ML20012B465

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Amend 66 to License NPF-29,reflecting Planned Organization Changes
ML20012B465
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 03/05/1990
From: Adensam E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20012B466 List:
References
NUDOCS 9003140459
Download: ML20012B465 (6)
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NUCLEAR REGULATORY COMMISSION r, -I L

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SYSTEMS ENERGY RESOURCES. INC., et al DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AftENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No. NPF-29 l'

1.

The Nuclear Regulatory Comission (the Comission) has found that A.

The application for amendment by System Energy Resources, Inc.,

(the licensee), dated September 11, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth'in 10 CFR Chapter I;

'B.

The facility will operate 'in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission;

-l C.

~Thereisreasonableassurance(1)thattheactivitiesauthorizedby

-l this amendment can be conducted without endangering the health and J

safetyofthepublic,and(ii)thatsuchactivitieswillbeconducted

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in compliance with the Comission's regulations; i

1 D.

The issuance of this amendment will not be inimical to the common J

defense and security or to the health and safety of the public; and l

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E.

The issuance of this amendment is in accordance with 10 CFR Part 51 i

L of the Comission's regulations and all applicable requirements have been satisfied.

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. Accordingly, the license is amended by changes to the Technical s

1 Specifications, as indicated in the attachment to this license amendment;

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  • i and paragraph 2.C.(2) of Facility Operating License No. NPF-29 is hereby y

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(2) Technical Specifications

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The Technical Specifications contained in Appendix A and the j

Environmental Protection Plan contained in Appendix B, as revised f

through Amendment No. 66, are hereby incor' rated into this

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.9 license. System Energy Resources, Inc, shall operate the facility in accordance with the Technical Specifications and the Environmental i

Protection Plan.

i 3.

This license amendment is effective as of its date of issuance.

-l FOR THE NUCLEAR REGULATORY COMMISSION j

i Ronnie Lo/for i

Elinor G. Adensam. Director Project Directorate 11-1 i

Division of Reactor Projects - 1/11 Office of Nuclear. Reactor Regulation j

Attachment:

Changes to the Technical

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Specifications 3

Date of Issuance:

March 5, 1990 l

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p-4 ATTACHMENT TO LICENSE AMENDMENT NO. 66 FACILITY OPERATING LICENSE NO. NPF-29 t-00CLET NO. 50-416 ktplace the following pages of the Appendix A" Technical Specifications with the attached pages. The revised pages are identified by /cendment nurrber and contair, vertical lines indicating the area of change, Remove Insert i

e 6-6 6-6 6-1E E-12 6-13 6-13 1

  • 4 1

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1 ADMINISTRATIVE CONTROLS INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) (Continued) i RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification

  • that thase activities are performed correctly and that human errors are reduced as much as practical.

3 AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities operations activities or other i

means of improving unit safety to the Vice President, Nuclear Operations.

l 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shif t Technical Advisor shall provide technical support to the Shif t Superintendent in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to safe operation of the unit.

I 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable.pbsitions, except for the Superintendent, Radiation Control and Shif t Technica1'Adv.isor, who shall meet or exceed the education and experience requirements'of' ANSI /ANS 3.1-1981 as endorsed by Regul-atory Guide 1.8, Revision 2,1987, and licensed personnel who shall meet or r

exceed the criteria of the accredited license training program; and those members of the Independent Safety Engineering Group used for meeting the minimum comple-ment specified in Section 6.2.3.2, each of whom shall have a Bachelor of Science degree or be registered as a Professional Engineer and shall have at least two years experience in their field, at least one year of which experience shall be in the nuclear field.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager, Nuclear Training shall meet or l

exceed INPO accreditation criteria and 10 CFR Part 55, and shall include i

familiarization with relevant industry operational experience.

6.5 REVIEW AND AUDIT 6.S.1 PLANT SAFETY REVIEW COMITTEE (PSRC)

FUNCTION 6.S.1.1 The PSRC shall function to advise the GGNS General Manager on all matters related to nuclear safety.

  • Not responsible for sign-off function.

GRAND GULF-UNIT 1 6-6 Amendment No. 66

Ri1NISTRATIVE CONTROLS AUT'HORITY 6.5.2.9 The SRC shall report to and advise the Vice President, Nuclear Operations on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of SRC activities shall be prepared, approved and distributed as indicated below; Minutes of each SRC meeting shall be prepared, approved and forwarded a.

to the Vice President, Nuclear Operations within 14 days following each meeting, b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vice President, Nuclear Operations within 14 days following completion of the review.

Audit reports encompassed by Section 6.5.2.8 above, shall be c.

forwarded to the Vice President, Nuclear Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES

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6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

Procedures required by Technical Specification 6.8 and other proce-a.

dures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved.

Each such procedure or procedure change shall be reviewed by an individual / group other than the individual / group which prepared the procedure or procedure change, but who may be from the same organization as the individual / group which prepared the procedure or procedure change.

Procedures other than Administrative Procedures shall be approved as delineated in writing by the GGNS General Manager.

The GGNS General Manager shall approve administrative procedures, security implementing procedures l

and emergency plant implementing procedures.

Temporary approval to 1

l procedures which clearly do not change the intent of the approved procedures may be made by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License.

Temporary changes shall be reviewed by the reviewing authority within 14 days of being issued.

For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to-approve the procedure shall approve the change.

b.

Proposed changes or modifications to plant nuclear safety-related l

structures, systems and components shall be reviewed as designated by the Vice President, Nuclear Operations.

Each such modtfication shall be reviewed by an individual / group other than the indiv-idual/ group which designed the modification, but who may be from the same organization as the individual / group which designed the modi-fications.

Implementation of proposed modifications to plant nuclear safety-related structures, systems and components shall be approved by the GGNS General Manager.

GRAND GULF-UNIT 1 6-12 Amendment No. 66

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ADMINISTRATIVE CONTROLS s

' ACTIVITIES (Continued) l Proposed tests and experiments which affect plant nuclear safety and c.

are not addressed in the Final Safety Analysis Report shall be reviewed by on individual / group other than the individual / group which prepared the proposed test or experiment.

d.

Events reportable pursuant to Section 50.73 to 10 CFR Part 50 shall be investigated and a report prepared which evaluates the event and which provides recommendations to prevent recurrence.

Such report shall be approved by the GGNS General Manager.

t-Individuals responsible for reviews performed in accordance with e.

6.5.3.1.s, 6.5.3.1.b, 6.5.3.1.c and 6.5.3.1.d shall meet or exceed the qualification requirements of Section 4.4 of ANSI 18.1, 1971, i

as p.*eviously designated by the Vice President, Nuclear Operations or l

GGNS General Marager, as applicable.

Each such review shall include a determination of whether or not additional, cross-disciplinary re-i view is necessary.

If deemed necessary, such review shall be per-formed by the re~ view personnel of the appropriate discipline.

f.

Each review shall include a determination of whether or not an unreviewed safety question is involved.

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g.

Records of the above activities shall be provided to the GGNS General Manager, PSRC and/or as necessiry for required reviews.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

The Commission shall be notified pursuant to the requirements of a.

Section 50.72 to 10 CFR Part 50, and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50,-and b.

Each REPORTABLE EVENT shall be reviewed by the PSRC and submitted to the SRC and the Vice President, Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit it I

violated:

The NRC Operations Center shall be notified by telephone as soon as a.

possible and in all cases within one hour.

The Vice President, Nuclear Operations and the SRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PSRC.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems or structures, and (3) corrective i

l actions taken to prevent recurrence, i

GRAND GULF-UNIT 1 6-13 Amendment No. 66

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