ML20043H559
| ML20043H559 | |
| Person / Time | |
|---|---|
| Issue date: | 06/18/1990 |
| From: | Rossi C Office of Nuclear Reactor Regulation |
| To: | Floyd S BWR OWNERS GROUP |
| Shared Package | |
| ML20042D839 | List: |
| References | |
| NUDOCS 9006260105 | |
| Download: ML20043H559 (3) | |
Text
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June 18,1990 Mr. S. D. Ployd EWF Owners Group c/o Carolina Power and Light Company 411 Fayetteville Street Raleigh, North Carolina 27602 SilBJECT: CENERAL ELECir.lC COMPAl;Y (GE) TOPICAL REPORT 1;EDC-31677P, " TECHNICAL SPEClf! CATION 1MrF0VEMENT ANALYSIS F0P EUR ISOLATION ACTUAT101:
i INSTf:UMENTAT10li*
Dear Mr. Floyd:
We have completed our review of the subject topical report submitted by the BWE Owners Group by letter dated June 27, 1989. provides our Safety EvaluationReport(SEP),whichwaspreparedafterreviewingtheTechnicalEval-untion Report (TER attached to the SER) developed under contract by Science i
Applications International Corporation. We concur with the findings contained j
in the TER.
j We find that NEDC-31677P provides an acceptable basis for extending surveillance test intervals (ST!s) and allowed outage times (A0Ts) for isolation actuation instrumentation not conson to the reactor protection system (RPS) or the emergency core cooling system (ECCS). Similar TS changes to those requested here, for isolation actuation instrumentation common to RPS and ECCS instrumentation, have been approved in an NRC staff letter to the BWR Owners Group chairman dated January 6. 1%9. The NRC staff has concluded that the analyses presented in NEDC-31677P are accepteble for resolving the issue of extension of STis and A0Ts for isolation actuation instrunentation not conson to the FPS or ECCS, subject to the conditions noted herein (Enclosure 1).
l As noted in the enclosed SER, applicants for proposed Technical Specification changes for individual plants must:
1.
Confirm the applicability of the generic analyses of NEDC-31677P to the plant.
2.-
Confirm that any increase in instrument drift due to the extended STis is properly accounted for in the setpoint calculation methodology.
(for additional information on this issue, see letter from C. E. Rossi to R. F. Janecek, dated April 27,1988.)
' Enclosure 2 provides an acceptable format for proposed TS changes based on j
NE00-31677P. including those already approved in the NRC staff letter to the BWR Owners Group chairman dated January 6,1989. Our review of plant-sptcific changes will censider the applicability of the topical report to the specific Ni gn1 NRC FH.E CENTER COPY M
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o Mr. S. D. Floyd plant, along with the A0T extension limitations noted in the SER (Enclosure 1).
Licensees and applicants are encouraged to propose changes to TS that ere consistent with the guidance provided in the enclosures. Proposed license amendments conforming to this guidance will be expeditiously reviewed by the NRC Project Menager for the facility.
Proposed amendments that deviate from this guidance will require a longer, more detailed review, Please contact the Project Manager if you have questions on this matter.
In accordance with the procedures established in NUREG-0390, " Topical Reports Review Status,* we request that the GE/BWR Owners Group publish accepted revisions of NEDC-31677P, both proprietary and non-proprietary, within three -
months of receipt of this letter. Theacceptedversionsshould(1) incorporate this letter and the enclosed Safety Evalaution Report including (2) include an -
the Technical Evaluation Report, between the title page and the abstract and A (designated accepted) following the report identification symbol.
Should our acceptance criteria or regulations change so that our conclusions as to the acceptability of the report are no longer valid, the BWR Owners Group and/or the applicants or licensees referencing this topical report will be expected to revise and resubmit their respective documentation, or submit justification for the continued applicability of the topical report without revision of its documentation.
l l
Sincerely, Odtinel Signed by l
Charles E. Rossi l
Charles E. Rossi, Director Division of Operational Events Asse'ssment U. S. Nuclear Regulatory Commission
Enclosures:
As stated l
DISTRIBUTION:
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s ld Mr. S. D. Floyd plant, along with the A0T extension limitations noted in the SER (Enclosure 1).
Licensees and applicants are encouraged to propose changes to TS that are consistent with the guidance provided in the enclosures.
Proposed license amendments conforming to this guidance will be expeditiously reviewed by the NRC Project Manager for the facility. Proposed amendments that deviate from this guidance will require a longer, more detailed review. Please contact the Project Manager if you have questions on this matter.
In accordance with the procedures established in NUREG-0390, " Topical Reports Review Status " we request that the GE/BWR Owners Group publish accepted.
revisions of NEDC-31677P, both proprietary and non-proprietary, within three months of receipt of this letter. Theacceptedversionsshould(1) incorporate this letter and the enclosed Safety Evalaution Report including the Technical Evaluation Report, between the title page and the abstract and (2) include an -
A (designated accepted) following the report identification symbol.
Should our acceptance criteria or regulations change so that our conclusions as to the acceptability of the report are no longer valid, the BWR Owners Group and/or the applicants or licensees referencing this topical report will be expected to revise and resubmit their respective docunentation, or submit justification for the continued applicability of the topical report without revision of its documentation.
Sincerely, Charles E. Rossi, Director Division of Operational Events Assessment U. S. Nuclear Regulatory Commission
Enclosures:
As stated DISTRIBUTION:
WTRussell MLWohl WGKennedy j
ACThadani CHBerlinger DMCrutchfield FJCencel
-PSwetland-41 Grimes JWRoe RJBarrett DOEA R/F BKGrimes SNewberry OTSB R/F SAVarga JAcalvo Central files
-CMHolahan-RLEmch PDR CERoa1 OTSB Members DOCultENT NAME:
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