ML18010A994

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Summarizes 921113 Meeting W/Nrc to Discuss Licensing Activities at Facility.Reemphasizes & Reaffirms Request That NRC Issue LCO Amend,Originally Submitted on 901229,to Address Nonapplicability of Mode 4,per GL 87-09
ML18010A994
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 01/26/1993
From: Mccarthy D
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-87-09, GL-87-9, NLS-93-013, NLS-93-13, NUDOCS 9302020284
Download: ML18010A994 (6)


Text

.,ACCEI ERAT DOCUMENT DIST VTION SYSTEM REGULA INFORMATION DISTRIBUTIO YSTEM (RIDS)

ACCESSIGN NBR:9302020284 DOC.DATE: 93/01/26 NOTARIZED: NO FAt IL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION MCCARTHY,D.C.

Carolina Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

DOCKET 05000400

SUBJECT:

Summarizes 921113 meeting w/NRC to discuss licensing activities at facility.Reemphasizes

& reaffirms request that NRC issue LCO amend, originally submitted on 901229,to address nonapplicability of Mode 4,per GL 87-09.

DISTRIBUTION CODE:

ZOOID COPIES RECEIVED:LTRi ENCL 0 SIZE:

TITLE: OR Submittal: General Distribution D

NOTES:Application for permit renewal filed.

/

05000400 A

RECIPIENT ID CODE/NAME PD2-1 LA LEiN INTERNAL: ACRS

.NRR/DOEA/OTSB11 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS1 EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD2-1 PD NRR/DET/ESGB NRR/DST/SELB 7E NRR/DST/SRXB 8E OC/LFMB 01 NSIC COPIES LTTR ENCL D

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D NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTETH CONTACI'HE DOCUMENT CONTROL DESK, ROOM P1-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI D

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 21 ENCL

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Carolina Power 8 Light Company SERIAL:

NLS-93-013 United States Nuclear Regulatory Commission ATTENTION:

Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63

SUMMARY

OF MEETING HELD WITH THE NRC ON NOVEMBER 13 1992 Gentlemena On November 13, 1992, Carolina Power 5 Light Company (CPGL) met with the NRC to discuss licensing activities related to the Shearon Harris Nuclear Power Plant (SHNPP).

By letter dated December 4,

1992, the NRC provided a summary of that meeting.

Carolina Power 6 Light Company has reviewed that summary and is concerned that it does not accurately reflect the situation relative to a Request for License Amendment pertaining to Limiting Condition for Operation (LCO) Action Requirements.

The purpose of this letter is to provide a clarification to the NRC summary.

On December 29,

1990, CPQL submitted a Request for License Amendment which proposed to revise three separate SHNPP Technical Specifications to address the non-applicability of Mode 4 for specified systems, utilizing guidance contained in Generic Letter 87-09.

This item was routinely discussed at meetings held between CPGL and the NRC; and from those meetings, CPGL expected an amendment,to be issued by June 1992.

However, by letter dated July 9, 1992, the NRC stated that the CPGL request would be approved if CPGL also agreed to adopt a new Technical Specification for Atmospheric Dump Valves which was being included in the revised Standard Technical Specifications (NUREG-1431).

The NRC's letter further stated that if CPGL chose not to adopt the NRC recommendations, then further review of the CP6cL Request for License Amendment would proceed at a lower priority.

Carolina Power 5l Light Company met with the NRC on August 14, 1992 in White Flint, Maryland, to discuss SHNPP licensing activities.

At that meeting, in light of the NRC's July 9, 1992 letter, CPSL expressed concern about the handling of the license amendment

request, emphasizing that the issue of a Technical Specification for Atmospheric Dump Valves had no relevance to CPEL's amendment request.

The SHNPP Atmospheric Dump Valves (Steam Generator Power-Operated Relief Valves), which are ASME III, Safety Class 2 valves with Class lE power supplies, are not affected by the proposed Request for License Amendment.

9302020284 9'30i26 PDR ADOCK 05000400 P

PDR 411 Fayettevilte Street o P. O. Box 1551 o Raleigh. N. C. 27602 (1887AHHP)

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~Document Control De~

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4 Subsequent to the August 14, 1992 meeting, the NRC verbally informed CPGL that we could respond to the July 9, 1992 letter by simply indicating that the new Technical Specification would not be adopted.

On September 29,

1992, CPQL responded to that effect and reemphasized that the NRC should proceed with the existing amendment request.

During the licensing review meeting held on November 13, 1992, the NRC indicated that CPQL's response did not provide a specific reason for not adopting the new Atmospheric Dump Valve Technical Specification.

Carolina Power 6 Light Company noted that the September 29, 1992 response was in accordance with feedback received from the NRC following the August 14, 1992 meeting and again expressed concern that the NRC was not handling the CPQL request appropriately or consistently.

With respect to the NRC's meeting summary of December 4,

1992, CP&L did not indicate that it may withdraw the Request for License Amendment.
Rather, CPGL stated that it would be necessary for the NRC to justify rejection of the request.

Carolina Power 6 Light Company's position remains unchanged and is summarized as follows:

The original amendment request was submitted utilizing the guidance contained in Generic Letter 87-09 (a NUREG-1435 multiplant action item) in order to clarify confusing LCO Action Statements.

It is essentially administrative in nature and has no relevance to the Atmospheric Dump Valves which are not in the SHNPP Technical Specifications.

The SHNPP Atmospheric Dump Valves are appropriately classified as ASME III, Safety Class 2, with Class 1E power supplies, and are maintained and tested accordingly.

Carolina Power 6 Light Company presently has no plans to implement the new revised Standard Technical Specifications at SHNPP.

Therefore, CPQL reemphasizes and reaffirms its request that the NRC issue the LCO amendment as originally submitted in order to clarify confusing Technical Specification requirements.

Questions or comments regarding this matter may be referred to Mr. R.

W.

Prunty at (919) 546-7318.

Yours very truly, C'avid C. McCarthy Manager Nuclear Licensing Section LSR/jbw cc:

Mr. S.

D. Ebneter Mr. N. B. Le Mr. J.

E. Tedrow

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