ML18086B017

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Proposed Tech Specs Section 6 Re Administrative Controls
ML18086B017
Person / Time
Site: Salem  PSEG icon.png
Issue date: 10/23/1981
From:
Public Service Enterprise Group
To:
Shared Package
ML18086B015 List:
References
NUDOCS 8111120396
Download: ML18086B017 (14)
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Text

6.0 ADMINISTRATIVE CONTROLS

6. 1 RESPONSIBILITY

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shall be responsible for overall facility operation

.I and shall delegate in writing the succession to this responsibility during his absence ..

6.1.2 The Senior Shift Supervisor or during his absence frDll the Control Room, a designated individual shall be* responsible for the Control Room connand function. A management directive to this effect, signed by the "ic.c p,...~*d e.""t-Nvc.I&~ shal 1 be reissued to all station personnel on an annual J

basis.

6.2 ORGANIZATION OFF SITE 6.2. l The offsite organization for facility aanagement and technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

a. Each on duty shift shall be ca11posed of at least the* *inimum shift crew composition shown in Table* 6.2-1.
b. At least one licensed Operator shall be in the contrtl room when fuel is in the reactor. In addition, at least one licensed Senior Reactor Operator shall be in the.Control Room while the unit is in MODE 1, 2, 3 or 4.
c. A health physics technician# shall be on site when fuel is in the reactor.
d. All CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsi-bilities during this operation.
e. ~ site Fire jrigade of at least S mellbers shall be aaintained onsite at all times . The Fire Brigade shall' not include 4 llembers of the minimum shift crew necessary for safe* shutdown of the unit or any personnel required for other essential functions during a fire

!mergency.

JTh~ n..a.**th pt-iycics technical and Fire Brigade composition AY be less than the mi._il'l"*"t "~~Jiremer*ts for a period of ti* not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accom-

,.odate. lhlc.)Cpc!cte1.1 a!.>sence of the health physics tachnican and/er Fire Brigade tl!W:!t*!~c ... ~ ,.ov.,*ded i11111ediate action is Uken to restore the the health physics te~~ftlc.i~ a,,J./(!'1' Fire Brigade to within the aini*um requirements.

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TABLE 6.2-1 MINIMUM SHIFT *cREW COMPOSITION SALEM UNIT I WITH UNIT ;l IN MODES 5 OR 6 OR DE-FUELED POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3 &4 MODES 5 & 6 SS la la SRO la none RO 2 l AO 3 2b {

STA l none Maintenance 1 none Electrician WITH UNIT a IN MODES l, 2, 3 OR 4 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL P.OSITION MODES 1, 2, 3 &4 MODES 5 & 6 SS la la SRO la none RO 2 l AO 3C l STA la none Maintenance la none Electrician

~/ Individual may fill the same position on Unit 2.

b/ One of the two required individuals may fill the same position on Unit 2. such that there are a total of three AOs for both units.

£/ One of the three required individuals may fill the same position on .._

Unii 1, such that *~toiP!"I? are a total of five AOs for both units. ....

SALEM - UNIT 6-4 (To Ac*c* ~11W ""' ,,. 2..)

TABLE 6.2-1 (Continued)

SS - Shift Supervisor with a Senior Reactor Operators License on Unit 2 SRO - Individual with a Senior Reactor Operators License on Unit 2 RO - Individual with a Reactor Operators License on Unit 2 AO - Auxiliary Operator STA - Shift Technical Advisor Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2.1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 1, 2, 3 or 4, an individual {other than the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Control Room command function. During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 5 or 6, an individual with a valid RO license (other than the Shift Technical Advisor) shall be de~ignated to assume the Control Room co11111and function.

SALEM - UNIT~~ 6-S

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6.2.3 SAFETY REVIEW GROUP (SRG)

FUNCTION 6.2.3.1 The SRG shall perform independent reviews of plant operations and to advise appropriate station/corporate management on the overall *afety of plant operations.

COMPOSITION 6.2.3.2 The SRG shall be composed of at least five dedicated, full-time engineers, located on Artificial Island and *hall report to the General Manager - Nuclear Support.

tu:SPONSIBLITIES 6,2.3.3 TheSRG shall be responsible for:

a. Review of selected plant operating characteristics, NRC issuances, industry advisories, and other *ources of plant design/operating experience dafa that may indicate areas for improving plant *afety.
b. Review of selected facility features*, equipment.and systems.
c. Review of selected procedures, and plant activities including maintenance, mod-ifications, operational problems and operational analysis.

d *. Surveillance of *selected plant operations and maintenance activities to provide independent verification* that they are performed correctly and that human errors are reduced to as low *as reasonably achievable.

AUTHORITY 6.2.3.4 The SRG shall make detailed recommendations for improving plant safety to the appropriate station/corporate management through the General Manager - Nuclear Support.

6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve 1n an advisory capacity to the Shift Supervisor. On matters pertaining to the engineering aspects assuring safe operation of the unit.

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each membe~ of the,facility staff shall meet or exceed the minimum qualirications of ANSI N18. 1-1971 for comparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 Ni<C 1et ter to a 11 1i censees, except for the Ra di at 1on. Protection E~'"'&a._., who shall meet or exceed the ~a11f1cations of Resulatorv Guide 1.8, September 1975,-..w:l the Shift Techn1cal Advisor who shall have a bachelor's degree or ]

~quivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

6.4 TRAINING 6.4. 1 A retraining and replacement tra1n1ng program for the facility staff shall be coordinated by each functional level manager (Department Head) at the fac11 ity and maintained under the direct ion of the ~~.. -'T....i"i"* and shall meet ol'" exceed the requirements and recommendations of Section S.S of ANSI J

~1e.1~1971 and Appendix "A" of 10 CFR Part SS and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.

6.4.2 A training proaram for the Fire Brigade sha,1 be maintained under ]

the direction of the ~~~c::~-T~,,..,,Mlr and shall meet or exceed the requiremen'ts of Section 27 of the NFPA Code-1975, except for Fire arigade training sessions which shall be held at least quarterly.

  • Not !e~ponsible for sign-off function.

SALEM' - .UNIT I ~l 6-6

ADMINISTRATIVE CONTROLS 6.5 REVIEW ANO AUDIT 6.5.1 STATION OPERATIONS REVIEW C0"'41TTEE (SORC)

FUNCTION 6.5.1.1 The Station Operations Review Co1N11ittee shall function to

~ 0~+10~$ on all matters related to nuclear safety.

COMPOSITION 6.5. 1.2 The Station Operations Review COlllllittee shall be composed of the:

Chairman: Assistant General Manager - Salem Operations Vice Chairman: Operations Manager Vice Chairman: Technical Manager Vice Chairman: Maintenance Manager Member: Radiation Protection £ft!'""eer Member: Operating Engineer Member: Technical Engineer Member: Reactor Engineer Member: Maintenance Engineer Member: Senior Shift Supervisor Member: Senior Radiation Protection Supervisor ALTERNATES

6. 5. 1. 3 All alternate members shall be appo1nted "'fn writlng by the SORC Chairman to serve on a temporary basis; however, no more than t~o alternates shall participate as voting members in SORC activities at any one time*.

MEETING FREQUENCY 6.5. 1.4 The SORC shall meet at least once per calendar month: and as convened by the SORC Chairman or his designated alternate.

QUORUM 6.5. 1.5 The minimum quor\Jlll of the SORC necessary for the performance of the SORC responsibility and authority provisions of these technical specifications shall consist of the Ch~~nnan or his designated alternate and four ..mbers including alternates.

  • RESPONSIBILllI ES 6.S.1.6 The Station Operations Review Co11111ittee shall be responsible for:
a. Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the_.c.. ~~ ..~~*~0,.-a."'*~":. to affect nuclear safety.

SALEM - UNIT I ~:2. '--i J

ADMINISTRATIVE CONTROLS

b. Review of all proposed tests and experiments that affect nuclear safety.
c. Review of all proposed changes to Appendix "A" Technical Specifications.
d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
e. Investigation of all violations of the Technical Specifications including the preparation and fo,..arding of reports covering evalua-tion and recomiendat ions. to prevent recurrence* to the Vu;c. Pres 14 c..-.1'-

Nuc 1ear 4! *and to the Chainnan of the Nuclear Review Board.

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f. Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Convnission.
g. Review of facility operations to detect potential nuclear safety hazards.
h. Performance of special reviews, investigations or analyses. and reports thereon as requested by the Chairman of the Nuclear Review Board.
i. Review of the Plant Security Plan and implementing procedures and shall submit reco11111ended changes to the Chairman of the Nuclear Review Board.
j. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chainnan of the Nuclear Review Board*.

AUTHORITY

6. 5. 1. 7 a.

The Station Operations Review Committee shall:

Recommend to. the c.--1""-'"t"-S&J.-o,.-........i~ *rro~-:1* .. dis~,..v.J +

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items considered under 6.5.l.6(a) through (d) above~

b. Render determinations in writing with regard to* whether or not each item considered under ~.S.1.6(a) through (e) above constitutes an unreviewed safety question.
c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the '11r.& P.-e.s -

ac:le"'-t- - ~ucJ~ and the* Nuclear Review Board of d i s a a r e e m e n t !1 J

. between the SORC and the Gc..--.l. M-...,..--~ Gr--"-*MS ; ho... e~lf', 11.-. ~~

~c.i.o-s~o,.-~~-h~ shall have responsibility for resolution of such disagree-ments pursuant to 6.1. l above.

RECORDS 6.5. 1.8 The.Station Operations Review Committee shall maintain written minutes of each meeting that, at a minimum, document the results of all SORC activities 6-8

ADMINISTRATIVE CONTROLS performed under the responsibility and authority provisions of these technical specifications. Copies sha11 be provided to the \bee p.,.a.~a~e.~+ -

t\JL>c-\~.,. and Chairman of the Nuclear Review Board.

J 6.5.2 NUCLEAR REVIEW BOARD (NRB)

FUNCTION

6. 5. 2. l The Nuclear Review Board 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 engineering
h. electrical engineering
i. quality assurance
j. nondestructive testing*
k. emergency prepardness-COMPOSITION 6.5.2.2 The Vice President - ~uc..l~a..~ shall, appoint at least nine .embers to the Nuclear Review Board and shall designate frOlll this membership a chairman and l

at least one vice chairman. The llellbership shall collectively possess experience and competence to provide independent review and audit in the areas listed in Section 6.5.2.l. The chairman and vice chair11an shall have nuclear background in engineering or operations and shall be capable of determining when to call in experts to assist the NRB review of coinplex problems. All members shall have at least a Bachelor Degree in Engineering or related sciences. The chair-man shall have at least six years of professional level aanagerial experience in the power field and all other members shall have-at least five years of cumulative professional level experience in the fields listed in Section 6.5.2.1.

ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the NRB Chairman to serve on a temporary basis; however, no 110re than two alternates shall parti-cipate as voting members in NRB activities at any one time. Educational and experience qualifications required of aubers are also applicable to alternates ..

CONSULTANTS 6.5.2.4 Consultants shall be utilized as deter11ined by the NRB Chairaan to provide expert advice to the NRB.

MEETING FREQUENCY I -

6.5.2.5 The HRB shall meet at least once per calendar quarter during the initial year of unit o~F~~tion fellowing fuel loading and at least once per six months thereaf~er.

SALEM - l,INIT If :Z. 6-9

ADMINISTRATIVE CONTROLS QUORUM 6.5.2.6 The minimum quorum of NRB necessary for the performance of the NRB review and audit functions* of these technical specifications shall consist of the Chairman or his designated alternate and at least 4 NRB members including alternates. No more than a minority of the quorum shall have line responsi-bility for operation of the facility.

REVIEW

6. 5. 2. 7 The NRB shall review:
a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d. Proposed changes to Technical Specifications or this operating license.
e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
g. Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.
i. Reports and meetings minutes of the Station Operations Review Committee.

AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance

  • of the 'NRB. These audits shall encompass:
a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

SALEM - UNIT~ 6-10

ADMINISTRATIVE CONTROLS

b. The performance, training and qualifications of the entire facility staff ~t least once per 12 months.
c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 110nths.
d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix 11 811 , 10 CFR SO, at least once per 24 11enths.
e. The Facility Emergency Plan and i11ple11enting procedures at least once per 24 months.
f. The Facility Security Plan and i11ple11enting procedures at least once per 24 110nths.
g. Any other area of facility ooeration considered appropriate by the NRB or the Vice President- ~~c;.feA~* ]
h. The Facility Fire Protection Progr111 and implementing procedures at least once per 24 inonths.
i. An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 110nths utilizing either qualified offsite licensee personnel or an outside fire protection firm.
j. An inspection and audit of the fire protection and l~ss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

AUTHORITY

6. 5. 2. 9 The NRB shall report to and advise the Vice President-t.i"C'..leo.."" on ]

those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2. 10 Records of NRB activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each NRB 91eting shall be p"'t!pared, approvP.d and forwarded to the V1ce President-<<Juc..le&r- withi" 14 days fol lowing each meeting. ]
b. Reports of reviews ence11passed by .S.ctio" 6.5.2. 7 Uole, sh~ll be prepared, apprcved and forwarded to the Vf ce Pres i delS't- ~\tC.le.o..r within 14 days followin; completfoa. of -th!! review. l SALEM - UNIT I t~

ADMINISTRATIVE CONTROLS

c. Audit reports encompassed by Section 6.5.2.8 above, shall be for-warded to the Vice Pres1dent*fJ~~le..# and to the management positions responsible for the areas audited w1th1n 30 days after completion of the audit.

6*. 6 REPORTABLE OCCURRENCE ACTION 5, 6. 1 The fol lowing actions shall be .taken for REPORTABLE OCCURRENCES:

a. The Co11111ission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
b. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the SORC and submitted to the HRS and the v"e. f,.c.-a,de."'-+-"-'uc.\ea..11". l 6.7 SAFETY LIMIT VIOLATION 6.7. l The following actions shall be taken in the event a Safety Limit is violated:
a. The unit shall be placed in at least HOT STANDBY within one hour.
b. The NRC Operations Center shall be notified by telephone as soon as ]

possible and 1n all cases within one hour. The V1c.e- p,.e.s.-

rc:h:.~+-~uc.\&Q.ro &nd the NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. A Safety Limit Violation Report shall be prepared. The report shall b.e reviewed by the SORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence. *
d. The Safety Limit Violation Report shall be submitted to the Co11111ission, ]

the NRB and the V1c.e. P~*s1dell'i- - "3 uc.leQ.-1.1" within 14 days of the violation. .

6.8 PROCEDURES AND PROGRAMS 6.8. l Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures reco11111ended in Appendix. "A" of Regulatory Guide 1.33, Revision 2, February 1978.
b. Refueling operations.
c. Surveillance and test activities of safety related equipment.
d. Security Plan implementation.
e. Emergency Plan implementation.
f. Fire Protection Program implementation.

SALEM - UNIT 1 l1 6-12

ADMINISTRATIVE CONTROLS 6.8.2 Each procedure and adlllinistrat1v~ policy of 6.8. 1 above, and changes thereto, shall be reviewed by the SORC and approved by the c; ...-J~ .. ~-s-le"" ~pe~+-°'"

prior to implementation and reviewed periodically as set forth in acillinis-3 trative procedures.

6.8.3 Temporary changes to procedures of 6.8. 1 above INiy be ..de provided:

a. The- intent of the origina-1 procedure is not altered.
b. The change is approved by two !Mtllbers of the* plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c. The change is docU11tented, reviewed by the SORC and approved by the Gte..Q"".J.

M'"'rSoJ6- O,e-+.i..,htithin 14 days of implaentation.

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6.8.4 The following programs shall be aaintained:

a. Primary Coolant Sources Outside Contain1tent A program to reduce* leakage from those portions of systems outside contain11ent that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The*

systems include (recirculation spray, safety injection, chemical and volume control, gas stripper, recombiners, *** ). The program shall include the- following:

(i) Preventative maintenance and periodic visual inspection require-inents , _and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in areas under accident conditions.

This program shall include the following:

(i) Training of personnel, (ii) Procedures for 90nitoring, and (iii) Provisions for .. intenance of sampling and analyses equipment.

-c. Secondary Water Chemistry A program for 11enitoring of seco1id&.".1 Wl(tey* che11-\stry to inhibit ste111 generator tube degradation. ih\s ,PGg~!.11 shall ir.:lude:

(i) Identification of 1 sar,>ling schtrdvle for thi? cdt-".c:al variables and the control po'i nts f t.M.se. .,.,;~lei.

SALEM - UNIT ~

l ADMINISTRATIVE CONTROLS

&.8.2 Each procedure and ad9inistrativ~ po1icy of 6.8.1 .bove, and changes 1 thereto, shall bt reviewed by the SORC and lf.lprovtd by the c~-J~--~-s-. e""' Cpe,.,,-h.-:

j prior to imple.entation and reviewed periodica11y as set forth 1n adllinis- .

trative-procedu~es.

6.8.3 T1111por1ry changes to procedures of 6.8. 1 IDove ..Y be . .de provided:

1. The intent of tilt original procedure is not altered.
b. The change is approved by 'tll<<) ..-bers of the,,?1ant ~nagleeei nt st.ao ff, at least one of whOll holds a Senior l1act.or """1r1tor s cense n the unit affected. ]
c. The change is doc"9enttd, "viewed by the SORC and ai>>proved by the e;. ... -..t .

~*"'rs.J- o,c--.+.;,11111.,ithin 14 days of imp1-nt.ation.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9. 1 In addition to the app1icable reporting requirmnents of Tit1e 10, Code of Federa1 Regu1ations, the fellowing reports shall be sutlnitted to the Directer of the Regional Office of Inspection and Enfore1111ent unless otherwise noted.

STARTUP REPORT 6.9.1 .1 A s11m1ary report of plant startup and power escalation testing sha11 be sut:mitted following (1) receipt of an operating license, (2) amendment to the license involving 1 planned increase 1n power 1eve1, (3) installation of fuel that has different design or has been 111nu-facture~ by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thenna1, or hydraulic perfor-mance of the plant.

6.9.1 .2 The startup report sha11 address each of the tests identified in the F'SAR and sha11 1nc1ud1 a description of the eeasured values of the operating conditions or chara*cter1stics.obtained during the test program and a canparision of these values with design predictions and specifica-tions. Any COM"tctive actions that were rtquired to obtain satisfactory operation shall also be dascT"ibed. Any add1t1ona1 specific details required 1n 11cense conditions based on other commitments shall be in-cluded in this raport.

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SALEM - UNIT I lcnencbent No. 9

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