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{{#Wiki_filter:.A.CCELKRATED DI BUTfON DEMONS ON SYSTEM REGULATO INFORMATION DISTRIBUTION TEM (RIDS)ACCESSION NBR:9002220473 DOC.DATE: 90/02/07 NOTARIZED:
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NO DOCKET I FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana&05000315 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana a 05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.E.
Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
Document Control Branch (Document Control Desk)
 
==SUBJECT:==
Application for amends to Licenses DPR-58&DPR-74.Amends mod Tech Specs 4.0.2.DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL TITLE: OR Submittal:
General Distribution NOTES: SIZE: RECIPIENT ID CODE/NAME PD3-1 LA GIITTERrJ.
INTERNAL: NRR/DET/ECMB 9H NRR/DST 8E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 1 5 5 1 1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DOEA/OTSB11 NRR/DST/SELB 8D NRR/DST/SRXB 8E O~CJ EMB EG FILE NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 1 1 h NCTE IO ALL rrRZDS>>MKIPIENIS PIZASE HELP US IO REDUCE%ASTEl CGHI'ACI'IHE DOQ3MERI'XÃIBDL DESK RDCN Pl-37 (EXT.20079)IO EIiQGÃAK%3 RXHt MrrME PKH DIBTRIBUTI(W LISTS FOR DOCQMEHZS RXJ DCHIT NEEDI D D TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 19
~I El I W Indiana Michigan Power Company P.O.Box 16631 Columbus, OH 43216 AEP:NRC:1021 GL 89-14 Donald C.Cook Nuclear Plant Units 1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 GENERIC LETTER 89-14 TECHNICAL SPECIFICATION CHANGES U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Attn: T.E.Murley February 7, 1990
 
==Dear Dr.Murley:==
This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss)for the Donald CD Cook Nuclear Plant Units 1 and 2.Specifically, we propose to modify Technical Specification 4.0.2 and its associated Bases.Technical Specification 4.0.2 permits surveillance intervals to be extended up to 25 percent of the specified interval.It also limits extending surveillances so that the combined time intervals for'ny three consecutive surveillances intervals do not exceed 3.25 times the specified surveillance interval.This application for amendment proposes to delete the 3.25 extension limit in accordance with the guidance in Generic Letter 89-14,"Line Item Improvement in Technical Specifications-Removal of the 3.25 Limit on Extending Surveillance Intervals." Our reasons for the proposed changes, as well as our analyses concerning significant hazards considerations, are contained in Attachment 1 to this letter.Attachment 2 of this submittal contains proposed revised T/S pages that reflect the proposed changes.In addition, we request that the amendment be issued by September 1, 1990 and be effective immediately to prevent an unnecessary shutdown of Cook Nuclear Plant Unit 1.0ol PDR ADOCK 05000315 Dr.T.E.Murley-2-AEP:NRC'1021 We believe that the proposed changes will not result in (1)significant change in the types of effluents or a significant increase in the amounts of any effluents that may be released offsite, or (2)a significant increase in individual or cumulative occupational radiation exposure.These changes have been reviewed by the Plant Nuclear Safety Review Committee and by the Nuclear Safety and Design Review Commi.ttee.
In compliance with the requirements of 10 CFR 50.91(b)(l), copies of this letter and its attachments have been transmitted to Mr.R.C.Callen of the Michigan Public Service Commission and Mr.G.Bruchmann of the Michigan Department of Public Health.This document has been prepared following Corporate procedures that incorporates a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M P.Alexich Vice President eh Attachments cc: D.H.Williams, Jr.A.A.Blind-Bridgman R.C.Callen G.Charnoff A.B.Davis NRC Resident Inspector-Bridgman NFEM Section Chief
 
Attachment 1 to AEP:NRC:1021 Reasons and 10 CFR 50.92 Analyses for Changes to the Donald C.Cook Nuclear Plant Units 1 and 2 Technical Specifications Attachment 1 to AEP:NRC:1021 Page 1 Descri tion of Chan e As suggested in Generic Letter 89-14, this application for amendment proposes to revise Technical Specification (T/S)4.0.2 by removing the requirement that the combined time interval for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.Additionally, we are proposing to modify the associated TS Bases.Back round Technical Specification 4.0.2 permits surveillance intervals to be extended up to 25 percent of the specified interval.This exten-sion facilitates scheduling activities and allows surveillances to be postponed when plant conditions are not suitable for conducting a surveillance.
Specification 4.0.2 also limits extending surveillances so that the combined time interval for any three consecutive time.intervals shall not exceed 3.25 times the specified surveillance interval.On August 21, 1989, the NRC issued Generic Letter 89-14,"Line-Item Improvements in Technical Specifications
-Removal of the 3.25 Limit on Extending Surveillance Intervals." The Generic Letter concluded that removal of the 3.25 limit from Specification 4.0.2 results in a"greater benefit to safety than limiting the use of the 25 percent allowance to extend surveillance intervals-.
Im act on Plant 0 erations Approval of this request will provide the following benefits: 1.Facilitates scheduling of surveillance activities and allows surveillances to be postponed when plant conditions are not conducive to the safe conduct of a surveillance.
2.Reduces the potential for unnecessary forced shutdowns to perform surveillance activities.
3.Eliminates the administrative and logistical burden associated with tracking the use of the 25 percent allowance to ensure compliance with the 3.25 limit.4.Minimizes the need for surveillance interval extension amendments.
Safet Evaluation Many surveillances have a specified surveillance interval of 18 months.Generally, an 18-month surveillance interval is intended
~
Attachment 1 to AEP:NRC:1021 Page 2 to allow the surveillance to be performed when the unit's shutdown during a refueling outage.Therefore, the actual time interval for the performance of these surveillances is dependent on the length of a fuel cycle, but it cannot exceed 18 months plus the 25 percent allowance.
The safety benefit of performing these surveillances during a plant shutdown is that systems do not have to be zemoved from service at a time that they are required to be operable.,This minimizes the amount of time which systems are unavailable during power operation due to surveillance requirements, thereby minimizing the impact on safety, In a few instances, the TS specifically require some surveillances to be performed during a plant shutdown, When a limit is reached on extending an 18-month interval, a forced plant shutdown to perform these surveillances is generally the only alternative short of a license amendment that defers the performance of these surveillances until the end of a fuel cycle.Usually, the length of a fuel cycle would not exceed 18 months by more than the 25 percent allowance, i.e., 4-1/2 months, A more common situation has been to encounter the 3,25 limit on the combined time interval for three consecutive surveillance intervals.
The NRC staff has normally approved one-time amendment requests to waive the performance of 18-month surveillances until the end of the fuel cycle when they would exceed the 3.25 limitation on consecutive surveillances yet would not exceed the 25 percent allowance for extending the 18-month surveillance interval.A forced shutdown to perform these surveillances is not)ustified from a risk standpoint to avoid exceeding the 3.25 limit when extending these surveillances is within the 25 percent allowance.
The 18-month surveillances are normally performed during a refueling outage when the plant is in a desirable condition for conducting, these surveillances.
As stated in the NRC's Safety Evaluation for Commonwealth Edison's LaSalle Station, the risk of performing some of these surveillances during plant operation has been determined to be greater than the impact on safety of exceeding the 3'5 limit.In addition to its application to refueling outage surveillances, the use of the 25 percent allowance for extending surveillance intervals can provide a safety benefit when it is used during plant operation, When plant conditions are not suitable for the conduct of suzveillances due to safety systems out-of-service for" maintenance oz due to other ongoing activities, safety is enhanced by the use'f the allowance that permits a surveillance interval to be extended, In such cases, the safety benefit of extending a surveillance interval up to 25 percent would exceed the risk reduction derived by conforming to the 3.25 limitation.
, I 4I Attachment 1 to AEP:NRC:1021 Page 3 Zn summary, based on the above considerations, the removal of the 3.25 limit will have an overall positive impact on safety.Consequently, we believe there is reasonable assurance that the proposed, change will not adversely affect the health and safety of the public, Si nificant Hazards Considerations Per 10 CFR 50.92, a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not: (1)involve a significant 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, or (3)involve a significant reduction in a margin of safety.Criterion 1 Deletion of the 3.25 extension limitation will not significantly affect equipment reliability and does not affect the probability or consequences of accidents previously evaluated in the FSAR Update.The surveillance interval will still be constrained by the 25 percent interval extension criteria of T/S 4.0.2.The risk involved with the alternative to perform 18-month surveillances during plant operation is greater than the risk involved with exceeding the 3.25 limit.When plant conditions are not conducive for the safe conduct of surveillances due to safety systems being out-of-service for maintenance or due to other ongoing surveillance activities, safety is enhanced by the use of the allowance that permits a surveillance interval to be extended.Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Criterion 2 The proposed revision to the T/S will not result in any physical alteration to any plant system, nor would there be a change in the method by which any safety-related system performs its function.Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
Attachment 1 to AEP:NRC:1021 Page 4 Criterion 3 Deletion of the requirement that any three consecutive surveillance intervals shall not exceed 3.25 times the interval will not significantly affect equipment reliability, rather it will reduce the potential to interrupt normal plant operations due to surveillance scheduling, This proposed exemption will allow all surveillance intervals to be constrained by the maximum allowable extension of 25 percent of the specified surveillance interval, which may enhance safety when used during plant operation, Therefore, the proposed change does not involve a significant reduction in a margin of safety.Lastly, we note that the Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48FR14870) of amendments considered not likely to involve significant hazards considerations.
The sixth of these examples refers to changes which may result in some increase in the probability of occurrence or consequences of a previously analyzed accident or may reduce in some way a safety margin, but the results of which are clearly within limits established as acceptable.
The effect of the proposed T/S changes will be to provide deletion of the 3.25 extension limitation found in T/S 4.0.2.The changes, however, are supported, by Generic Letter 89-14.Therefore, we conclude that the example cited is relevant and that the changes should not involve significant hazards considerations.
Attachment 2 to AEP:NRC:1021-Proposed Revised Technical Specification Changes}}

Revision as of 04:12, 23 October 2019

Application for Amends to Licenses DPR-58 & DPR-74,deleting Extension Limit,Per Generic Ltr 89-14, Line Item Improvement in Tech Specs-Removal of 3.25 Limit on Extending Surveillance Intervals.
ML17328A569
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 02/07/1990
From: Alexich M
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: Murley T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17328A570 List:
References
AEP:NRC:1021, GL-89-14, NUDOCS 9002220473
Download: ML17328A569 (13)
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