ML20247G599

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Proposed Tech Specs Revising Current Position Titles W/New Titles Due to Planned Organizational Changes
ML20247G599
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 09/11/1989
From:
SYSTEM ENERGY RESOURCES, INC.
To:
Shared Package
ML20247G556 List:
References
NUDOCS 8909190104
Download: ML20247G599 (9)
v • d • e


Text

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' PROPOSED TECHNICAL SPECIFICATION-MARKED UP PAGES FOR NL 89/06 8909190104 890911 PDR P

ADOCK 05000416 ppc NLSAECM89061201 - 10 i

'. ML 94lCb ADMINISTRATIVE CONTROLS 1

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INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) (Continued)

RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification

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

AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities operations activities or other means of improving unit safety to the Vice President, Nuclear Operntions.

6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Adviser shall provide technical support to the Shift Superintendent in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to safe opera i o the unit 6.3 UNIT STAFF QUALIFICATIONS fcfN 8d "

6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable pocitions, except for the Ct.es.istry/Rediatien Central Superint;nd:nt a and Shift Technical Advisor, who shall meet or exceed the education and experience requirements of ANSI /ANS l8 3.1-1981 as endorsed by Regulatory Guide 1.8, Revision 2,1987, and licensed personnel who shall meet or exceed the criteria of the accredited license training program; and those members of the Independent Safety Engineering Group used for meeting the minimum complement 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 i the nuclear field.

6.4 TRAlNING h er,l]Q bea Aininy 6.4.1 A retraining and replacement training pr gram for the unit staff chall be maintained under the direction of the Training].,uperint nd:nt, shall mee l ceed INP0 accreditation criteria and 10 CFR Part 55, and shall include i familiarization with relevant industry operational experience.

6.5 REVIEW AND AUDIT l 6.5.1 PLANT SAFETY REVIEW COMMITTEE (PSRC)

FUNCTION 6.5.1.1 The PSRC shall function to advise the GGNS General Manager on all matters related to nuclear safety.

  • Not responsible for sign off function.

1 GRAND GULF-UNIT 1 6-6 AmendmentNo.70,51,_l l

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,'  : NL 88/10 ?

... ADMINI'STRATfVE CONTROLS PLANT SAFETY REVIEW COMMITTEE (PSRC) (Continued)

COMPOSITION 6.5.1.2 The PSRC shall be composed ofnthe- .

Cha -

Manager, Plant Support t Vice Cha aber: Manager, Plant Operations t Member: Manager, Plant Mainten Member: tions Supe 31 ent $

Member: Manage reance and System Engineering g Member: r,Qua tvices &

Member: Chem stry/ Radiation 1 Superintendent .$

Member: I&C Superintendent Mem . Plant Licensing Superintendent

' ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the GGNS General.

' Manager to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSRC activities at any one time.

MEETING FREQUENCY 6.5.1.4 The PSRC shall meet at least once per calendar month and as convened by the PSRC Chairman or Vice Chairman.

QUORUM 6.5.1.5 The quorum of the PSRC necessary for the performance of the PSRC.

responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or Vice Chairman and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The PSRC shall be responsible for review of:

a. Station administrative procedures and changes thereto.
b. The safety evaluations for (1) precedures, (2) changes to procedures, q equipment.or systems, and (3) tests or experiments completed under i the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question and all programs required by Specification 6.8 and changes thereto.
c. Proposed procedures and changes to procedures, equipment or systems which may involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d. Proposed tests or experiments which may involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
e. Proposed changes to Technical Specifications or the Operating License.

GRAND GULF-UNIT 1 6-7 Amendment No. 47,

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.,...- NL 88/10 p ..

Insert to Page 6-7 nine members of GGNS onsite operating organization management at .the.

Superintendent level or above.

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NL 88/10

-ADMINISTRATIVE CONTROLS 6.5.2' SAFETY REVIEW Cott(ITTEE (SRC)

FUNCTION 5.5.2.1 The SRC shall function to provide independent review and audit of designated activities in the areas of:

a. nuclear power plant operations
b. nuclear engineering
c. chemistry and radiochemistry
d. metallurgy
e. instrumentation and control
f. radiological safety
g. mechanical and electrical engineering a
h. quality assurance practices COMPOSITION 5.
6. 5. 2. 2 4he " ' " ' - -- - ' ' ' ' -

k san: Vice President, Nuclear Operations Member: Vice President, Nuclear En ineering & 5 3 Member: ter, Nuclear Plant En ineerf x Member: site i r, GGN5 N Member: Director, Qua s I Member: Designated R nta U Systes services, Inc.

Member: GGNS a Manager Member: ector, Nuclear Licensing 8 Member- Manager, Radiological and Environmental Se t

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r: Manager, Operational Analysis .

ATwo or more additional voting seabers shall be consultants to systes Energy Q'nser't

-~ BJ Resources Inc. consistent with the reconnendations of the Advisory Committee T on Reactor Safeguards letter. Mark to Palladino dated October 20. 1981. A "The SRC members shall hold a Bachelor's degree in an engineering or physical science field or equivalent experience and a minimum of five years of technical expeHence of which a minimum of three years shall be in one or more of the disciplines of 6.5.2.la threugh h. In the aggregate, the seabership of the hserfC) committee shall provide specific practical experience in the majority of th disciplines of 6.5.2.la through h.

ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting seabers in SRC activities at any one time.

GRAND GULF-UNIT 1 a'i- 9 Amends nt Nc. 42, -

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,. NL 88/10 Insert A The SRC shall be composed of a Chairman and nine voting members.

Insert B The Chairman and members shall meet the qualifications below.

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NL 88/10 Insert C The SRC Chainnan shall. hold a Bachelor!s degree in an engineering or physical science field or an equivalent and a minimum of six years of professional level managerial experience in the power field. In addition, the Chainnan shall have the necessary overall nuclear background to determine when to call consultants and contractors for dealing with complex problems beyond the scope of System Energy Resources, Inc. expertise.

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. z ' NL 94/elo t

ADMINISTRATIVE CONTROLS g AUTHORITY I

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 I

6.5.2.10 Records of SRC activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each SRC meeting shall be prepared, approved and forwarded 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.
c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President, Nuclear Operations and to the management positions responsible for the areas audited within 30 days after comp 10 tion of the audit by the auditing organization.

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 'g 6.5.3.1 Activities which affect nuclear safety shall be cono'octed as follows:

a. Procedures required by Technical Specification 6.8 and other proce-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 imples,enting procedures and emergency plant implementing procedures. Temporary approval to 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

/ structures, systems and components shall be reviewed as designated YiceM

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.as. by thep ite :fra ter OC":. Each such modification shall be reviewed l by an individual / group other than the individual / group which tiesigned the modification, but who may be from the same organization as the (

individual / group which designed the modifications. Implementation of propos e modifications to plant nuclear safety-related structures, systers and components shall be approved by the GGNS General Manager.

6-12 Amendment No.10;_ l GRAND GULF-UNIT 1

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ADMINISTRATIVE CONTROL 5'

  1. INACTIVITIES (Continued)

- c. Proposed tests and experiments which affect plant nuclear safety.and are not addressed in the Final Safety Analysis Report shall be reviewed

! by an individual / group other than the individual / group which prepared the proposed test or experiment.

d. ' Events reportable pursuant to Section $0.73 to 10 CFR Part 50 shall be investigated and.'s report prepared which evaluates the event.

l-and which provides recommendations to prevent recurrence. Such report shall be approved by the GGNS General Manager.

." g . Individuals responsible for reviews performed in accordance with 6.5.3.1.a, 6.5.3.1.b, 6.5.3.1.c and 6.5.3.1.d shall meet or exceed b Y ik e frt Nli b .t. the qualification requirements of Section 4.4 of ANSI 18.1, 1971, O/ Af> '5 Pr'*"5 Y d'5i8"'t'd bY th'F;' Ofit's 22"s-or GGNS Gener.1 l b Manager, as applicable. Each such review shall include a determina-tion of whether or not additional, cross-disciplinary review is ,

necessary. If deemed necessary, such review shall be performed by the review personnel of the appropriate discipline.

f. Each review shall include a determination of whether or not an unreviewed safety question is involved.
g. Records of the above activities shall be provided to the GGNS General Manager, PSRC and/or as necessary for required reviews.

6.' 6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified pursuant to the requirements of 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 sha,11 be taken in the event a Safety Limit is violated:

a. The NRC Operations Center shall be notified by telephone as soon as 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 bte prepared. The report shall be reviewed ty 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 action taken to prevent recurrence.

GRAND GULF-UNIT 1 6-13 Amendment No. 10_.l j

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