ML18011A218

Application for Amend to License NPF-63,proposing Rev to TS to Remove Organizational title-specific Listing of Plant Nuclear Safety Committee Membership & Replace W/Functional Description of Composition & Specific Requirements

ML18011A218
Person / Time
Site:	Harris
Issue date:	10/22/1993
From:	Robinson W CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18011A220	List: ML18011A218 ML18011A221
References
HNP-93-848, NUDOCS 9310270041
Download: ML18011A218 (13)

Text

ACCEI ERATO@ DOCUMXNT DIST UTION SYSTEM REGULATOR INFORMATION DISTRIBUTIO STEM (RIDS)

ACCESSION NBR:9310270041 DOC.DATE: 93/10/22 NOTARIZED: YES DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH .'NAME AUTHOR AFFILIATION ROBINSON,W.R. Carolina Power s Light Co.

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

SUBJECT:

Application for amend to license NPF-63,proposing rev to TS to remove organizational title-specific listing of plant nuclear safety committee membership & replace w/functional D description of composition & specific requirements.

DISTRIBUTION CODE: ROOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution L ENCL

+ SIZE:

NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD2-1 LA 1 1 PD2-1 PD 1 1 LE,N 2 2 D INTERNAL: ACRS 6 6 NRR/DE/EELB 1 1 NRR/DORS/OTSB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OC/LFDCB 1 0 OGC/HDS1 1 0 FI 01 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 D

D NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 19

Carolina Power & Light Company P. O. Box 165 New Hill, NC 27562 File: HO-930179 SERIAL: HNP-93-848 OCr 2 a lm 10 CFR 50.90 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 REQUEST FOR LICENSE AMENDMENT PLANT NUCLEAR SAFETY COMMITTEE COMPOSITION Gentlemen:

In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power & Light Company (CP&L) hereby requests a revision to the Technical Specifications (TS) for the Shearon Harris Nuclear Power Plant (SHNPP).

The proposed revision will remove the organizational title-specific listing of Plant Nuclear Safety Committee (PNSC) membership in TS 6.5.2.2 and replace it with a functional description of PNSC composition and specific PNSC member qualification requirements (TS 6.5.2.3). Also, Section 6.5.2.2 is revised to stipulate that PNSC members be designated by the Plant General Manager. These revisions to the PNSC are being made to provide support of PNSC membership requirements and to deal with organizational changes without requiring a change to the Technical Specification, while still maintaining the necessary qualifications to adequately advise the Plant General Manager on matters related to nuclear safety.

Enclosure 1 provides a detailed description of the proposed changes and the basis for the changes. details, in accordance with 10 CFR 50.91(a), the basis for the Company's determination that the proposed changes do not involve a significant hazards consideration. provides an 'environmental evaluation which demonstrates that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental assessment needs to be prepared in connection with the issuance of the amendment.

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HAP-93-848 Page 2 provides page change instructions for incorporating the proposed revisions. provides the proposed Technical Specification pages.

In accordance with 10 CFR 50.91(b), CP&L is providing the State of North Carolina with a copy of the proposed license amendment.

Since these changes are administrative in nature and because CP&L's recent reorganization has necessitated procedure revisions, CP&L requests that the proposed amendment be issued by the NRC by December 17, 1993. Once approved by the NRC, implementation will occur within 30 days.

Please refer any questions regarding this submittal to Mr. D. C. McCarthy at (919) 362-2100.

Yours very truly, W. R. Robinson SDC/smh

Enclosures:

1. Basis for Change Request

2. 10 CFR 50.92 Evaluation

3. Environmental Considerations

4. Page Change Instructions

5. Technical Specification Pages W, R. Robinson, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power & Light Company.

Notary (Seal)

My commission expires: My Commission Expires 2/5/g5 ao ud.

NOTARY c: Mr. Dayne H. Brown PUB L(C Mr. S. D. Ebneter Mr. N. B. Le Mr. J. E. Tedrow

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ENCLOSURE SERIAL: HNP-93-848 ENCLOSURE 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO NPF-63

~

REQUEST FOR LICENSE AMENDMENT PLANT NUCLEAR SAFETY COMMITTEE COMPOSITION BASIS FOR CHANGE RE UEST

~Back round Section 6.5.2 of the Technical Specifications (TS) for the Shearon Harris Nuclear Power Plant (SHNPP) specifies requirements for the organization, responsibilities and functioning of the Plant Nuclear Safety Committee (PNSC). Section 6.5.2.2 specifies the composition of the PNSC by listing the titles of the individuals who make up the PNSC. As a result of a recent corporate reorganization, certain titles and positions have changed.

Pro osed Chan e The proposed revision will remove the organizational title-specific listing of Plant Nuclear Safety Committee (PNSC) membership in TS 6.5.2.2 and replace it with a functional description of PNSC composition and specific PNSC member qualification requirements (TS 6.5.2.3). Also, Section 6.5.2.2 is revised to stipulate that PNSC members be designated by the Plant General Manager. These revisions to the PNSC're being made to provide support of PNSC membership requirements and to deal with organizational changes without requiring a change to the Technical Specification, while still maintaining the necessary qualifications to adequately advise the Plant General Manager on matters related to nuclear safety.

Basis Section 6.5.2.2, PNSC Composition, will be revised to eliminate the specific list of organizational titles of designated PNSC members. In lieu of designating specific individuals to make up the PNSC composition, representatives with stipulated technical experience and degree requirements will be appointed from functional areas similar to those previously designated. Specifically, the PNSC will be composed of representatives from the functional areas of engineering, operations, maintenance, health physics/chemistry, nuclear assessment and regulatory affairs. The members, including the Chairman, will be designated in writing by the Plant General Manager. Instead of designating members by specific title, the PNSC Chairman, members and alternates will need to meet the qualification requirements stipulated in the Specification. All members and alternates will be required to have an bachelor's degree in an engineering or science field. Members or alternates may still serve without an bachelor' degree if they have 10 years technical experience with a minimum of 3 years experience in one or more of the designated -functional areas to be represented.

In addition to the bachelor's degree or equivalent, the Chairman will be required to have 10 years of power plant experience of which 3 years shall be nuclear power plant experience. Members and any designated alternates will be required to have 5 years technical experience of which a minimum of 3 years will be in one or more of the designated functional areas to be represented.

Page E1-1

ENCLOSURE SERIAL: HNP-93-848 In Section 6.5.2.2, the responsibility to appoint PNSC members is being changed from the PNSC Chairman to the Plant General Manager.

Conclusions These proposed revisions to TS 6.5.2 are administrative changes that would allow greater flexibility in establishing PNSC membership while maintaining the necess'ary qualifications of the board to adequately advise the Plant General Manager on matters related to nuclear safety. The qualification requirements will continue to ensure that the board has the necessary expertise to consider matters pertaining to nuclear safety and an appropriate representation of functional areas. Therefore, the effectiveness of the SHNPP PNSC is unchanged by this proposed revision.

Page E1-2

ENCLOSURE '1 SERIAL: HNP-93-848 ENCLOSURE 2 i

SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT PLANT NUCLEAR SAFETY COMMITTEE COMPOSITION 10 CFR 50.92 EVALUATION The Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the,,proposed amendment would 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. Carolina Power 6 Light Company'as reviewed this proposed license amendment request and determined that its adoption would not involve a significant hazards determination. The bases for this determination are as follows:

Pro osed Chan e The'roposed revision will remove the organizational title-specific listing of Plant Nuclear Safety Committee (PNSC) membership in TS 6.5.2.2 'and replace it with a functional description of PNSC composition and specific PNSC member qualification requirements (TS 6.5.2.3). Also, Section 6.5.2.2 is revised to stipulate that PNSC members be designated by the Plant General Manager. These revisions to the PNSC are being made to provide support of PNSC membership requirements and to deal with organizational changes without requiring a change to the Technical Specification, while still maintaining the necessary qualifications to adequately advise the Plant General Manager on matters related to nuclear safety.

Basis This change does not involve a significant hazards consideration for the following reasons:

The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.

The changes to Technical Specification 6.5.2 are administrative changes to allow greater flexibility in establishing PNSC membership while maintaining the necessary qualifications of the committee to adequately advise the Plant General Manager on matters related to nuclear safety.

The qualification requirements will continue to ensure that the committee has the necessary expertise to consider matters pertaining to and that the appropriate functional areas will be represented.

nuclear'afety Given that the effectiveness of the PNSC is maintained and that the PNSC has no direct impact on the factors which may initiate or mitigate accidents previously evaluated, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

Page E2-1

ENCLOSURE SERIAL: HNP-93-848 The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.

The changes to Technical Specification 6.5.2 are administrative changes to allow greater flexibility in establishing PNSC membership while maintaining the necessary qualifications of the committee to adequately advise the Plant General Manager on matters related to nuclear safety.

The qualification requirements will continue to ensure that the committee has the necessary expertise to consider matters pertaining to "nuclear safety that the appropriate functional areas will be represented. Given that the effectiveness of the PNSC is maintained and that the PNSC has no direct impact on the factors which may initiate or mitigate accidents, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed amendment does not involve a significant reduction in the margin of safety.

The changes to Technical Specification 6.5.2 are administrative changes to allow greater flexibility in establishing PNSC membership while maintaining the necessary qualifications 'of the committee to adequately advise the Plant General Manager on matters related to nuclear safety.

The qualification requirements will continue to ensure that the committee has the necessary expertise to consider matters pertaining to nuclear safety that the appropriate functional areas will be represented. Given that the effectiveness of the PNSC is maintained, this change does not involve a significant reduction in the margin of safety.

Page E2-2

ENCLOSURE 'I%SERIAL: HNP-93-848 ENCLOSURE 3 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT PLANT NUCLEAR SAFETY COMMITTEE COMPOSITION ENVIRONMENTAL CONSIDERATIONS 10 CFR 51.22(c)(9) provides criterion for and identification of licensing and regulatory actions eligible for categorical exclusion from performing an environmental assessment. A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (3) result in an increase in individual or cumulative occupational radiation exposure. Carolina Power 6 Light Company has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment. The basis for this determination follows:

Pro osed Chan e The proposed revision will remove the organizational title-specific listing of Plant Nuclear Safety Committee (PNSC) membership in TS 6.5.2.2 and replace it with a functional description of PNSC composition and specific PNSC member qualification requirements (TS 6.5.2.3). Also, Section 6.5.2.2 is revised to stipulate that PNSC members be designated by the Plant General Manager. These revisions to the PNSC are being made to provide support of PNSC membership requirements and to deal with organizational changes without requiring a change to the Technical Specification, while still maintaining the necessary qualifications to adequately advise the Plant General Manager on matters related to nuclear safety.

Basis The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the following reasons:

As demonstrated in Enclosure 2, the proposed amendment does not involve a significant hazards consideration.

2. The proposed amendment does not result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite. Revision of the Plant Nuclear Safety Committee administrative controls specified in the Technical Specifications has no impact on the amount, types or release mechanisms of radioactive materials at the Shearon Harris Nuclear Power Plant. As such, the change can not affect the types or amounts of any effluents that may be released offsite.

Page E3-1

ENCLOSURE SERIAL: HNP-93-848 The proposed amendment does not result in an increase in individual or cumulative occupational radiation exposure. The administrative controls specified in the Technical Specifications for the Plant Nuclear Safety Committee have no impact on radiation area work practices or the occupational exposure of site workers. Therefore, the amendment has no affect on either individual or cumulative occupational radiation exposure.

Page E3-2

ENCLOSURE SERIAL: HNP-93-848 ENCLOSURE 4 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT PLANT NUCLEAR SAFETY COMMITTEE COMPOSITION 4

PAGE CHANGE INSTRUCTIONS Removed Pa e Inserted Pa e 6-9 6-9