ML20100B954

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Revised McGuire Nuclear Station Selected Licensee Commitments Manual, Effective Pages
ML20100B954
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 01/19/1996
From: Crane K
DUKE POWER CO.
To:
References
PROC-960119, NUDOCS 9601290326
Download: ML20100B954 (16)
v • d • e


Text

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  • LESS RECtetENT IS OTHERWISE DUKE POWEH COMPANY p)0005 G A COPP EC050 DATE:

01/19/96 (2)4189 UAYNE M H0YLE, MG010P DOCUMENTTRANSMITTAL FORM DOCUMENT TRANSMfTTAL, 10,552 (3)1557 R 0 SHARPE EC13G p)4409 S A GEUEHR EC050 (5) 3379 D E CALDUELL MG01RC r:1 3718 MCG CHEM SHIFT GEN SUPV MG01CH cA CONomoM YES } NO p)3133 M E PACETTI MG02ME

REFERENCE:

(s)1896 J S MURANSKY ECOBH OTHER ACKW4K 79ENTREQUIRED ]YES (93 0794 NSRB STAFF ECOSN MCGUIRE NUCLEAR STATION IF QA OR OTN-  ? NOWLEDGEMENT REQUIRED. PLEASE SELECTED LICENSEE REtu?T BY RETURNING THIS FORM OR OPC O 013609 L K CRIMINGER RP SUPV MG01RP gKN pt)3744 HCG DIR SIM (LINDSAY) MG030T COMMITMENTS MANUAL mr staw 02)3044 MCG DOC CNTRL MISC MAN MG02DM P.O. Box 12700 wu uo02Ou 03)0422 MCG SAFETY REVIEW GROUP MG01SR p4)5512 Z L TAYLOR-CN01RC Huntersvde. North Caronna 28078 0 516593 D E HOLDEN MG03A2 06)2257 R A IIARRIS MG02ME R.cd By Det.

(t7:3759:U;S;HUCLEAR.. REG;UASHUDC

  • 0 816299 J. SPENCER HACKNEY MG010P PAGE 1 0F 4 DOCUMENT NO. C D Q 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 TOTAL SLC 16.13-2 NA NA 01/19/96 MADM-03 V1 V1 V1 V1 V1 V1 V1 V1 V1 V1 V2 V1 V2 V1 V1 V1 V7 J1 74 SLC 16.13-3 NA iA 01/19/96 L 10 C.3 CD O

CD CD REMARKS:

T C MCMEEKIN

'[j VICE PRESIDENT 9601. '0326 960119 '

PDR ADOCK 05000360 l bs\ MCGUIRE NUCLEAR STATION p PDR BY KAY L CRANE MG01RC KLC/CJB

6 January 18, 1996 To: All Holders of the Selected Licensee Commitments Manual Please find attached new SLCs 16.13-2, " Technical Review and Control" and 16.13-3, " Plant Operations Review Committee".  !

Your copy of the manual should be revised as follows:

Remove these pages: Insert these pages:

List of Effective Pages List.of Effective Pages Revision 8 Revision 9 Page 16.0-2 Page 16.0-2, 1/96 Page 16.13-2 through Page 16.13-7, 1/96 Questions or problems should be directed to Kay Crane, McGuire Regulatory Compliance at extension 4306.

b g Kay L. Crane, McGuire Regulatory Compliance

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McGuire maclear Station Selected Licensee Casunitments List of Effective Pages Page Revision Date LOEP Tab i

List of Effective Pages 9 1 through 7 {

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Revision 9 7

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/~% TABLE OF CONTENTS E

)

SECTION TITLE PAGE NO.

NsL:.

16.13 COMMITMENTS RELATED TO CONDUCT OF OPERATIONS 16.13-0 16.13-1 FIRE BRIGADE 16.13-1 16.13-2 TECHNICAL REVIEW AND CONTROL 16.13-2 16.13-3 PLANT OPERATIONS REVIEW COMMITTEE 16.13-6 16.14 COMMITMENTS RELATED TO REFUELING OPERATIONS 16.14-0 l

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b s

.s 16.0-2 1/96, .

( 16.13 CONDUCT OF OPERATIONS 16.13-2 TECHNICAL REVIEW AND CONTROL  ;

COMMITMENT I

A Technical Review and Control Program covering the preparation, review, and approval of documents important to station operation l shall be established and maintained for the site.  ;

APPLICABILITY:

This commitment is applicable at all times and applies to the j review and control activities described in items a through j as i listed below. Personnel performing the preparation, review, and approval activities covered by this commitment shall meet or exceed the qualifications of ANSI N18.1-1971 (the conformance j status for this standard is as listed in Table 17-1 of the Duke i Power Topical Report, Quality Assurance Program, Duke-1-A).

a. The preparation, review, and approval of station procedures ,

shall be done in accordance with station Technical l Specifications. Individuals responsible for these reviews ,

shall be members of the supervisory staff assigned to the j

( '

\ site, be previously designated by the Site Vice President as -

a Qualified Reviewer, and successfully complete the site Qualified Reviewer training program. Review of environmental radiological analysis procedures, shall be performed by the General Manager, Environmental Services or a designee. Each such review shall include a determination of whether or not additional, cross-disciplinary review shall be performed by the appropriately designated site review personnel.

b. Proposed modifications shall be designed and the design reviewed in accordance with station Technical Specifications. The proposed modification design, the l design review, and design approval shall be in accordance l with ANSI N45.2.11 as described in Table 17-1 of the Duke  ;

Power Topical Report, Quality Assurance Program, Duke 1-A. i Proposed modifications to nuclear safety related structures, systems, and components shall be approved prior to implementation by the Station Manager or the Manager of Engineering; or for the Station Manager by a Maintenance Superintendent, the Operations Superintendent, or the Work Control Superintendent, as previously designated by the Station Manager. Upon implementation approval, the modification shall be implemented in accordance with the 16.13-2 1/96 O

" Duke Power Nuclear Station Modification Program and approved

/

procedures (as discussed in Item a above).

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c. ' Proposed changes to the. station Technical Specifications shall be prepared in accordance with station Technical Specifications. Each. proposed Technical Specification ,

change shall be reviewed by the Plant Operations Review Committee (PORC)' and the Nuclear Safety Review Board (NSRB)  !

. prior to submittal to the Nuclear Regulatory Commission. ,

Proposed changes to the Technical Specifications shall be  !

approved by the Station Manager, or for the Station Manager by a designated manager or company officer. Technical .

Specifications submittal cover letters shall be signed by an i officer of Duke Power Company. ]

i

d. Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical ,

Specifications shall be reviewed by the Plant Operations  :

Review' Committee (PORC). i

e. Incidents reportable pursuant to station Technical l Specifications and all violations of Technical Specifications shall be investigated and a report prepared ,

which evaluates the occurrence and.which provides j

/~5 recommendations to prevent recurrence. Such reports shall' j be approved by the Manager, Safety Assurance and provided to the Site Vice President and the Plant Operations Review Committee (PORC). ,

f. The Manager, Safety Assurance shall assure the performance of special reviews and investigations, and the preparation ,

and submittal of reports thereon, as requested by the Site j Vice President. Such reports shall be provided to the Plant i Operations Review Committee (PORC).

.i

g. The Manager, Safety Assurance shall assure the performance ,

of a review by a knowledgeable individual / organization of l every unplanned onsite release of radioactive material to i the environs, including the preparation and forwarding of reports covering evaluation, recommendations, and j disposition of the corrective action to prevent recurrence i to the Site Vice President, and to the Plant Operations  ;

Review Committee (PORC).  !

h. The Manager, Safety Assurance shall assure the performance ,

of a review by a knowledgeable individual / organization of l

~

changes to the Process Control Program, Offsite Dose Calculation Manual (ODCM), and Radwaste Treatment Systems. l l

16.13-3 1/96 ,

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1. The Manager, Safety Assurance shall ensure the performance

(N) s, m

of a review by a knowledgeable individual / organization of the Fire Protection program and implementing procedures and submittal of recommended changes to the Director, Organization Effectiveness Services.

.j . Reports documenting each of the activities performed under this commitment shall be maintained. Copies shall be provided to the NSRB.

REMEDIAL ACTION: Not Applicable BASIS:

a. The requirements contained in this selected licensee commitment were relocated from the McGuire Technical Specifications with the approval of the U. S. Nuclear Regulatory Commission. Changes to this SLC shall be considered a change in an NRC commitment and shall be made ,

only in accordance with the approved Compliance Manual i Procedure for the Control of Selected Licensee Commitments and by use of the 10 CFR 50.59 evaluation process.

/s b. This SLC implements the review requirements of

( ANSI N18.7-1976/ANS-3.2 and ANSI N45.2.11-1974 as referenced I in the Duke Power Company Topical Report, Quality Assurance Program, Duke-1-A.

TESTING REQUIREMENTS: Not Applicable

REFERENCES:

1. ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel
2. ANSI N18.7-1976/ANS-3.2, Administrative Controls and l Quality Assurance for the Operational Phase of Nuclear Power Plants
3. ANSI N45.2.11-1974, Quality Assurance Requirements for the Design of Nuclear Power Plants
4. Compliance Manual Procedure for the Control of Selected Licensee Commitments
5. Nuclear System Directive 209, 10 CFR 50.59 Evaluations p 6. 10 CFR 50.59 9

16.13-4 1/96 ,

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l l

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O 7. Nuclear System Directive 703, Administrative Instructions for Station Procedures l

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l 16.13-5 1/96 ,

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/~'s 16.13 CONDUCT OF OPERATIONS Nd' 16.13-3 PLANT OPERATIONS REVIEW COMMITTEE ,

l COMMITMENT A Plant Operations Review Committee (PORC) shall be established and maintained for the site. The PORC shall be composed of the ,

Manager of Safety Assurance, the Station Manager and his/her l direct reports most responsible for station operation and i maintenance, the Manager of Engineering and his/her direct reports most responsible for engineering support of station operation and maintenance, or designated alternates. The PORC j Chairperson, members, and alternate members shall be qualified in l accordance with ANSI N18.1-1971 and be appointed by the Site Vice l President. The quorum necessary for conducting the PORC l functions shall consist of the Chairperson, or his/her designated alternate, and at least three other PORC members including l alternates.

Reports of reviews encompassed by this Selected Licensee Commitment shall be prepared and forwarded to the Site Vice President and the Nuclear Safety Review Board.

/7 APPLICABILITY j

Nu ,]

a. The FORC shall be responsible for reviewing the following prior to final approval:
1. All proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications;
2. Operability evaluations resulting in a Justification for Continued Operation and a proposal for discretionary enforcement;
3. Operability evaluations resulting in the decision that affected systems, structure or components are OPERABLE but degraded; and
4. All proposed changes to the station Technical Specifications, Bases, or Facility Operating License,
b. The PORC shall be responsible for reviewing the effectiveness of corrective actions for:
1. Licensee Event Reports and Special Reports made to the

()

V NRC; 16.13-6 1/96 -

l i

2. Violations of Technical Specifications;  !

)

3. Special reviews and investigations as requested by the  !

Site Vice President; and

4. Reports on unplanned onsite releases of radioactive '

material to the environs.

c. The PORC shall review additional programs, procedures and plant activities as directed by the Site Vice President, j REMEDIAL ACTION: Not Applicable i BASIS: ,
a. The PORC shall be established to recommend to the Station Manager approval or disapproval of the items listed under APPLICABILITY prior to their final approval. ,

I

b. The PORC shall report to the Site Vice President on the l areas of responsibility specified in this selected licensee commitment.

() TESTING REQUIREMENTS: Not Applicable

REFERENCES:

1. ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel
2. ANSI N18.7-1976/ANS-3.2, Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants
3. Nuclear System Directive 308, Plant Operations Review Committee ,

1 i

16.13-7 1/96 .

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