Amend to License NPF-21,revising TS SR 3.8.1.8 to Allow for Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML17284A8071998-11-0909 November 1998 Supplemental Application for Amend to License NPF-21, Requesting Minor Wording Changes to Clarify Intent of Proposed New License Section 2.B.(6).Addl Info That Describes Physical Storage of Matls,Encl ML17284A7161998-08-0505 August 1998 Application for Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7051998-07-17017 July 1998 Application for Exigent Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc, Battery E-B1-2 ML17292B3401998-04-16016 April 1998 Application for Amend to License NPF-21,modifying Requirement That cold-worked Austenitic Stainless Steel Used in Newly Designed ECCS Pump Suction Strainers Must Have Yield Strength Not Greater than 90,000 Psi ML17292B1301997-12-0404 December 1997 Application for Amend to License NPF-21,modifying Min Critical Power Ratio Safety Limits by 980515 to Allow Continued Power Operation at WNP-2 Following Restart from R-13 Refueling Outage ML17292B0261997-08-14014 August 1997 Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line ML17292A9401997-07-16016 July 1997 Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing ML17292A8631997-05-20020 May 1997 Application for Amend to License NPF-21,requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A7561997-03-22022 March 1997 Application for Amend to License NPF-21,modifying Response Time Testing Surveillance Requirements for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A5491996-10-15015 October 1996 Application for Amend to License NPF-21 to Modify TS for Secondary Containment & Standby Gas Treatment Sys to Reflect Revised Secondary Containment Drawdown & post-accident Analyses Results.Affidavit,Encl ML17292A5381996-10-10010 October 1996 Application for Amend to License NPF-21,requesting Addition of Section 2B(6) Re Allowance of Storage of Byproduct, Source & Special Nuclear Materials ML17292A4081996-08-0909 August 1996 Requests Amend to License NPF-21,revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 GO2-96-089, Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage1996-04-24024 April 1996 Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage ML17291B2781996-03-19019 March 1996 Application for Amend to License NPF-21,revising Containment Leakage Testing ML17291B2071996-01-19019 January 1996 Application for Amend to License NPF-21 Re Primary Containment Leakage Testing GO2-95-265, Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC1995-12-0808 December 1995 Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC ML17291B0921995-10-26026 October 1995 Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A8421995-06-0606 June 1995 Application for Amend to License NPF-21,changing TS 6.0, Administrative Controls by Revising Assistant Managing Director,Operations & Plant Manager Position Titles ML17291A8381995-06-0606 June 1995 Application for Amend to License NPF-21,modifying Index of TS by Deleting Ref to Bases Pages.Future Changes to Bases Info Will Be Evaluated Per 10CFR50.59 ML17291A8321995-06-0606 June 1995 Application for Amend to License NPF-21,modifying TS 6.9.3.2 by Adding Re to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications,Consistent W/Gl 88-16 ML17291A7551995-04-25025 April 1995 Application for Amend to License NPF-21,adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1 ML17291A4791994-10-31031 October 1994 Application for Amend to License NPF-21,revising TSs to Relocate Safety/Relief Valve Position Indication Instrumentation Requirements ML17291A4741994-10-31031 October 1994 Application for Amend to License NPF-21,revising TS 3/4.1.3.1, Reactivity Control Sys. ML17291A4201994-09-26026 September 1994 Suppl to 930709 Application for Amend to License NPF-21 Re Increase in Power Operation,Changing Power/Flow Maps in TS 3/4.2.6,3/4.2.7,3/4.2.8 & 3/4.4.1 & Bases to Reflect Use of Siemens Power Corp Staif Code for Stability Analysis ML17291A3941994-09-18018 September 1994 Application for Amend to License NPF-21,changing TS Table 3.6.3-1 Re Primary Containment Isolation Valve Requirements ML17291A3171994-08-0808 August 1994 Application for Amend to License NPF-21,amending TS 4.0.5, Surveillance Requirements for Inservice Insp & Testing Program. ML17291A2151994-07-12012 July 1994 Application for Amend to License NPF-21,requesting Amend to Ts,Relocating TS Table for Instrument Response Time Limits ML17291A2201994-07-0808 July 1994 Application for Amend to License NPF-21,revising TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances ML17290B1711994-05-0606 May 1994 Application for Amend to License NPF-21,revising TSs 3/4.3.7.5,3/4.4.2 & 3/4.5.1 for Main Steam Relief Valve Position Indication ML17290B1551994-05-0505 May 1994 Application for Amend to License NPF-21,requesting Mod of Three Equipment Piece Numbers Included in Table 3.6.3-1, Primary Containment Isolation Valves. ML17290A9631994-02-17017 February 1994 Application for Amend to License NPF-21,revising TS to Support Hydrostatic Testing ML17290A9601994-02-17017 February 1994 Application for Amend to License NPF-21,revising TS Section 6.0, Administrative Controls, Including Changing Reporting Relationship for QA Functions in Section 6.2.1.e of TS from Managing Director to Assistant Managing Director,Operations ML17290A9551994-02-0808 February 1994 Application for Amend to License NPF-21,consisting of Changes to TS Table 3.6.3-1,for RCIC-V-8,increasing Stroke Time from 13 Seconds to 26 Seconds & Deleting Note (J) Reference from RCIC-V-8 & RCIC-V-63 ML17290A9031994-01-13013 January 1994 Application for Amend to License NPF-21,requesting Continued Plant Operation W/Eccs Functional,But Not in Strict Compliance W/Requirements for Demonstrating That Response Time within Limits of TS 3/4.3.3, ECCS Instrumentation. ML17290A8961994-01-0606 January 1994 Application for Amend to License NPF-21,requesting Changes to TS to Clarify Instrumentation Testing Requirements ML17290A8781994-01-0606 January 1994 Application for Amend to License NPF-21,requesting Rev to TS to Relocate Requirements for Seismic Monitoring Instrumentation to FSAR & Plant Procedures ML17290A8921994-01-0606 January 1994 Suppl to 930709 Application for Amend to License NPF-21, Increasing Licensed Power Level from 3,323 Mwt to 3,486 Mwt W/Extended Load Line Limit & Changing SRV Setpoint Tolerance to Include Changes to TS Paragraph 6.9.3.2 ML17290A8391993-12-20020 December 1993 Application for Amend to License NPF-21,revising TS 3/4.6.1.8, Drywell & Suppression Chamber Purge Sys. ML17290A8181993-12-0606 December 1993 Application for Amend to License NPF-21,requesting TS Surveillance Requirement 4.6.6.1.b.3 Be Revised to Provide Appropriate Acceptance Criteria for Demonstrating Operability of Primary Containment Hydrogen Recombiner Sys ML17290A8221993-12-0606 December 1993 Application for Amend to License NPF-21,adding Footnote to TS Table 4.3.7.5-1, Accident Monitoring Instrumentation Srs, Exempting Channel Calibr of Safety/Relief Valve Position Indicators from Spec 4.0.4 for 24 H 1999-07-29
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17284A9101999-10-13013 October 1999 Application for Amend to License NPF-21,revising TS 3.3.6.1, Table 3.3.6.1-1, Primary Containment Isolation Instrumentation. Footnote (D) Is Removed Since Both Inboard & Outboard Trip Sys Are Now Functional in All Modes ML17284A8501999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17284A8471999-07-29029 July 1999 Application for Amend to License NPF-21,revising Tech Specs SR 3.5.2.2, Condensate Storage Tank Water Level. ML17284A8441999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a. ML17284A8431999-07-29029 July 1999 Application for Amend to License NPF-21,removing License Condition 2.C.(16),Attachment 2,Item 3(b) Re post-accident Neutron Flux Monitoring ML17284A8401999-07-29029 July 1999 Application for Amend to License NPF-21,amending Tech Specs SR 3.8.4.6 of TS 3.8.5, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17292B6891999-06-0303 June 1999 Application for Amend to License NPF-21,reflecting Change in Name of Washington Public Power Supply Sys to Energy Northwest.Marked-up Copy of Affected Pages of OL for Plant, Encl ML17292B6441999-04-20020 April 1999 Application for Amend to License NPF-21,revising TS 3.4.11 to Replace Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6321999-04-0707 April 1999 Application for Amend to License NPF-21,requesting Mod to MCPR Safety Limits by 990930 to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B4861998-12-17017 December 1998 Application for Amend to License NPF-21,revising TS SR 3.8.1.8 to Allow for Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML17284A8071998-11-0909 November 1998 Supplemental Application for Amend to License NPF-21, Requesting Minor Wording Changes to Clarify Intent of Proposed New License Section 2.B.(6).Addl Info That Describes Physical Storage of Matls,Encl ML17284A7161998-08-0505 August 1998 Application for Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7051998-07-17017 July 1998 Application for Exigent Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc, Battery E-B1-2 ML17292B3401998-04-16016 April 1998 Application for Amend to License NPF-21,modifying Requirement That cold-worked Austenitic Stainless Steel Used in Newly Designed ECCS Pump Suction Strainers Must Have Yield Strength Not Greater than 90,000 Psi ML17292B1301997-12-0404 December 1997 Application for Amend to License NPF-21,modifying Min Critical Power Ratio Safety Limits by 980515 to Allow Continued Power Operation at WNP-2 Following Restart from R-13 Refueling Outage ML17292B0261997-08-14014 August 1997 Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line ML17292A9401997-07-16016 July 1997 Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing ML17292A8631997-05-20020 May 1997 Application for Amend to License NPF-21,requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A7561997-03-22022 March 1997 Application for Amend to License NPF-21,modifying Response Time Testing Surveillance Requirements for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A5491996-10-15015 October 1996 Application for Amend to License NPF-21 to Modify TS for Secondary Containment & Standby Gas Treatment Sys to Reflect Revised Secondary Containment Drawdown & post-accident Analyses Results.Affidavit,Encl ML17292A5381996-10-10010 October 1996 Application for Amend to License NPF-21,requesting Addition of Section 2B(6) Re Allowance of Storage of Byproduct, Source & Special Nuclear Materials ML17292A4081996-08-0909 August 1996 Requests Amend to License NPF-21,revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 GO2-96-089, Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage1996-04-24024 April 1996 Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage ML17291B2781996-03-19019 March 1996 Application for Amend to License NPF-21,revising Containment Leakage Testing ML17291B2071996-01-19019 January 1996 Application for Amend to License NPF-21 Re Primary Containment Leakage Testing GO2-95-265, Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC1995-12-0808 December 1995 Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC ML17291B0921995-10-26026 October 1995 Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A8421995-06-0606 June 1995 Application for Amend to License NPF-21,changing TS 6.0, Administrative Controls by Revising Assistant Managing Director,Operations & Plant Manager Position Titles ML17291A8381995-06-0606 June 1995 Application for Amend to License NPF-21,modifying Index of TS by Deleting Ref to Bases Pages.Future Changes to Bases Info Will Be Evaluated Per 10CFR50.59 ML17291A8321995-06-0606 June 1995 Application for Amend to License NPF-21,modifying TS 6.9.3.2 by Adding Re to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications,Consistent W/Gl 88-16 ML17291A7551995-04-25025 April 1995 Application for Amend to License NPF-21,adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1 ML17291A4791994-10-31031 October 1994 Application for Amend to License NPF-21,revising TSs to Relocate Safety/Relief Valve Position Indication Instrumentation Requirements ML17291A4741994-10-31031 October 1994 Application for Amend to License NPF-21,revising TS 3/4.1.3.1, Reactivity Control Sys. ML17291A4201994-09-26026 September 1994 Suppl to 930709 Application for Amend to License NPF-21 Re Increase in Power Operation,Changing Power/Flow Maps in TS 3/4.2.6,3/4.2.7,3/4.2.8 & 3/4.4.1 & Bases to Reflect Use of Siemens Power Corp Staif Code for Stability Analysis ML17291A3941994-09-18018 September 1994 Application for Amend to License NPF-21,changing TS Table 3.6.3-1 Re Primary Containment Isolation Valve Requirements ML17291A3171994-08-0808 August 1994 Application for Amend to License NPF-21,amending TS 4.0.5, Surveillance Requirements for Inservice Insp & Testing Program. ML17291A2151994-07-12012 July 1994 Application for Amend to License NPF-21,requesting Amend to Ts,Relocating TS Table for Instrument Response Time Limits ML17291A2201994-07-0808 July 1994 Application for Amend to License NPF-21,revising TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances ML17290B1711994-05-0606 May 1994 Application for Amend to License NPF-21,revising TSs 3/4.3.7.5,3/4.4.2 & 3/4.5.1 for Main Steam Relief Valve Position Indication ML17290B1551994-05-0505 May 1994 Application for Amend to License NPF-21,requesting Mod of Three Equipment Piece Numbers Included in Table 3.6.3-1, Primary Containment Isolation Valves. ML17290A9631994-02-17017 February 1994 Application for Amend to License NPF-21,revising TS to Support Hydrostatic Testing ML17290A9601994-02-17017 February 1994 Application for Amend to License NPF-21,revising TS Section 6.0, Administrative Controls, Including Changing Reporting Relationship for QA Functions in Section 6.2.1.e of TS from Managing Director to Assistant Managing Director,Operations ML17290A9551994-02-0808 February 1994 Application for Amend to License NPF-21,consisting of Changes to TS Table 3.6.3-1,for RCIC-V-8,increasing Stroke Time from 13 Seconds to 26 Seconds & Deleting Note (J) Reference from RCIC-V-8 & RCIC-V-63 ML17290A9031994-01-13013 January 1994 Application for Amend to License NPF-21,requesting Continued Plant Operation W/Eccs Functional,But Not in Strict Compliance W/Requirements for Demonstrating That Response Time within Limits of TS 3/4.3.3, ECCS Instrumentation. ML17290A8961994-01-0606 January 1994 Application for Amend to License NPF-21,requesting Changes to TS to Clarify Instrumentation Testing Requirements ML17290A8781994-01-0606 January 1994 Application for Amend to License NPF-21,requesting Rev to TS to Relocate Requirements for Seismic Monitoring Instrumentation to FSAR & Plant Procedures ML17290A8921994-01-0606 January 1994 Suppl to 930709 Application for Amend to License NPF-21, Increasing Licensed Power Level from 3,323 Mwt to 3,486 Mwt W/Extended Load Line Limit & Changing SRV Setpoint Tolerance to Include Changes to TS Paragraph 6.9.3.2 ML17290A8391993-12-20020 December 1993 Application for Amend to License NPF-21,revising TS 3/4.6.1.8, Drywell & Suppression Chamber Purge Sys. ML17290A8181993-12-0606 December 1993 Application for Amend to License NPF-21,requesting TS Surveillance Requirement 4.6.6.1.b.3 Be Revised to Provide Appropriate Acceptance Criteria for Demonstrating Operability of Primary Containment Hydrogen Recombiner Sys ML17290A8221993-12-0606 December 1993 Application for Amend to License NPF-21,adding Footnote to TS Table 4.3.7.5-1, Accident Monitoring Instrumentation Srs, Exempting Channel Calibr of Safety/Relief Valve Position Indicators from Spec 4.0.4 for 24 H 1999-07-29
[Table view] |
Text
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AC~CELERATED DI UTION DEMON TION SYSIKM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9002160067 DOC.DATE: 90/02/05 NOTARIZED: YES DOCKET g FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION SORENSEN,G.C. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amend to License NPF-21,requestin DG test schedule of Table 4.8.1.1.2-1 be revised,per GL 84-15.
DISTRIBUTION CODE A050D COPIES RECEIVED LTR ENCL SIZE: D TITLE: OR Submittal: Station Blackout (USI A-44) 10CFR50.63, MPA A- 2 NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME , LTTR ENCL A PD5 PD 1 1 SAMWORTH,R'RR 1 1
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INTERNAL: ACRS 1 1 PD1-4PM TAM 1 NRR/DET/ESGB 8D 2 2 NRR/DST/SPLB8D1 2 2
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1 NUDOCS-ABSTRACT 1
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1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 R
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NOTE TO ALL "RIDS" RECIPIENIS:
PLEASE HELP US TO REDUCE WASIZl CONTACI'HE.DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISIRIBUTION LISIS FOR DOCUMENIS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 14
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WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 February 5, 1990 G02-90-019 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
NUCLEAR PLANT NO. 2, OPERATING LICENSE NPF-21 RE(VEST FOR AMENDMENT TO TECHNICAL SPECIFICATION TABLE 4.8.1.1.2-1, DIESEL GENERATOR TEST SCHEDULE PER GENERIC LETTER 84-15
Reference:
Letter, GC Sorensen (SS) to NRC, "Response to Station Blackout Rule", dated April 17, 1989 In accordance with the Code of Federal Regulations, Title 10 Parts 50.90 and
- 2. 101, the Supply System hereby submits a request for amendment to the WNP-2 Technical Specifications. Specifically, the Supply System is requesting the diesel generator (DG) test schedule of Table 4.8. 1. 1.2-1 be revised consistent with that recommended in Generic Letter (GL) 84-15.
On July 2, 1984, the NRC issued Generic Letter 84-15 (Proposed Staff Action to Improve and Maintain Diesel Generator Reliability). This Generic Letter presented the conclusion that the frequency of diesel generator start surveil-lance tests should be reduced to prevent premature diesel engine degradation, and encouraged licensees to submit changes to their Technical Specifications to accomplish a reduction in the number of DG surveillance tests. The Staff provided an example surveillance testing frequency in proposed Table 4.8. 1 Diesel Generator Test Schedule, attached to the Generic Letter. This proposed example test frequency table has been approved by the NRC on many recent docket actions.
Diesel Generators are assumed to be available to respond to analyzed accidents.
To ensure that DGs are capable to perform as they were designed, they must be tested on a routine basis. However, when the testing becomes excessive the tests themselves can lead to excessive wear and excessive periods when a DG is not in its normal standby ready status, and therefore, be a significant source of reduced reliability and availability. The proposed changes to the WNP-2 Technical Specifications provide for an increased number of valid test failures before increasing the test frequency, yet support, and are consistent with the Supply System DG target reliability goal of 0.95 (Reference). These changes are also consistent with the reliability goal stated in GL 84-15 and NUMARC 87-00.
67 90020397 900216p9 OCK 050 PGC
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REQUEST FOR AMEND. TO TS TABLE 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE PER GL 84-15 The Supply System has made changes to improve the reliability and minimize mechanical stress and wear on the DGs. A slow start capability has been added so that the DGs can be started slowly and warmed up in accordance with the manufacturer's recommended procedures prior to loading. A recent design modification replaced coil relays with solid state relays in the voltage sensing/regulator circuitry and output breaker closing logic circuitry to improve the reliability of these circuits. And with the slow start capability described above, based on a state of the art electrical governor replacement, the governor control was changed to reverse acting so that on" failure of the electrical governor the mechanical governor assumes control. In keeping with the goal to minimize mechanical stress and wear on the DGs the following changes are requested to further enhance DG reliability and availability.
The first proposed change is to view the reliability goal on a per-DG basis as opposed to a per-nuclear-unit-basis. The primary purpose is to avoid increased testing of all DGs due to failures experienced on only one DG, and to increase testing on a DG whose reliability, may be degrading based on its performance rather than waiting for the overall facility reliability to decrease. This ensures that DGs experiencing failures receive attention and remedial than those DGs with high reliability and that those with high reliability actions'ooner are not tested to excess.
The second change is to add test frequency criteria based on the number of failures in the last 20 valid tests. The test interval is proposed to be 31 days when less than or equal to 1 DG failure occurred in the last 20 valid tests.
The 7 day test interval is proposed to be based on greater than 1 failure in the last 20 valid tests. This supports the above mentioned reliability goal of 0.95.
Two failures in 20 demands is a failure rate of 0. 1 which is at the threshold of acceptable diesel generator performance, and may be an early indication of degradation of the reliability, of a DG. However, when considered in a long run of demands, two failures in the last 20 demands may only be a statistically probable distribution of two random events. Hence two failures invoke a 7 day test frequency until the reliability is proven to be greater than or equal to 0.95 and the 31 day test frequency can be resumed. Consistent with this, the criteria for increased testing based on the last 100 valid tests is changed to less than or equal to 4 failures for the 31 day interval, and greater than 4 failures for the 7 day interval. Again, this supports the 0.95 target reliability goal.
The next change is to delete the DG test frequency intervals of 14 days and 3 days invoked at 2 or 3 failures in 100 demands. Both of these represent failure rates more conservative than the target reliability goal of the Supply System, the Generic Letter, and NUMARC 87-00. As such they would cause excessive testing that is not justified. The 14 day test interval is not necessary due to the additional testing required on a 7 day interval if the failures exceed 1 in the last 20 valid starts. The 3 day test interval represents potentially excessive testing which could lead to premature DG degradation.
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RE(UEST FOR AMEND TO TS TABLE 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE PER GL 84-15 The final change will require that once two or more failures in the last 20 starts occur the 7 day test interval is required. Seven consecutive failure free valid tests will be required prior to returning to the 31 day test interval (in addition to meeting the other requirements for returning to the 31 day test interval). This maintains an acceptable level of reliability.
These revised test frequencies are in accordance with GL 84-15 (which includes the 20 valid test criteria based on a reliability goal of 0.95), and are consistent with recent changes approved on other dockets (i.e., Grand Gulf-8/1/88).
The Supply System has evaluated this amendment request per 10CFR 50.92 and determined that it does not represent an unreviewed safety question or a significant hazard because it does not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated.
The DGs are not assumed to be involved in the initiation of any accident previously analyzed. The requirements for DG operability, their mode of operation and design, remain unchanged by this amendment request such that the assumptions made in accident analyses for the DG response are maintained. Therefore this change, which affects only the frequency of routine testing of the DGs, can not involve an increase in the probability or consequences of an accident previously evaluated.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated.
Since the DGs design, intended function and mode of operation remain unchanged, this request cannot create the possibility of a new and different kind of accident from any accident previously evaluated.
- 3) Involve a significant reduction in a margin of safety.
The NRC concluded in GL 84-15 that excessive testing results in degradation of DGs. Any potential adverse affect of reduced testing at a time when a DG failure may occur is judged to be offset by the improvement in reliability gained from reduced testing, and consistent with the GL 84-15 recommendation conclusions, these changes will not involve a significant reduction in a margin of safety.
Page Four REQUEST FOR AMEND TO TS TABLE 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE PER GL 84-15 As discussed above, the Supply System considers that this change does not involve a significant hazards consideration, nor is there a potential for significant change in the types or significant increase in the amount of any effluents that may be released offsite, nor does it involve a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 1OCFR 51.22(c)(9) and therefore, per lOCFR 51.22(b), an environmental assessment of the change is not required.
This Technical Specification change has been reviewed and approved by the WNP-2 Plant Operations Committee (POC) and the Supply System Corporate Nuclear Safety Review Board (CNSRB). In accordance with lOCFR 50.91, the State of Washington has been provided a copy of this letter.
Very truly yours, 4
G. C. Sorensen, Manager Regulatory Programs PLP/bk Attachments cc: JB Martin - NRC RV NS Reynolds - BCP&R RB Samworth - NRC DL Williams - BPA/399 NRC Site Inspector - 901A C Eschels - EFSEC
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Request for Amend to TS 4.8.1.1.2-1 STATE OF WASHINGTON )
Subject:
DG T Sch dule
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COUNTY OF BENTON )
I, G. C. SORENSEN, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.
DATE , 1990 G. C. SO N, Manager Regulatory Programs On this day personally appeared before me G. C. SORENSEN to me known to be the individual who executed the foregoing instr ument and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned.
GIVEN under my hand and seal this day of ,1990.
o ary Pu ic in and or t e State of Washington Residing at
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