ML20063Q125

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Proposed Tech Specs Reflecting Position Title Change of Vice President,Nuclear Operations to Vice President, Operations
ML20063Q125
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 08/09/1990
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20063Q120 List:
References
NUDOCS 9008200067
Download: ML20063Q125 (12)
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Text

{{#Wiki_filter:,__ 'I .NL-90/0(o 6.0 AMINISTRATIVE CDNTROLS 6.1 RESPONSIBILITY 6.1.1 The GGNS General Manager ihall be responsible for overall unit operation ] and shall delegate in writing the succession to this responsibility during his 1 absence. 6.1.2 The Shift Superintendent or, during his absence froa~ the Control Roos, a designated individual shall be responsible for the Control Roos command I function. A management directive to this effect signed by thbYh; h;;itst, e "n u r 3 :nti =: shall be reissued to all station personn *f6n an annual

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JSERT) l 6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit organization. j and corporate management, respectively..The onsite and offsite organizations l shall include the positions for activities affecting the safety of the nuclear l power plant, j i a. Lines of authority, responsibility, and communication shall be y established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as l appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions,'or in equivalent forms of documentation. These requirements shall be documented in the-UFSAR and updated at least annually, b. The GGNS General Manager shall be responsible for overall unit safe operation and shall have control over those'onsite activities hg@ necessary for safe operation and maintenance of the plant. c. The Yh: " xid=t, ':=hr %:r; tin; shall have corporate n responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in ~ operating, saintaining, and providing technical support to the plant to ensure nuclear safety. 2 d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall I. ave sufficient organizational freedom to ensure their independence from operating pressures. 6.2.2 UNIT STAFF The unit organizathn shall be subject to the following; a. Each or. duty shift shall be composed of at leest the sinteum shift crew ;omposition shown in Table 6.2.2-L b. At least one licensed Reactor Operator shall be in the control room I when fuel is in the reactor. In addition, while the en tor is in OPERATIONAL CONDITION 1, 2 or 3, at least one license 6 ionior Reactor Operator shall be in the Control Room. 9008200067 900809 gDR ADOCK0500g6 GRAND GULF-UNIT 1 6-1 Amendment No. 45) 1 -n-,- ,.w, .n.

.NL-90/c6 1 6.0 AMINISTRATIVE CDNTROLS 6.1 RESPONSIBILITY' 6.1.1 The GGNS General Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his 1 absence. l 5.1.2 The Shift Superintendent or, during his absence from the Contro' Room, l a designated individual shall be responsible for the Control Room cosuk..id function. A sanagement directive to this-effect signed by th '!h; ";;;id;;t, t:h:r O:r:th:: shall be reissued to all station personnel n an annual basis. hNMRh l 6.2 ~ ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite' organizations shall be established for unit organization. and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant. a. Lines of authority, responsibility, and c:ommunication shall be i established and defined for the highest management levels through intermediate levels to and including all operating organization i positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descript*.sns of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms i of documentation. These requirements shall be documented ~in the UFSAR and updated at least annually. b. The GGNS General Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities

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NL -90/o6 ADMINISTRATIVE CONTROLS INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) (Continued) RESPONSIBILITIES a 2.3.3 The ISEG shall be responsible for maintaining surveillance of unit Jv cities to provide independent verification

  • that these activities are M /med 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 "u; Tc;;it;;, ".;h;; ^;;7;^,0;;. l j 6.2.4 SHIFT TECHNICAL-2 VISOR (IdrrR3 f 6.2.4.1 The Shift Technical Advisor shall provide technical support to the Shift Superintendent in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to safe operation of the u it. i j i 6.3 UNIT STAFF QUALIFICATIONS i 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 Radiation Control and Shift Technical Adv.isor, who shall meet er ex education and experience requirements of ANSI /ANS 3.1-1981 atory Guide 1.8, Revision 2,1987, aed licensed personnel who shail wet oras endorsed bi exceed the criteria of the accredited license training program; and those members of the Independent Safety Engineering Group used for meeting the minimum comple - i 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 experien:e in their field, at least one year of which experience shall be in the nuc1ser field. l 6.4 TRAINING s 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 exceed INP0 accreditation criteria and 10 CFR Part 55, and shall include familiarization with relevant industry operational experience. ~! 6.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY REVIEW Com!TTEE (PSRC) FUNCTION l 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. I GRAND GULF-UNIT 1 6-6 Amendment No. 66; E .-.m .u

i l NL-90/06 INSERT Vice President, Operations.GGNS l l t i i A9006281/SNI.1CFLR - 10

L-To >l i INIS RA IVE CONTROL 5 l i .i EI. I 6.5.2.8 Audits of unit activities shall be performed under the cognizance of { the SRC. These audits.shall encespass: t The conformance of unit operation to provisions contained within the - a. Appendix A Technical Specifications and appitcable license conditions l at least once per 12 months. i b. The performance, training and qualifications of the entire unit staff at least once per 12 months. The results of actions taken to correct deficiencies occurring in c. unit ~ equipment, structures, systems or.nethod of operation that affect nuclear safety at least once per 6 months.- l d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50 at least once per 24 months.; i l 1he Energency Plan and implementing procedures at least once per l e. j 12 months. t ~ l" f. The Security Plan and implementing procedures at least once per 12 months. ~ l 9 Any other area of unit' operation considered appropriate by the SRC g or the,"t; " ; i nt, t u r W e;tc.;.. h. The Fire Protection Program and implementing' procedures at least once i per 24 months.- 1. An independent fire protection and loss prevention inspection and audit shall be performed at least once per 12 months utilizing either ~ qualified offsite licensee personnel or.an outside fire protection firm. ,f. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant 3 at intervals no greater than 36 months. k. The radiological environmental monitoring program and the results thereof at ' east once per.12 months. 1. The OFF5!TE 00$E CALCULATION MANUAL and implementing procedures at least once per 24 months. i n. The PROCESS CONTROL PROGRAM and isplementing procedures for so.lidification of radioactive wastes at least once per 24 months.- s n. The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15. February 1979, at " east once per 12 months, i GRAND GULF-UNIT 1 6-11' Amendment No'.10 p t u -.-..---..--..--.--.I

i NL-90/06 t INSERT i Vice President, Operations GGNS-t E i t t i i l f b t 6 A9006281/SNI.ICFLR - 10

- - - - - - - - - - ~ _- - -- - - - h AL-90/06 ADMINISTRATIVE CONTROLS. i AUTHORITY m ASERTD i 6.5.2.9 The SRC shall report to and advise the 0;;r;th:: on those areas of responsibility specified in Sections 6.5.2.7 and ' m.............,.. i 6.5.2.8. h RECORDS 6.5.2.10 Records of SRC activities shall be prepared. approved and distributed t as indicated below: Minutes of each SRC meeting::shall be prepared, approved and. forw a. ,_leg to the Y S; "r;;fd::t, " :.

0;;r:thn; within 14 days following.

l each m;eeting. i s b. Reports of reviews encom assed by Section 6.5.2,7 above shall be prepared, approved and forwarded to ".he Vu; Pre;%; t. ".;h;.- n j. 0;:r;th : within 14 days following completion of the review. Audit reoorts encompassed by Section 6.5.2.4 above, shall be c. forwardedtotheLV u; Pr;; M: t " :h:r %:r:thn; and'to the l management posit'ons 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 l 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. 4 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 es 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 t approve administrative procedures, security implementing procedures and emergency plant implementing procedures.. Tecpary approval to procedures which clearly do not change the intent of ths 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 3ABER structures, systems and components shall be reviewed as designated L 1 by the;Y h; " ;;id:.t. ";;h;r 0;;r.tu..;. Each such modification l shall be reviewed by an incividual/ 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 i safety-related structures, systems and components.shall be approved by the GGNS General Manager, GRAND GULF-UNIT 1 6-12 Amendment No. 66; O = ~ w ,e ,,,w, ..s,,--n . ~.., e_,,,,.,,,-,.,,..,,.e4,,e,.wn_, , m m.,.,m 9_o ,-,,.,n..,.,-,~,-wmw,..mv.o e n. w--

NL-90/06 _ INSERT Vice President Operations GGNS I k .s b A9006281/SNLICFLR - 10

RL Ao/os, ADMINISTRATIVE CONTROLS + ACT!v! TIES (Continued)- 2 Proposed tests and experiments which affect plant nuclep safety and i c. are not addressed in the Final Safety Analysis Report sh611 be reviewed i by an individual / group other than the individual / group which prepared the proposed test _or experiment. d.- Events reportabis 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 i shall be' approved by the GGNS General Nanager. 1 ( e. I Individuals responsible for reviews performed in accordance with j 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 j the cualification reevirements of Section 4.4 of ANSI 14.1' 1971, i m IN6E9 ' as previously designated by the'"t; Tr;;id;7.t. ";i;; ^;;,;;ti;r.; or - 1 GGNS General Manager, as_ applicable. Each such review shall include a determination of whether or not additional, cross disciplinary re-3 view is necessary..- If deemed necessary,' such review shall be ~ formed by the review personnel of the appropriate discipline. per-j f. Each review shall include a determination of whether or not an unreviewed safety question is involved. l l g. Records' of the above activities shall be provided to the GGNS General Manager, PSRC and/or as r.ecessary for required reviews. l +

6. 6 REPORTA8LE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTA8LE EVENTS:

The Commission shall be notified pursuant to the requirements of i 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 REPORTA8LE EVENT shall be reviewed by the PSRC'and-submitted-to the SRC and the-V4;; Tre;t ;;.t. ".i;; 0;;r;t%c.;. l 6.7 SAFETY LINIT VIOLATION psgAT 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: g The NRC Operations Center shall be notified by elephone as soon-as-a. possible and in all cases within one hour. The 'd;; Tc;;id;r.t. "; m ;r 0;;r;ti;r.; :nd the.SRC shall:be notified within 24 hours, b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PSRC. This report shall describe (1). applicable l circumstances preceding the violation, (2)-effects of the violation upon unit components, systems or structures, and (3) corrective actions taken to prevent recurrence. i GRAND. GULF-UNIT 1 6-13 Amendment.No. 66; L l 5

F 9 NL-90/06 INSERT Vice President. Operatiot.s GGNS L ? h r A9006281/SNLICFLR'- 10

l -\\ .\\ L NL-90/06 ADMINISTRATIVE CONTROLS ] 1AFETY LIMIT V!0LATION (Continued) The Safety Lief t Violation Report shall be subettted'to the c. Comaidston,: the ~ 54C and the "ir " nM:.t. "=hr ^ :=th= within 1 . 14 days of the violation. I ]

d..

Critical operation of the unit shal1~not be resumed until authorized by the Commission. 6.8 PROCEDURES AND P M *! 6.8.1-Written procedures shall be established, toplemented and maintained covering the activities referenced below: The applicable procedures-recommended in Appendix "A" of Regulatory i a. Guide 1.33 Revision 2, February 1978. i b. Refueling operations. f Surveillance and test activities of safety related ' equipment. - c. d. Security Plan faplementation.- j e. Emergency Plan implementation. }' 'f. Fire Protection Progree implementation. i g. PROCES$ CONTROL PROGRAM implementation.- h. 0FF31TE 00$t CALCULATION MANUAL implementation. [ 1. Quality Assurance Progree for effluent and environmental sonitoring, ' [ using the guidance in Regulatory Guide 4.15, Feoruary 1979.

5. 8. 2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed

.I as required by 4.3, above, prior to implementation and shall be reviewed periodically as set forth in administrative procedures.. 6 i l 6.8.3 The following programs shall be established, implemented, and maintained: Primary Coolant Sources Outside Containment a. i A progree to reduce leakage from those portions of systems outside i 1 conta<neent that could contain highly radioactive fluids during a i serious transient or accident to as low as practical levels. The systems include the: 1. RCIC system-outside containment containing steam or water, j except the drain line to the main condenser. t 2. RNA system outside containment containing steam or water, except the line to the LRW system and headers that are isolated by manual valves. 3, HPC$ system. 4. LPCS system. 5. Hydrogen analyzers of the combustible gas control system. l d GRAND GULF-UNIT 1 6-14 Amendment No.10) t -~.m ___.___,__,.._..._,_,,,,._.,,.m..,

NL-90/06 INSERT Vice President. Operations GGNS l l A9006281/SNLICruR'- 10}}

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