ML20155B039
| ML20155B039 | |
| Person / Time | |
|---|---|
| Issue date: | 09/22/1988 |
| From: | Rossi C Office of Nuclear Reactor Regulation |
| To: | Grace D BWR OWNERS GROUP |
| Shared Package | |
| ML20154C334 | List: |
| References | |
| NUDOCS 8810060165 | |
| Download: ML20155B039 (7) | |
Text
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UNITED STATES
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W ASHINGTON, D. C. 20666
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SEP 2 21988 Fr. Donald N. Grace, Chairman BWR Owners' Group GPU Nuclear 1 Upper Pond Road, Building E Parsippany, New Jersey 07054
Dear Mr. Grace:
SUBJECT:
GENERAL ELECTRIC COMPANY (GE) TOPICAL REPORT NEDC-30851P, SUPPLEMENT 1. "TECHNICAL SPECIFICATION IMPROVEMENT ANALYSIS FOR BWR CONTROL ROD BLOCK INSTRUMENTATION" We have completed our review of the subject topical report submitted by the BWR Owners' Group by letter dated June 23, 1986. provides our Safety Evaluation Report (SER) which was prepared after reviewing the Technical Evaluation Report, Enclosure 2, (TER attached to the SER), developed under contract by Brookhaven National Laboratory. We concur with the findings contained in the TER. illustrates an appropriate sample Technical Specification change.
We find that NEDC-30851P, Supplement 1 provides an acceptable basis for extending surveillance test intervals (ST!s) for control rod block function (CRBF) instrumentation. The CRBF shares comon instrumentation with the reactor protection system (RPS), which had similar Technical Specification (TS) changes approved in staff letters to the BWR Owners' Group chairman dated July 15, 1987 and January 24, 1988. The staff has concluded that the analyses presented in NEDC-30851P, Supplement I are acceptable for resolving the CRBF STI extension issue, subject to the conditions noted herein.
As noted in tha enclosed SER, applicants for proposed Technical Specification changes for individual plants must:
1.
Confirm the applicability of the generic analyses of NEDC-30851P, Supplement 1 to the plant.
2.
Confirm that any increase in instrument drif t due to the extended STIs is properly accounted for in the setpoint calcdation methodolcgy.
(For additional information on this issue, see letter from C. E. Rossi to R. F. Janecek, dated April 27,1988). provides an acceptable format for proposed TS changes based on NEDC-30851P, Supplement 1.
Our review of plant-spectfic changes will consider only the applicability of the topical report to the specific plant. Licenseet 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 longer, more detailed review. Please contact the Project Manager if you have
')J questions on this matter.
esiOOQ1M Oft, [h PDR C
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}lW0d Donald N. Grace 2
In accordance with procedures established in NUREG-0390, "Topical Reports Review Status," we request that the GE/BWR Owners' Group publish accepted versions of NEDC-30851P, Supplement 1, both proprietary and non-proprietary, within three months of receipt of this letter.
The accepted versions should (1) incorporate this letter and the enclosed Safety 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 changa so that our conclusions as to the acceptability of the report are no longer valid, the BWR Owners' Group and/or the applicants 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 docun'entation.
Sincerely, OdrN1 Sind By Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Enclosures:
As stated Distribution TJ)ii raglia~NRR MWohl, NRR SNewberry, NRR LShao, NRR CHBerlinger, NRR RJBarrett, NRR AThadant, NRR WDlanning, NRR FCongel, NRR DOEA R/F JRoe, NRR OTSB R/F BGrimes, NRR Central Files SVarga, NRR DCS GHolahan, NRR PDR
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In accordance with procedures established in NUREG-0390, "Topical Reports Review Status," we request that the GE/BWR Dwners' Group publish accepted versions of NEDC-30851P, Supplement 1, both proprietary and non-proprietary, within three months of receipt of this letter. The accepted versions should (1) incorporate this letter and the enclosed Safety Evaluation Report between the title page and the abstract and (2) include an -A (designated accepted) following the report indentification 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 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.
Sincerely, Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Enclosures:
As stated (TCPICAL REPORT / GRACE /WOHL)
- (see previous concurrence)
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Because the proposed changes are voluntary and subject to the confirmatory actions noted above, we do not intend to issue a revision to the Standard Technical Specifications (STS) et this tice.
Eventually the STS will be revised to incorporate these changes as part of the NRC TS Improvement Piogram.
In accordance with procedures established in NUREG-0390, "Topical Reports Review Status," we request that the GE/BWR Owners' Group publish accepted versions of NEDC-30851P, Supplement 1, both proprietary and ncn proprietary, within three months of receipt of this letter.
The accepted versinns should (1) incorporate this letter and the enclosed Safety Evaluation Report between the citle page and the abstract and (2) include an -A (designated accepted) following the report indentification symbol.
Should our acceptance criteria or regulations change so that our conclusions as to the acceptability of the report are no longer valfi, the BWR Owners' Group and/or the applicants referencing this topical repe t 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.
Sincerely, Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation Enclosuias:
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In accordance with procedures established in NUREG-0390, "Topical Reports Review Status," we request that the GE/BWR Owners' Group publish accepted versions of NEDC-30851P, Supplement 1, both proprietary and non-proprietary, within three months of receipt of this letter. The accepted versions should (1) incorporate this letter and the enclosed Safety 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 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.
i Sincerely, 1
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c ar es E. Rossi, Director i
Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Enclosures:
As stated i
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Donald N. Grace 2
In accordance with procedures established in NUREG-0390, "Topical Reports Review Status." we request that the GE/BWR Owners' Group publish acceoted versions of NEDC-30851P, Supplement 1, both proprietsry and non-proprietary.
l within three months of receipt of this letter.
The accepted versions should (1) incorporate this letter and the enclosed Safety 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 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.
Sincerely, 0:'rM Signed By Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Enclosures:
As stated Distribution FJMiraglia, NRR MWohl, NRR SNewberry, NRR LShao, NRR CHBerlinger, NRR RJBarrett, NRR AThadani, NRR WDLanning, NRR FCongel, NRR DOEA R/F JRoe, NRR OTSB R/F BGrimes, NRR Central Files SVarga, NRR DCS GHolahan, NRR POR g4 (g[d y(6pc.
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wasmNoroN. o. c. 20sss k, * * * * ' p SEP 2 21988 Mr. Donald N. Grace, Chairman BWR Owners' Group GPU Nuclear i Upper Pond Road, Building E Parsippany, New Jersey 07054
Dear Mr. Grace:
SUBJECT:
GENERAL ELECTRIC COMPANY (GE) TOPICAL REPORT NEDC-30851P, SUPPLEMENT 1 "TECHNICAL SPECIFICATION IMPROVEMENT ANALYSIS FOR BWR CONTROL R00 BLOCK INSTRUMENTATION" We have completed our review of the subject topical report submitted by the BWR Owners' Group by letter dated June 23, 1986. provides our Safety Evaluation Report (SER) which was prepared after reviewing the Technical Evaluation Report, Enclosure 2, (TER attached to the SER), developed under contract by Brcokhaven National Laboratory. We concur with the findings contained in the TER. illustrates an appropriate sample Technical Specification change.
We find that NEDC-30851P, Supplement 1 provides an acceptable basis for extending surveillance test intervals (STis) for control rod block function (CRBF) instrumentation. The CRBF shares coninon instrumentation with the reactor protection system (RPS), which had similar Technical Specification (TS) changes approved in staff lette's to the BWR Owners' Group chaiman dated July 15, 1987 and January 24, 1988. The staff has concluded that the analvses presented in NEDC-30851P, Supplement I are acceptable for resolving the CRBF STI extension issue, subject to the conditions noted herein.
As noted in the enclosed SER, applicants for proposed Technical Specification changes for individual plants must:
1.
Confim the applicability of the generic analyses of NEDC-30851P, Supplement 1 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 infomation on this issue, see letter from C. E. Rossi to R. F. Janecek, dated April 27,1988). provides an acceptable format for proposed TS changes based on NEDC-30851P, Supplement 1.
Our review of plant-specific changes will consider only the applicability of the topical report to the specific plant. Licensees and applicants are encouraged to propose changes to TS that are consistent with the guidance provided in the enclosures. Proposed license amendments confoming to this guidance will be expeditiously reviewed by the NRC Project Manager for the facility. Proposed amendments that deviate from this guidance will require knger, more detailed review.
Please contact the Project Manager if you have questions on this matter.