Text

Proposed Tech Specs Section 6.0 Re Administrative Controls
	ML18101B178
Person / Time
Site:	Salem, Hope Creek
Issue date:	01/11/1996
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18101B176	List: ML18101B175; ML18101B178;
References
	LCR-H95-06, LCR-H95-6, LCR-S95-13, LR-N95092, NUDOCS 9601190414
	Download: ML18101B178 (51)
	v • d • e

ATTACHMENT 2 PROPOSED CHANGES TO THE SALEM 1 TECHNICAL SPECIFICATIONS LICENSE AMENDMENT APPLICATION TO CHANGE SECTION 6.0, ADMINISTRATIVE CONTROLS, FOR SALEM GENERATING STATION UNIT 1 FACILITY OPERATING LICENSE NUMBER DPR-70 LR-N95092 DOCKET NO. 50-272 LCR S95-13 The following Technical Specifications have been revised to reflect the proposed changes:

Technical Specification Pages Index XV, XVIII and XIX 6.1.1 6-1 6 .1. 2 6-1 6.2.1.b and c 6-1 6.2.2.e and f 6-2 6.3 6-7

6.5 6.6.1.b 6.7.1.b and d 6-8 through 6-16 6-16 6-16 6.8.2 6-17 6.8.3.c 6-17 9601190414 960111 PDR ADOCK 05000272 p - PDR

BASES

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SECTION 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION B 3/4 9-1 3/4.9.2 INSTRUMENTATION B 3/4 9-1 3/4.9.3 DECAY TIME B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS B 3/4 9-1 3/4.9.5 COMMUNICATIONS B 3/4 9-1 3/4.9.6 MANIPULATOR CRANE B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION . . . . . B 3/4 9-2

3/4.9.9 3/4.9.10 and 3/4.9.11 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF ISOLATION SYSTEM . . .

WATER LEVEL - REACTOR VESSEL AND STORAGE POOL

. . . . . B 3/4 9-2 B 3/4 9-3 3/4.9.12 FUEL HANDLING AREA VENTILATION SYSTEM B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN . . . . . . . . . . B 3/4 10-1

~3/4.10.2 GROUP HEIGHT, INSERTION AND POWER

"-~~~~~..._,ISTRIBUTION LIMITS B 3/4 10-1 3/4.i0.3 PHYSICS TESTS B 3/4 10-1 3/4.10.4. NO FLOW TESTS B 3/4 10-1

SALEM - UNIT 1 xv Amendment No. 59

ADMINISTRATIVE CONTROLS

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SECTION 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION Onsite and Offsite Organizations 6-1 Facility Staff . . 6-1 Shift Technical Advisor 6-7 6.3 FACILITY STAFF QUALIFICATIONS 6-7 6.4 TRAINING . . . . . 6-7 6.5 REVIEW AND AUDIT . . . . . 6-7 6.5.1 S'PA'PIOH OPEIU'i'PIONS REVIEW COHPH'P'PEE (SORC)

Funetien 6 8

CSffiPOSitien Alternates Heetin§' Frequeney QueruRI . . . . .

Respensibilities SORC Review Preeess 6

6 6

6 8

8 8

8 9

10 Autherity . . . . . 6 10 Reeerds and Reperts 6 10 6.5.2 UUCLEA:R SJ>tFE'PY REVIEW MID ABDI'P Funetien 6 10 CSffiPSSitien 6 10 Censultants G 11 Offsit:e Safet:y Review Group (OSR) 6 11 Fundt:ien . . . . . . . . . . 6 11 Review 6 12 Audit:s 6 12 Reeerds and Reperts . . 6 13 Onsit:e Safet:y Review Group (SRG) 6 13 Funet:ien 6 13 Rcspensibilitics 6 14

.".ut:herit:y . . . . . . . . . . . . . . . . . . . . . . 6 H:

SALEM - UNIT 1 XVIII Amendment No. ~

ADMINISTRATIVE CONTROLS

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SECTION 6.5.3 TECHNICAL REVIEW MID CONTROL 6 14 Activities . . . . . . . . . 6 H:

Procedure Related Documents 6 14 non Procedure Related DocumeE:ts 6 15 Records aE:d Reports 6 16 6.6 REPORTABLE EVENT ACTION 6-16.

6.7 SAFETY LIMIT VIOLATION 6-16.

6.8 PROCEDURES AND PROGRAMS 6-17 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS 6-20 6.9.2 SPECIAL REPORTS 6-24

6.10 RECORD RETENTION 6.11 RADIATION PROTECTION PROGRAM 6.12 HIGH RADIATION AREA 6-24 6-26 6-26 6.13 PROCESS CONTROL PROGRAM (PCP) 6-27 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6-28 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6-28 6.16 ENVIRONMENTAL QUALIFICATION 6-29

SALEM - UNIT 1 XIX Amendment No. +/-.)-3.

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6 . 1 . 1 The jceneral Hanage~ Salem Operationsj,1i\i\1#i.#/:fumi\M:#J!i!#I shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Senior Nuclear Shift Supervisor or, during his absence from the control room, a designated individual, shall be responsible for the control room command function. A management directive to this effect, si ned b the 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as 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 Salem Updated Final Safety Analysis Report and updated in accordance with 10 CFR S0.71(e).

0---b-.--T-h-+:i~.,--G-e_n_e_r_a_l_p_q_a_n_a_g_e_r_ _S_a_l_e_m_,_O_p_e_F_a_t_i_*o_n_s_p_°l_':a-.n-...t;-:*_,-;:,:m-.a-*'.'.-$-:a-'g_e__:r-.J shal 1 be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. The Chief NueleaF OffieeF and PFesident NueleaF Business Unit

$.\M#M#ii\#$#:'/#\iii#.@J##.9.iil.ii@#f$:;$.@§~#i: shall have corporate responsibility foroverall plant nuclear safety and shall take any measures nee e to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

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 have sufficient organizational freedom to ensure their independence from operating pressures.

SALEM - UNIT 1 6-1 Amendment No. -3:-6 ADMINISTRATIVE CONTROLS 6.2.2 FACILITY STAFF The facility organization shall be subject to the following:

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1;

b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, at least one licensed Senior Reactor Operator shall be in the Control Room area at all times.

c. All CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during this operation.

d. The amount of overtime worked by plant staff members performing safety-related functions must be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12)

e. The Operating Engineer, Senior Nuclear Shift Supervisors, and Nuclear Shift Supervisors shall each hold a senior reactor operator license. The Nuclear Control Operators shall hold reactor operator

.0 f.

licenses.

The Operations Manager shall meet one of the following.

(1) Hold an BRO license.

(Z!) Have held an BRO license for a similar unit (PWR) .

SALEM - UNIT 1 6-2 Amendment No. +/-6--&

ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall serve in an advisory capacity to the Senior Nuclear Shift Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.

6.2.3.2 The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971i for comparable positions, except for the individual designated as the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1. 8, September 1975, =#¥~

~:?2%ifiM and the licensed operators who shall comply with the requirements of 10CFR55.

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X¥Y:t:>~~':':'.F .. f;':f;'**:::~m;g::::f,~£@mNtt 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall:

1) be coordinated by each functional level manager (Department Head) at the facility and maintained under the direction of the Manager - Nuclear Training

2) meet or exceed the requirements and recommendations of Section 5.5 cf ANSI NlB.1-1971 for all affected positions except licensed operators and

3) comply with the requirements of 10CFR55 for licensed operators.

The Operations Hanager shall meet: one of t:he following.

1) Hold an SRO license.

2) Have held an SRO license for a similar unit (PWR) .

SALEM - UNIT 1 6-7 Amendment No. -r-o--+

ADMINISTRATIVE CONTROLS

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6. 5 .1 STATION OPER.<TIONS REVIEW COMMITTEE (SORG)

FUNCTION 6.5.1.1 The Station Operations Review Committee shall function te advise the General Manager Salem Operations en operational matters related te nuclear safety.

COMPOSITION 6.5.1.Zl The Station Operations Review Committee (SORC) shall be composed ef.

Chairman. General Manager Salem Operations Member and Vice Chairman. Maintenance Manager Member and Vice Chairman. Operations Manager Member and Vice Chairman. Technical Manager Member. Radiation Protection Manager Member. Operating Engineer Member. Technical Engineer Member. Maintenance Engineer

6.5.1.3 Member .

Member.

Chemistry Manager Onoite Safety Review Engineer ALTERNATES All alternate members shall be appointed in writing by the SORC Chairman.

a. Only designated Vice Chairmen er the General Manager Salem Operations may act as Chairman of a SORC meeting.

b. Ne mere than two alternates to members shall participate as voting members in SORC activities at any one meeting.

c. Alternates shall only represent their respective departments.

d. Alternates fer members will net malee up part ef the voting quorum when the members the alternate represents is aloe present.

MEETHlG FREQUENCY 6.5.l.~ The SORG shall meet at least once per calendar month and as convened by the SORC Chairman er his designated alternate.

QUO RUH

6.5.1.5 The minimum quorum ef the SORG necessary fer the performance ef the SORC responsibility and authority previsions ef these technical specifications SALEM - UNIT 1 6-8 Amendment No. -6

ADMINISTRATIVE CONTROLS

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QUORUM ( eontinued) shall consist of the Chairman or his designated alternate and four members ineluding alternates.

RESPONSIBILITIES 6.5.1.6 The Station Operations Review Committee shall be responsible for.

a. Review of. (1) Upper tier administrative proeedures within the seope of Regulatory Guide 1.33 (2/78), and changes thereto and (2) Newly ereated proeedures or changes to eJEisting proeedures that re~uire a 10CFR50.59 safety evaluation as deseribed in Section 6.5.3.2.d.

b. Review of all proposed tests and eJrperiments that affect nuelear safety.

e. Review of all proposed ehanges to Appe:adiJE "A" Technieal Speeifieations.

d. Review of all proposed eha:ages or modifieations to plant systems or equipment that affect nuelear safety .

e.

f.

Review of the safety evaluations that have been eompleted u:ader the provisions of 10CFR50.59.

Investigation of all violations of the Teehnical Speeifieations ineluding the reports eovering evaluatio:a and reeoffiffiendations to prevent reeurrenee.

g. Review of all REPORTABLE EVENTS.

h. Revim: of faeility operations te detect potential nuelear safety ha2ards.

i. Perferma:aee of speeial reviews, investigations or analyses and reports thereo:a as requested by the General Manager Salem Operations.

j._ Review of the Faeility Seeurity Plan and implementi:ag proeedures and ehanges thereto that require a 10CFR50.59 safety evaluation, er involve a potential deerease in the effectiveness of the plan, per 10CFR50. 54 (p) .

k. Review of the Faeility Emergency Plan and implementing proeedures and ehanges thereto that re~uire a 10CFR50.59 safety evaluation, or involve a potential decrease in the effeetiveness of the plan, per 10CFR50. 5 4 (~) .

1. Review of the Fire Proteetio:a Program and implementing proeedures and ehanges thereto that require a 10CFR50.59 safety evaluation.

SALEM - UNIT 1 6-9 Amendment No. -3

ADMINISTRATIVE CONTROLS

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~

RESPONSIBILITIES (eentinued)

!fl. Review ef all unplanned en site releases ef radieactivity te the envirens including the preparatien ef reperts covering evaluatien, receffiffiendatiens and disposition of the corrective actien te prevent reeurrenee.

n. Review of changes te the PROCESS CONTROL PWHJAL and the OFF SITE DOSE CALCULJ'f.FION PWHJAL.

SORG REVIEW PROCESS 6.5.1.7 A technical review and control systeffi utili:cing EJUalified reviewers shall function to perfor!fl the periodic or routine review of procedures and changes thereto. Details of this technical review process are provided in Section 6.5.3.

AU'I'IIORITY 6.5.1.8 The Station Operations Review Coffiffiittee shall.

a. Provide reCOffiffiendations to the General Manager

Saleffi Operations indicating \lritten approval or disapproval of ite!fls considered under 6.5.1.6 above.

b. Provide written notification within Zl4 hours to the Vice President Nuclear Operations and the Director Quality Assurance and Nuclear Safety Review of disagree!flent between the SORG and the General Manager Saleffi Operations, hmrcver, the General HaE:ager Saleffi Operations shall have responsibility for resolution of ouch disagree!flento pursuant to 6.1_1 above.

RECORDS MID REPORTS 6.5.1.9 The Station Operations Review Coffiffiittee shall !flaintain written lflinuteo of each !fleeting and copies shall be provided to the Vice President Nuclear Operations, the Director Quality ."tssurance and Nuclear Safety and the Manager Nuclear Safety Review.

6 . 5 . Zl PJUCLEAR SAFETY REVIEW MID liODIT FlHlCTIOPJ 6.5.Zl.l The Nuclear Safety Departffient shall f1::1-Ilction to provide the independent safety review prograffi and audit of designated activities.

COMPOSITION

6. 5. Zl. Zl The PJuclear Safety Departffient, under the cogni:cance of the Director Quality Assurance and Nuclear Safety Review, shall consist of the Manager Nuclear Safety, the Offoite Safety Review staff (OSR) and the Onsite Safety Review Group (SRG) The OSR staff and the SRG each consist of at least four SALEM - UNIT 1 6-10 Amendment No. tr-&

ADMINISTRATIVE CONTROLS

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COMPOSITION (continued) dedicated, full time engineers.

The Manager nuclear Safety and the Offsite Safety Review staff shall meet er mweed the qualifications described in Section 'i. 7 of ANS 3 .1 1981 and shall be guided by the provisions for independent review described in Section 'i.3 of MlSI Nl8. 7 1976 (ANS 3. i!) .

The Offsite Safety Review staff shall generally possess meperience and competence in the areas listed in Section 6.5.i!.4.l. A system of qualified reviewers frem other technical organi:;:ations may be used te augment OSR staff mepertise in the disciplines of Section 6.5.i!.4.l, where appropriate. Such qualified reviewers shall meet the same qualification requirements as the Offsite Safety Review staff, and shall not have been involved with performance of the original worlE.

The Onsite Safety Review Group staff shall meet er meceed the qualifications described in Section 4. 4 of MiS 3 .1 1981.

CONSULTMl'TS

6.5.i!.3 Consultants or ether technical eJeperts shall be utili:;:ed by the Nuclear Safety Department to the eJetent necessary.

6.5.i!.4 FUNCTION OFFSITE SAFETY REVIEW GROUP (OSR) 6.5.i!.4.l The OSR staff shall function te provide independent review and audit ef designated activities in the areas ef.

a. Nuclear Power Plant Operations

b. Nuclear Engineering

c. Chemistry and Radiochemistry

d. Metallurg7*

e. Instrumentation and Control

f. Radiological Safety

g. Mechanical Engineering

h. Electrical Engineering

i. Quality Assurance j . Nondestructiv*e Testing

k. Emergency PreparedRess SALEM - UNIT 1 6-11 Amendment No. -3

ADMINISTRATIVE CONTROLS

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REVIEW 6.5.2.4.2 The OSR staff shall review.

a. The safety evaluations for changes to procedures, equipment, or systems, and tests or meperiments completed under the provisions of 10CFR50.59, to verify that such actioas did not constitute an unreviewed safety question, b Proposed changes to procedures, equipment, or systems, and tests or meperiments that involve aa unreviewed safety question as defined in 10CFR50.59,

c. Proposed changes to Technical Specifications or to the Operating License,

d. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance,

e. Significant operating abaormalities or deviations from normal and mepected performaE:ce of plaE:'t: equipmeE:'t: 't:ha't: affect. nuclear safety,

f.

g.

.".11 REPORTABLE EVENTS, All recognised indications of an unanticipated deficiency in some aspect of design or operatioE: of structures, systems or components that could affect auclear safety,

h. Reports aad meeting minutes of the Station Operatioas Review Cofflfflittee.

AUDITS 6.5.2.4.3 Audits of facility activities shall be performed under the cognisance of the OSR staff. These audits shall eacofflpass.

a. The conformance of facility operatioa to provisions contained 'a'lthin the Technical Specifications and applicable license coaditions at least once per 12 months.

b. The performance, training, and qualifications of the entire facilit::

staff at least once per 12 months.

c. The results of actions t~een to correct deficiencies occurring 1n facility equipment, structures, systems, or method of operation that affect nuclear safety at least once per 6 moaths .

d. The perforfflance of activities required by the Operational Qual it':'

Assurance Prograffl to H1eet the Criteria of AppendiJe B to 10CFRS O. 1 :_

least once per 24 fflonths.

SALEM - UNIT 1 6-12 Amendment No. ~

ADMINISTRATIVE CONTROLS

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MJDITS e.

(continued)

The Facility Emergency Plan and implementing procedures at least once per 12 months.

f. The Facility Security Plan and implementing procedures at least once per 12 months.

g. Any other area of facility operation considered appropriate by the Director Quality Assurance and Pruclear Safety Review or the Chief Pruclear Officer and President Pruclear Business Unit.

h. The Facility Fire Protection Program and implementing procedures at least once per 24 months.

i. The fire protection and loss prevention program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer(s) or an outside independent fire protection consultant. An outside independent fire protection consultant shall be utilized at least once per 36 months.

j. The radiological enviroffiftental monitoring program and the results

thereof at least once per 12 months .

The above audits may be conducted by the Quality .'\ssurance Department or an independent consultant. Audit plans and final audit reports shall be reviewed by the OSR staff.

RECORDS NlD REPORTS 6.5.2.4.4 Records of OSR activities shall be maintained. Reports of reviews and audits shall be prepared and distributed as indicated below.

a. The results of reviews performed pursuant to Section 6.5.2.4.2 shall be reported to the Claief Pruclear Officer and President Nuclear Business Unit at least monthly.

b. Audit reports prepared pursuant to Section 6.5.2.4.3 slaall be forwarded by the auditing organization to the Claief Pruclear Officer and President Nuclear Business Unit and to the management positions responsible for the areas audited (1) within 30 days after completion of tlae audit for tlaose audits conducted by tlae Quality Assurance Department, and (2) within 60 days after completion of the audit for those audits conducted by a-a i-adependent consultant.

6.5.2.5 OH SITE SAFETY REVIEW GROUP (SRG)

FillJCTimi 6.5.2.5.1 The On Site Safety Review Group (SRG) shall function to provide.

the review of plant design and operating eJEperience for potential opportunities to improve plant safety, the evaluation of plant operations and SALEM - UNIT 1 6-13 Amendment No. 6

ADMINISTRATIVE CONTROLS

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FilliCTION ( em~t.iau.ed) maint.eaaaee aet.ivit.ies, and adviee t.e maaa§'emeat. ea Urn everall Eftialit.y aad safet.y ef plaat. eperat.ieas.

The SRG shall make reeemmeadat.ieas fer revised preeedu.res, eEfl:lipmeat.

medifieat.ieas, er et.her meaas ef imprevia§' plaat. safet.y t.e apprepriat.e st.at.iea/.eerperat.e maaa§'emeat..

RESPONSIBILITIES G.5.2.5.2 The SRG shall be respeasible fer.

a. Review ef seleet.ed plaat. eperat.iag eharaet.erist.ies, ~me issu.aaees, iadttst.ry adviseries, aad et.her apprepriat.e seu.rees ef plaat. desiga aad

eperat.iag meperieaee iafermat.iea t.hat. may iadieat.e *areas fer impreviag plant. safet.y.

b. Review of seleet.ed faeilit.y feat.u.res, e~ipmeat., aad syst.ems.

e. Review ef seleet.ed preeedttres aad plaat. aet.ivit.ies iaelu.diag maiat.eaaaee, medifieat.iea, eperat.ieaal preblems, aad eperat.ieaal aaalysis. ,

d. Su.rveillaaee ef seleet.ed plaat. eperat.ieas aad maiat.eaaaee aet.ivit.ies t.e previde iadependeat. verifieat.iea* t.hat. t.hey are perfermed eerreet.ly aad t.hat. httmaa errers are redtteed t.e as lew as reaseaably achievable.

AUTHORITY G.5.2.G The Nu.elear Safet.y Depart.ffient. shall repert. t.e aad advise t.he Chief Nu.elear Offieer aaei Presieieat. Uuelear Busiaess Uait. ea t.hese areas ef respeasibility specified ia Seet.ieas G.5.2.4 and G.5.2.5.

G. 5. 3. TECmHCAL REVIEW MID CONTROL ACTIVITIES G.5.3.l Pregrams re~ired by Teehnieal Speeifieatiea 6.8 aad ether preeedures whieh af feet auelear safet.y as determiaed by the Geaeral P4aaager Salem Operat.ieas, et.her t.haa editerial er t.ypegraphieal ehaages shall be reviewed as fellews.

PROCEDURE REL}'1TED DOCUP4ENTS G. 5. 3. 2 Preeedures, Pr.egram aad ehaages t.herete shall be reviewed *as fellews.

a. Each aewly created precedure, pregram er chaage t.herete shall be iadepeaeieat.ly reviewed by aa iadividual lmewledgeable ia the subj eat area ether thaa the iadividu.al whe prepared the

Net. respeasible fer sign eff fuaet.iea SALEM - UNIT 1 6-14 Amendment No. 6 ADMINISTRATIVE CONTROLS

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PROCEDURE RELA'3?ED DOCUHEN'3?8 (eontintteei) proeedttre, program er preeedttre ehange, bttt who may be from the same organi:catien as the individl:lal/grettp whieh prepared the preeeeiure or proeeEffire ehange. Preeeeiures ether than Station ~dministrative proeedl:lres will be approved by the appropriate Station Department Manager er by the General Manager Salem Operations. Eaeh Station Department Manager shall be responsible fer a predesignated elass of proeedttres. '3?he General Manager Salem Operations shall approve Station Administrative Preeedttres, Geeurity Plan implementing proceeiures and Emer~cncy Plan implementing proeeeittres.

b. On the spot ehanges to preeedttres whieh elearly de not ehange the intent of the approved preeedures shall be approved b;* two members of the plant management staff, at least one of whem holds a Genier Reaeter Operator License. Revisions te proeedl:lres whieh may involve a ehange in intent ef the approved proeedl:lres, shall be reviewed in accerdanee with Geetion 6.5.3.2.a abeve.

e. Individttals respeasible fer reviews performeei ia aecordance with item 6.5.3.2a abeve shall he approved hy tfie GORC Chairman and designated as Gtatiea Qttalified Reviewers. A system ef Station Qttalified Reviewers, eaeh of whem shall possess qualifieatiens that

!fieet er meeeed the requirements. ef Geetien 4. 4 of ANSI !HS. 1 1971, shall.he maintained by the SORG Chairman. Eaeh review shall inelttde a writt:en determination ef *,1fiether er ~et: additional cress diseiplinary review is neeessary. If deemed neeessary, stteh review shall be performed by the appropriate designatea review personnel.

d. If the Department Manager detcrffiiaes that the deettments involved require a 10CFR50.59 safety ewalttation, the deel:lffients shall be forwarded for SORG review and alse to the OGR staff for an independent review to determine whether or net an ttnreviewed safety question is involved. Pttrsttant te iOCFR50.59, HRC approval ef items involving l:lHrevicwcd safety qttcstieHs or '3?cchnieal Speeif ieatieH ehanges shall be obtained prier to implcmeHtatien.

NO!l PROCEDYRE REIJ'A'ED DOCUHEN'3?S 6.5.3.3 '3?ests or C3Etlcrimcnts, ehangcs to '3?eehnieal GpceifieatieHs, aHd ehaHges to equipment or systems shall be forwarded for SORG review and also to the OGR staff fer aH indcpendeHt review to determine whether or not aH unreviewcd safety question is involved. '3?hc resttlts ef the OGR staff reviews will be provided to SORG. Recoffiffiendatiens for approval arc made by SORG to the GeHeral Manager Salem- OpcratieHs. PttrsttaHt to 10CFR50. 59 ,* !l'RC approval of items involviHg ttHreviewed safety qttestieHs er rcqttiriHg '3?eehnieal SpeeifieatioH ehanges shall be obtained prior to implcmcntatioH .

SALEM - UNIT 1 6-15 Amendment No. +/--3

ADMINISTRATIVE CONTROLS

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RECORDS MID REPORTS 6.5.3.4 Written rceords of reviews performed in aeeordanec witfi item G.5.3.2a above, ineludin§J rceoffifficndations for approval or disapproval, sfiall be ffiaintaincd. Copies sfiall be provided to tfic General Hana§Jcr Salem Operations, SORC, tfic OSR staff and/or HRC as neecssary wficn tficir reviews arc required.

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

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 to 10CFR Part SO, and

b. Each REPORTABLE EVENT shall be reviewed by the SORC and the resultant Licensee Event Report submitted to the OSR staff and the 6.7 SAFETY LIMIT VIOLATION

6.7.1 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 in all cases within one hour. The Cfiicf Nuelear Offieer and President "Nuelcar Business Unit iieiifB'ftkfoHfB+/-iii:El.'i hiidlfei=ditio:f*::*:;::::*:*:::- and ............................. .

~~~~~~~il~~~;iiill~lll~~llll~lllllllllllll~lllllllill~:f::tm:]R:?f~#+#:w 9¥%1.@@gi,ii@ shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. A Safety Limit Violation Report shall be prepared. The report shall be 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.

1*

SALEM - UNIT 1 6-16 Amendment No. ~

ADMINISTRATIVE CONTROLS

===========================================================

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended 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.

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

~ -~'

6.8.2

i. Quality Assurance Program for effluent and environmental monitoring.

Each procedure and administrative policy of 6.8.1 above, and changes shall be reviewed and approved in aeeordanee with Speeifieation

~--,~ or 6.5.3, as appropriate, prior to implementation and reviewed

periodically as set forth in administrative procedures.

6.8.3 On-the-spot changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.

b. The change is approved by two members 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 documented and receives the same level of review

..-~~-,-~~~~~~~-=-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-~-

and approval as the original procedure under Speeifieation (1 6.5.3.2a within 14 days of implementation .

SALEM - UNIT 1 6-17 Amendment No.~

ATTACHMENT 3 PROPOSED CHANGES TO THE SALEM 2 TECHNICAL SPECIFICATIONS LICENSE AMENDMENT APPLICATION TO CHANGE SECTION 6.0, ADMINISTRATIVE CONTROLS, FOR SALEM GENERATING STATION UNIT 2 FACILITY OPERATING LICENSE NUMBER DPR-75 LR-N95092 DOCKET NO. 50-311 LCR 895-13 The following Technical Specifications have been revised to reflect the proposed changes:

Technical Specification Pages Index XVIII and XIX 6.1.1 6-1 6.1.2 6-1 6.2.1.b and c 6-1 6.2.2.e and f 6-2 6.3 6-7

*6.5 6.6.1.b 6.7.1.b and d 6-8 through 6-16 6-16 6-16 6.8.2 6-17 6.8.3.c 6-17

ADMINISTRATIVE CONTROLS INDEX

===========================================================

SECTION 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION Offsite and Offsite Organizations . . . . . . . . . . . . . . . . . . . . . . . . 6-1 Facility Staff . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 Shift Technical Advisor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-7 6.3 FACILITY STAFF QUALIFICATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-7 6.4 TRAINING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 - 7 6.5 6-5 6.5.1 S'I'MIO'H OPBRA'I'IOUS REVIEW COHMI'II'BB (SORC)

Function . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . *. . . . . . . . 6 8 CoFRposition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 8

Alternates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 8 Heetin§' Frequency . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 8 Quo ruff\ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 8 Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 9 SORC Review Process . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 10 Authority . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 10 Records and Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 10 6.5.2 HYCLE:AR S:AFE'I'Y REVIEW Function . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 10 CoFRposition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 10 Consultants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 11 Offsite Safety Review (OSR) . . . . . . . . . . . . . . . . . . . . . . . . . . 6 11 Function . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 11 Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 12 Audits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 12 Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 13 Onsite Safety Review Group (SRO) . . . . . . . . . . . . . . . . . . . . . 6 13 Function . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 13 Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 14 Authority . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 14 SALEM - UNIT 2 XVIII Amendment No. 1-

ADMINISTRATIVE CONTROLS

========================================================

SECTION PAGE 6.5.3 TECHNICAL REVIEW MID CONTROL 6 14 Activities 6 14 Procedure Related Decuffients 6 14 Hen Procedure Related Docuffients 6 15 Records and Reports 6 16 6.6 REPORTABLE EVENT ACTION 6-16 6.7 SAFETY LIMIT VIOLATION 6-16 6.8 PROCEDURES AND PROGRAMS 6-16 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS 6-19 6.9.2 SPECIAL REPORTS 6-23 6.10 RECORD RETENTION . . 6-23 6.11 RADIATION PROTECTION PROGRAM 6-25 *1 6.12 HIGH RADIATION AREA 6-25 6.13 PROCESS CONTROL PROGRAM (PCP) 6-26 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6-27 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS . . . . . . . . . . . 6-27 SALEM - UNIT 2 XIX Amendment No. ~

... ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 0 I

6. 1.1 The General Manager Salem Operationsffiffi~#:if{~~§.~;d shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Senior Nuclear Shift Supervisor or, during his absence from the Control Room, a designated individual shall be responsible for the Control Room command function. A management directive to this effect, signed by the Chief nuclear Officer and President Nuclear Business Unitii.i.@P:$.@#1P.9.#.1Mtf~#$.

!i$g~@~@f§f:i!$$~*' shall be reissued to all station personne1***c;11****a:n***~nnuaT ******

basis.

6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be

established and defined from the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as 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 Salem Updated Final Safety Analysis Report and updated in accordance with 10 CFR 50.71(e).

b. Th General Hanager Salem Operations:ffef!~ij#,ilmni'$@$ shall be responsible for overall facility safe operation an shall have control over those onsite activities necessary for safe operation and maintenance of the plants.

The Chief Nuclear Officer and President Huelear Business Unit

~~#.W.§@{#\j@jjj§pijiij@J#.#.i@Bl.~Wk@;;;=;g9@!# shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plants to ensure nuc-lear safety .

SALEM - UNIT 2 6-1 Amendment No. +/---5-&

ADMINISTRATIVE CONTROLS FACILITY STAFF (Continued)

b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, at least one licensed Senior Reactor Operator shall be in the Control Room area at all times.

c. All CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during this operation.

d. The amount of overtime worked by plant staff members performing safety-related functions must be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).

e. The Operating Engineer, Senior Nuclear Shift Supervisors, and

~fficlear Shift Supervisors shall each hold a senior reactor operator license. The Nuclear Control Operators shall hold reactor operator licenses.

f. The Operatioas Maaager shall meet oae of the following.

(1) Hold an BRO licease .

(2) Have held an BRO licease for a similar unit (PWR) .

SALEM - UNIT 2 6-2 Amendment No

ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.l The Shift Technical Advisor shall serve in an advisory capacity to the Senior Nuclear Shift Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.

6.2.3.2 The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI NlS.1-1971~ for comparable positions, except for the individual designated as the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, bh~

~!Hr'H~:F and the licensed operators who shall comply with the requirements of

~

10CFR55 .

e~::;:::~:r@ :; :=J=:~~:, w~&::f:#~:~:~~::::::f:~#~~w:::::::~:~~:t.:t.::,::::iBR'~:=:::w~:::::i~F: ::::::~!J¥::::::::ii'~:~2wff!n~Y 6.4 TRAINING 6.4.l A retraining and replacement training program for the facility staff shall:

1) be coordinated by each functional level manager (Department Head) at the facility and maintained under the direction of the Manager - Nuclear Training

2) meet or exceed the requirements and recommendations of Section 5.5 of ANSI NlS.1-1971 for all affected positions except licensed operators and

3) comply with the requirements 10CFR55 for licensed operators.

The Operations Manager shall meet one of the following.

1) Hold an SRO license.

2) Have held an SRO license for a similar unit (PWR) .

SALEM - UNIT 2 6-7 Amendment No. +/-1-+

ADMINISTRATIVE CONTROLS

===========================================================

6.5.1 STATION OPER:hTIONS REVIEW COMMITTEE (SORG)

FUNCTION 6.5.1.l The Station Operations Review Coffiffiittee shall function to advise the General Manager Salem Operations on operational matters related to nuclear safety.

COMPOSITIO:N 6.5.1.2 The Station Operations Review Committee (SORG) shall be composed of.

Chairman. General Manager Salem Operations Member and Vice Chairman. Maintenance Manager Member and Vice Chairman. Operations Manager Member and Vice Chairman. Technical Manager Member. Radiation Protection pqanager Member. Operating Engineer Member. Technical Engineer Member. pqaintenance Engineer Member. Chemistry Manager

Member .

.7\:LTERNATES 6.5.1.3 Onsite Safety Review Engineer All alternate members shall be appointed in writing by the SORC Chairman.

a. Only designated Vice Chairmen or the General Manager Salem Operations may act as Chairman of a SORG meeting.

b. No more than two alternates to members shall participate as voting members in SORC activities at any one meeting.

c. Alternates shall only represent their respective departments.

d. .'\lternates for members will not make up part of the voting quorum when the members the alternate represents is also present.

MEETHlG FREQUENCY 6.5.1.1 The SORG shall meet at least once per calendar month and as convened by the SORG Chairman or his designated alternate.

QUORUM 6.5.1.5 The minimum EfUOrum of the SORG necessary for the performance of the SORC responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate and four members including alternates.

SALEM - UNIT 2 6-8 Amendment No. +/-5 ADMINISTRATIVE CONTROLS

===========================================================

RESPONSIBILI'FIES 6.5.1.6 'Fhe Station Operations Review Col!\ff\ittee shall be responsible for.

a. Review of. (1) Upper tier administrative procedures within the scope of Regulatory Guide 1. 33 (2/78), and changes thereto and (2) Newly created procedures or changes to mEisting procedures that require a 10CFR50.59 safety evaluation as described in Section 6.5.3.2.d.

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to AppendiJE "A" 'Fechnical Specifications.

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

e. Review of the safety evaluations that have been completed under the provisions of 10CFR50.59.

f. IftVestigation of all violations of the 'Fechnical Speeifieations

g.

h.

including the reports covering evaluation and recol!\ff\endations to prevent recurrence.

Review of all REPOR'PABLE EVE:H'FS.

Review of facility operations to detect potential nuclear safety hazards.

i. Performance of special reviews, investigations or analyses and reports thereon as requested*by the General Manager Salem Operations.

j. Review of the Facility Security Plan and implementing procedures and changes thereto that require a 10CFR50.59 safety evaluation, or involve a potential decrease in the effectiveness of the plan, per 10CFR50.54(p).

k. Review of the Facility Emergency Plan and implementing procedures and changes thereto that require a 10CFR50.59 safety evaluation, or involve a potential decrease in the effectiveness of the plan, per 10CFR50.54(q).

1. Review of.the Fire Protection Program and implementing procedures and changes thereto that require a 10CFR50.59 safety evaluation .

ff\. Review of all unplanned on site releases of radioactivity to the_ environs including the preparation of reports covering evaluation, recoff\ff\endations and disposition of the corrective action to prevent recurrence.

SALEM - UNIT 2 6-9 Amendment No. +/-1-il-

ADMINISTRATIVE CONTROLS

===========================================================

RESPONSIBILITIES Fi.

(continued)

Review of changes to the PROCESS CONTROL HAUUAL and the OFF SITE DOSE CALCULlrTION P4MJUAL.

SORC REVIEW PROCESS 6.5.1.7 A technical review and coatrol system utilising qualified reviewers shall functioa to perform the periodic or routiae review.of procedures and changes thereto. Details of this technical review process are provided in Section 6.5.3.

AUTHORITY 6.5.1.8 The Station Operations Review Cofllf!littee shall.

indicating written approval uader 6.5.1.6.

b. Provide writtea notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President Pruclear Operations and the Directer Quality Assurance and Pruclear Safety Review of disagreeme:a:t between the SORC and 'ehe

General Hanager Salem Operations, however, the General Manager Salem Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS A:ND REPORTS 6.5.1.9 The Station Operations Review Cofllfflittee shall maintain written minutes of each meeting and copies shall be provided to the Vice President Nuclear Operations, the Director Quali'ey Assurance and Nuclear Safety Review and the Manager Nuclear Safety.

6. 5. 2 NUCLEAR SAFETY REVIEW AND ..rUDIT FUNCTION

6. 5. 2. 1 The Pluclear Safety Department shall fuaction to provide the independent safety review program and audit of designated activities.

COMPOSITION 6.5.2.2 The Nuclear Safety Department, under the cognisance of the Director Quality Assurance and Nuclear Safety Review, shall consist of the Manager Nuclear Safety, the Offsite Safety Review staff (OSR) and the Onsite Safety Review Group (SRO) . The OSR staff and the SRO each consist of at least four dedicated, full time engineers .

The Manager ANSI Nl8. 7 SALEM - UNIT 2

Nuclear Safety and the Offsite Safety Review staff shall meet or eJeceed the qualifications deqcribed ia Section 4. 7 of ANS 3 .1 1976 (.~l8 3. 2) .

6-10 1981 and shall be guided by the provisions for independent review described in Section 4.3 of Amendment No. ~

ADMINISTRATIVE CONTROLS

=======================================~================

COMPOSITION (continued)

The Offsite Safety Review staff shall generally possess eJEperience and competence in the areas listed in Section 6.5.2.4.1. A system of qualified reviewers from other technical organil!ations may be used to augment OCR staff e3Epertise in the disciplines of Section 6. 5. 2. 4 .1, where appropriate. Such qualified reviewers shall meet the same qualification requirements as the Offsite Safety Review staff, and shall not have been involved with performance of the original worle.

The Onsite Safety Review Group staff shall meet or meeeed the qualifications described in Section 4. 4 of .'\NS 3. 1 1981.

CO:NSULTANTS 6.5.2.3 Consultants or other technical meperts shall be utilii!ed by the Nuclear Safety Department to the metent necessary.

6.5.2.4 OFFSITE SAFETY REVIEW GROUP (OCR)

FilliCTION 6.5.2.4.1 The OCR staff shall function to provide independent :review and audit of designated activities in the areas of .

a. Nuclear Power Plant Operations

b. Nuclear Engineering

e. 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 Preparedness

SALEM - UNIT 2 6-11 Amendment No.

ADMINISTRATIVE CONTROLS

===========================================================

REVIEW 6.5.%!.'!.%! The OSR staff shall review.

a. The safety evaluatiens fer changes te precedures, equ:ipment, or systeffls, and tests er CJEperiments completed under the previsiens of 10CFR50.59, te verify that such actiens did not constitute an unreviewed safety qu:estion,

b. Propesed changes te procedures, equipment, er systems, and tests or eJt:periments that iE:Velve an i:rnreviewed safety qu:estien as defined in 10CFR50.59,

c. Preposed changes te Technical Specifications er to the Operating License,

d. Violations of codes, regulations, orders, Technical Specificatiens, license requ:irements, er of internal procedures er instructions having nuclear safety significance,

e. Significant operating abnormalities or deviatiens from normal and CJEpected perfermance of plant equ:ipment that affect nuclear safety,

f. All REPORTABLE EVENTS ,

g. All recegnized indications of an unanticipated deficiency in some aspect of design er operation of structures, systems or cempenents that could affect nuclear safety,

h. Reports and meeting minutes of the Statien OperatieE::s Review Cemmittee.

AUDITS 6.5.%!.'!.3 Audits of facility activities shall be performed under the cognizance of the OSR staff. These audits shall encompass.

a. The cenfermance ef facility operation te previsiens contained within the Technical Specificatiens and applicable license conditions at least once per 1%! months.

b. The perfermance, training, and qu:alificatiens of the entire facility staff at least once per 1%! months.

c. The results ef actions t~cen te correct deficiencies occurring in facility equipment, structures, systems, er methed ef operation that affect nuclear safety at least once per 6 months.

d. The perfermance of activities required by the Operational Quality Assurance Program to meet the Criteria of .'\ppendiJE B te 10CFR50, at least ence per %!'! months.

SALEM - UNIT 2 6-12 Amendment No. l--%!-

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===========================================================

S~O~.LNO~ 3:AI.L~.LSINIWffif

ADMINISTRATIVE CONTROLS

===========================================================

FillJCTIO:N (continued) maintenance activities, and advice to management on tfie overall quality and safety of plant operations. Tfie SRO sfiall malEe recommendations for revised procedures, equipment modifications, or other means of improving plant safety to appropriate station/ corporate management.

RESPONSIBILITIES 6.5.2.5.2 Tfie SRO sfiall be responsible for.

a. Review of selected plant operating cfiaracteristics, NRC issuances, industry advisories, and otfier appropriate sources of plant design and operating eJEperience inforl'flation tfiat may indicate areas for i1T1proving plant safety.

b. Review of selected facility features, equipl'flent, and systel'fls.

c. Review of selected procedures and plant activities including l'flaintenance, l'flodification, operational problel'fls, and operational analysis.

d. Surveillance of selected plant operations and l'flaintenance activities to provide independent verification* that they are perforl'fled correctly and tfiat human errors are reduced to as low as reasonably achievable.

NSR AUTHORITY 6.5.2.6 The Nuclear Safety Departl'flent shall report to and advise the Chief Nuclear Officer and President Nuclear Business Unit on those areas of responsibility specified in Sections 6.5.2.4 and 6.5.2.5.

6.5.3 TECIIlHCAL REVIEW .~ID CONTROL ACTIVITIES 6.5.3.1 Progral'fls required by Technical Specification 6.8 and other procedures which affect nuclear safety as deterl'flined by the General Manager Salel'fl Operations, other than editorial or tyiJographical changes shall be reviewed as follows.

PROCEDURE RELl'.c'I'ED DOCUMENTS 6.5.3.2 Procedures, Progral'fl and cfianges tfiereto shall be reviewed as follows .

*Not responsible for sign off function SALEM - UNIT 2 6-14 Amendment No. -5-e-

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D'l:IOS oq peprAoa:d oq 111"

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9 SiliN:?HfilDOG GS'iliV'1Sl:I Sl:IO:GS'DO'l:Id NON

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===========================================================

S~O~.LNOJ :!IAI.L~.LSINIWmf

ADMINISTRATIVE CONTROLS

===========================================================

RECORDS MID REPORTS 6.5.3.1 Written records of reviews performed in accordance with item 6.5.3.Z!a above, including recommendations for approval or disapproval, shall be maintained. Copies shall be provided to the General Manager Salem Operations, SORG, the OSR staff ane/or ~me as necessary when their reviews are required.

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

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 to 10CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the SORC and the resultant Licensee Event Re art submitted to the OSR staff and the 6.7 SAFETY LIMIT VIOLATION

6.7.1 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 hour.

w~thin one

b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Chief Nuclear Officer and President nuclear Business unit s:eiidi8.:iit6di'bhlat:e

c. A Safety Limit Violation Report shall be prepared. The report shall be 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. be submitted to the within 14 days of :~~

violation.

SALEM - UNIT 2 6-16 Amendment No.

ADMINISTRATIVE CONTROLS

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6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended 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.

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

i . Quality Assurance Program for effluent and environmental monitoring.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed and approved in accordance with Specification 6.5.1.6 or 6.5.3 as a ro riate rior to im lementation and reviewed periodically as set forth in administrative procedures.

6.8.3 On-the-spot changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.

b. The change is approved by two members 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 documented and receives the same level of review

-~~~~~a~n~d:...:..a~p.:....;;:p~r~o~v~a=...;:l.::.;=a~s:..._:t~h~e-==o~r~i~g~1~*n=--a=lc:=p~r~o~co.=e~d~u~r~e==*~un:..:....:.d_e_r~S-p~e-c_i_f_1_*c~a-t_i_o_n~~~--~-*l

_ 6.5.3.2a within 14 days of implementation. _

i SALEM - UNIT 2 6-17 Amendment No.---1-1-il-

ATTACHMENT 4 PROPOSED CHANGES TO THE HOPE CREEK TECHNICAL SPECIFICATIONS LICENSE AMENDMENT APPLICATION TO CHANGE SECTION 6.0, ADMINISTRATIVE CONTROLS, FOR HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NUMBER NPF-57 LR-N95092 DOCKET NO. 50-354 LCR H95-06 The following Technical Specifications have been revised to reflect the proposed changes:

Technical Specifications Pages Index xxiv, xxv and xxvi 6 .1.1 6-1 6.1.2 6-1 6.2.1.b and c 6-1 6.2.2 6-2 6.3.2 6-6 6.3.3 6-6 6.5 6-6 through 6-14 6.6.1.b 6-14 6.7.1.a 6-14 6.7.1.c 6-15 6.8.2 6-15 6.8.3.c 6-16 6.8.4.a 6-16 6 .13. 2 .1. a 6-24

INDEX ADMINISTRATIVE CONTROLS

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SECTION PAGE 6 .1 RESPONSIBILITY............................................. 6-1 6 . 2 ORGANIZATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 -1 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS . . . . . . . . . . . . . . . . . . . . . 6-1 6.2.2 UNIT STAFF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 Figure 6.2.1-1 (Deleted)........................ 6-3 Figure 6.2.2-1 (Deleted)........................ 6-4 Figuref::ij&,.$:i$, 6. 2. 2--il-$ Minimum Shift Crew Composition 1-----IM ...,.,.,.,.,.,.*.,.,.,.,.,.,.,. Singie Unit Facility............. 6-5 6.2.3 SHIFT TECHNICAL ADVISOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 6.3 UNIT STAFF QUALIFICATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6

6. 4 TRAINING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6

6. s REVIEW AND AUDIT'J~:~$']!§¥:@t%,gW,]i!B¥:11!1)¥JpE. * * * * * * * * * * * * * * * * * * *

6-6 6.5.1 S'F.'\:TIO:U OPER.1\Timm REVIEW COMl'HTTEE (SORG) . . . . . . . . . . . 6 6 FUNCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 6 COHPOS ITIO"N . . . . . . . . . . . . . . . . . . *. . . . . . . . . . . . . . . . . . . . . . . . 6 7

.'\:LTERHATES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 7 MEETING FREQUE~lCY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 7 QUORUM .. , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 7 RESPmiSIBILITIES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 7 REVIEW PROCESS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 8 A:UTIIORITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 9 RECORDS MID REPORTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 9 HOPE CREEK xxiv Amendment No. 5-2!-

, ~ ...

ADMINISTRATIVE CONTROLS INDEX

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SECTION PAGE 6.5.2 NUCLE."\R S.".. FE'l'Y REVIEW MID AUDIT . . . . . . . . . . . . . . . . . . . . . 6 9 FUNC'l'IOH . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 9 COHPOSI'l'IOl'L . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 9 CONSUL'l'Mi'l'S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 10 OFFSI'l'E SAFETY REVIEW (OSR) . . . . . . . . . . . . . . . . . . . . . . . . . 6 10 FUNCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 10 REVIEW . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 10 Au:DI'l'S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 11 RECORDS MID REPOR'l'S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 12

ONSI'l'E S.",.FETY REVIEW GROUP (SRG) . . . . . . . . . . . . . . . . . . . .

FilliC'l'ION . . . . . . . . . . . . . . . . . . . . . . . . . . : . . . . . . . . . . . . . . . . .

RESPONSIBILITIES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

6 12 6 12 6 12 AU'l'IIORI'l'Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 13 6.5.3 TEC!IlHCAL REVIEW MID CONTROL . . . . . . . . . . . . . . . . . . . . . . . . 6 13 ACTIVITIES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 13 PROCEDURE REh"1'l'ED DOCUHHN'l'S . . . . . . . . . . . . . . . . . . . . . . . . . 6 13 NON PROCBDURB RBLA'l'BD DOCUMENTS . . . . . . . . . . . . . . . . . . . . . 6 H RECORDS MID REPORTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 14 6.6 REPORTABLE EVENT ACTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-14 6.7 SAFETY LIMIT VIOLATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-14 6.8 PROCEDURES AND PROGRAMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-15 6.9 REPORTING REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-17

6.9.1 HOPE CREEK ROUTINE REPORTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

STARTUP REPORT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

6-17 6-17 xxv Amendment No ~

ADMINISTRATIVE CONTROLS INDEX

===========================================================

SECTION PAGE ANNUAL REPORTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-17 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT .. 6-18 0 1;;;;a~~p=~~!~ .... -~ ........ . 6-19 MONTHLY OPERATING REPORTS........................... 6-20 CORE OPERATING LIMITS REPORTS....................... 6-20 6 . 9. 2 SPECIAL REPORTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-20 6 . 10 RECORD RETENTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-21 6.11 RADIATION PROTECTION PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-22 6.12 HIGH RADIATION AREA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-22

6.13 6.14 6.15 PROCESS CONTROL PROGRAM (PCP) . . . . . . . . . . . . . . . . . . . . . . . . . . .

OFFSITE DOSE CALCULATION MANUAL (ODCM)..................

MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND 6-23 6-24 SOLID WASTE TREATMENT SYSTEMS........................... 6-24

HOPE CREEK xxvi Amendment No.

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY

6. 1. 1 The laeneral Hana§'er Hope Creek Operat:ionsP,W.:4.#.#.JJM@i#.#,-\#.# shall be responsible for overall unit operation and shall delegate in writing the I

succession to this responsibility during his absence.

6.1.2 The Senior Nuclear Shift Supervisor, or during his absence from the control room, a designated individual shall be responsible for the control room command function. A management directive to this effect si ned b the Chief Huclear Officer and President nuclear Business Unitm~ffejf,§jf!,lSR%mB#~1%~

p@i!i@:%%'1@?,1~)£)!;pj@p shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall b established and defined from the highest management levels through-intermedia te levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate in the form of organization charts, functional descrip-

tions 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 Hope Creek Generating Station Updated Final Safety Analysis Report and 1

---b-.--:-:-'~*ar-:-:-:-e-:-:-1-a-~-q-:-:-:-:-:-:-c-e-:-:-:-:--:-:-e-:-:-R-o_p_s_:-~-:-: -~-g-:f;-Jj-1;'J-:x)-;)~-t-w-:~-:,¥-:'.;~-; ,~-)-:;~: :-t:'.I*

-n-) shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

The Chief ~fficlear Officer and President nuclear Business Unit'sen+/-dr *.;.*.*.*.*.*.*.*.*,*.*.*.*.*.*.*,*.*.

':.*'\/*::<:;-::;::*:<~\nfr&~~#.:~f'\?:~:~~dbi: shall have cor orate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

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 have sufficient organizational freedom to ensure their independence from operating pressures.

UNIT STAFF 6.2.2 The unit organization shall be subject to the following:

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1; HOPE CREEK 6-1 Amendment No. ::t-=7-

ADMINISTRATIVE CONTROLS

-* ==============================================================================

UNIT STAFF (Continued)

' ... 7

b. At least one.licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Reactor Operator shall be in the control room;

c. ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or licensed Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; and

d. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions e.g., licensed Senior Reactor Operators, licensed Reactor Operators, radiation protection technicians, equipment operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of over-time. The objective shall be to have operating personnel work a nominal** 40-hour week while the unit is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance on major unit modifications, on a temporary basis the following guidelines shall be followed:

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

2. An individual should hot be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period, all excluding shift turnover time.

3. A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time.

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the appropriate department manager, or higher levels of management, in accordance with estab-lished procedures and with documentation of the basis for granting the devia-tion. Controls shall be included in the procedures such that individual over-time shall be reviewed monthly by the General Hanager Hepe Creek Operatienspf.ffe.#.t'Jffi@.#.ffe.§W# or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized .

**The shift schedule is based upon a 12-hour shift with a work week of either 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months or 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

HOPE CREEK 6-2 Amendment No.---5-:2-

ADMINISTRATIVE CONTROLS

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6.2.3 SHIFT TECHNICAL ADVISOR

./'

6.2.3.1 The Shift Technical Advisor shall provide advisory technical support to the Senior Nuclear Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.

6.3 UNIT STAFF QUALIFICATIONS 6.3.l Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1981 for comparable positions, except for the individual designated as the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, the individual designated as the operations manager who shall meet or exceed the minimum qualifications of ANSI/AN$ 3.1-1981 except as modified by Specification 6.3.3, and the licensed operators who shall comply with the requirements of 10 CFR Part 55.

6.3.2 The Operating Engineer, Senior Nuclear Shift Supervisors 7 and Nuclear Shift Supervisors, shall hold a senior reactor operator license. The Nuclear Control Operators shall hold a reactor operator license.

6.3.3 The Operations Manager shall meet one of the following.

( 1) Hold a senior reactor operator license, or (2) Have held a senior reactor operator license for this or a similar 6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall:

1) be maintained under the direction of the Manager-Nuclear Training 2) shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI/ANS 3.1-1981 for all affected positions except licensed operators, and 3) comply with the requirements of 10 CFR Part 55 for licensed operators.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager - Site Protection and shall meet or exceed the requirements of the SRP (NUREG-0800) Section 13.2.2.II.6, 10 CFR 50 Appendix R and Branch Technical Position CMEB 9.5.1, Section C.3.d.

6.5.1 STATION OPERJ\TIONS REVIEW COMMITTEE (SORG)

FUNCTiml" G.5.1.1 The SORG shall function to advise the General Manager Hope Creclc Operations on all matters related to nuclear safety.

HOPE CREEK 6-6 Amendment No. ~

ADMINISTRATIVE CONTROLS

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COMPOSITION 6.5.l.2 The SORG shall be composed of the.

Chairman.

Hember and Vice Chairman.

General Manager Hope Creek Operations Operations Manager Member and Vice Chairman. Technical Manager Member and Vice Chairman. Maintenance Manager Member. Maintenance Engineer Member. Technical Engineer Member. Radiation Protection Manager Member: Chefllistry Manager Member. Onsite Safety Review Engineer Member. Operating Engineer ALTERNATES 6.5.l.3 All alternate fllembers shall be appointed in writing by the SORG Chairfllan.

a. Only designated Vice Chairmen or the General Manager Hope Creek Operations may act as Chairfllan of a SORG meeting.

b. Ho 'ffiore than two alternates to fl\embers shall participate as voting fl\embers in SORG activities at any one meeting .

c. Alternate appointees will only represent their respective departfllent.

d. Alternates for members will not make up part of the voting quoru'ffi when the member the alternate represents is also present.

MEETING FREQUE~lCY 6.5.l.4 The SORG shall meet at least once per calendar month and as convened by the SORG Chairman or his designated alternate.

QUO RUH 6.5.1.5 The quorl::l'ffi of the SORG necessary for the perfor'ffiance of the SORG responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least four members including alternates.

RESPONSIBILITIES 6.5.l.6 The SORG shall be responsible for.

a. Review of. (l) Upper tier administrative procedures within the scope of Regulatory Guide l.33 (2/78), and changes thereto aad (2) Newly created procedures or changes to mEisting HOPE CREEK 6-7 Amendment No. ~

ADMINISTRATIVE CONTROLS

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procedures that require a 10 CFR 50.59 safety evaluation as described in Section 6.5.3.2.d.

b Review of all proposed tests and CJEperiments that affect nuclear safety.

c. Review of all proposed cfianges to AppeadiJe "A" Technical Specifications,

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

e. Review of the safety evaluations that have been completed under the provisions of 10 CFR 50.59.

f. Initiation or review of investigations of all violations of the Techaical Specifications including tfie reports coveriag evaluations and recoffiffiendations to prevent recurrence.

g. Review of all REPORTABLE EVENTS.

h. Review of facility operatioas to detect potential nuclear safet*y hazards.

i. Perfor'ffiaRce of special reviews, investigations or aRalyses and

j.

reports thereon as determined by SORG .

Review of the Facility Security Plan aad implementing procedures and changes thereto that require a 10 CFR 50.59 safety evaluation, or involve a potential decrease in the effectiveness of the plan, per 10 CFR50.54(p).

lE. Review of the Facility Emergency Plan and implementing procedures and changes thereto that require a 10 CFR 50.59 safety evaluation, or involve a f?Otential decrease in the effectiveness of the plan, per 10 CFR 5 0 . 5 4 ( q) .

1. Review of the Fire Protection Program and implementing procedures and changes thereto that require a 10 CFR 50.59 safety evaluation.

m. Review of all untJlanned on site releases of radioactivity to the environs inch1ding lehe preparation of reports covering evaluation, recoffiffiendations, and disposition of the corrective action to prevent recurrence.

n. Review of changes to the PROCESS CONTROL PWIDAL and the OFF SITE DOSE CALCULATIO:N P4..~ro.u.

REVIEW PROCESS

6. 5 .1. 7 A technical review and control system utilizing qualified rcvie*..*ers shall function to perform the f?eriodic or routine re\*iew of procedures and changes thereto. Details of this technical review process are provided in Section 6.5.3.

HOPE CREEK 6-8 Amendment Ne.

ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.8 The SORG shall.

a. Provide recommendations in writing to the General Manager Hope Creek Operations indicating approval or disapproval of items considered under Specification 6.5.1.6 prior to their implementation.

b. Provide written notification within 29: hours to the Vice President Nuclear Operations and to the Director Quality Assurance and Nuclear Safety Review of disagreement between the SORG and the General Manager Hope Creek Operations, however, the General Manager Hope Creek Operations shall have responsibility fer resolution of such disagreements pursuant to Specification 6.1.1.

RECORDS rum REPORTS 6.5.1.9 The SORG shall maintain minutes of each SORG meeting, and copies shall be provided to the Vice President *Nuclear Operations, Director Quality Assurance and Nuclear Safety Review and Manager Nuclear Safety.

6.5.2 NUCLEAR SAFETY REVIEW rum AUDIT FlHlCTION

6.5.2.1 The ~fficlear Safety Department shall function to provide the independent safety review program and audit of designated activities.

COMPOSITION 6.5.2.2 Nuclear Safety Department, under the cognisance of the Directer Quality Assurance and Nuclear Safety Review, shall consist of the Manager Nuclear Safety, the Offsite Safety Review staff (OSR) and the Onsite Safety Review Group (SRG) . The OSR staff and the SRG each consist of at least four dedicated, full time engineers.

The Manager Nuclear Safety and the Offsitc Safety Review staff shall meet or exceed tac qualificatieRs described in Section 4. 7 of rum 3 .1 1981 and shall be guided by the p>revisions fer indcp>cndcnt review described in Section 9:.3 of rum I N18. 7 1976 (rum 3. 2) .

The Offsitc Safety Review staff shall generally p>essess e1epericnce and competence in the areas listed in Section 6.5.2.9:.1. A system of qualified reviewers frolfl other technical ergani2ations shall be utilised to augment OSR staff m~crtisc in the disciplines of Section 6.5.2.9:.1, where appropriate.

Such qualified reviewers shall meet the same qualification requirements as the Offsite Safety Review staff, and shall not have been involved with performance of the original work .

The Onsitc Safety Review Group staff shall meet er CJEcccd the qualifications described ia Section 9:. 9: of rum 3 .1 HOPE CREEK 1981.

6-9 Amendment No . .::;.=t.

ADMINISTRATIVE CONTROLS

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cmrnULTANTC G.5.2.3 Consultants or other technical CJeperts shall be utilized by the Nuclear Safety Department as needed.

G.5.2.4 OFFCI'PE CAFE'PY REVIEW (OSR)

FUNCTION G.5.2.4.1 The OCR staff shall function to provide independent review and audit of designated activities in the areas of.

a. Huclear f:30wer f:3lant 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 . Uondestructiv*e testing

k. Emergency pref:3aredness REVIEW G.5.2.4.2 'Phe OCR staff shall review.

a. 'Phe safety evaluations for changes to procedures, equif:3ment, or systems, and tests or CJeperiments comf:3leted under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question,

b. Proposee changes to procedures, equif:3ment, or systems ane tests or eJEf:3eriments which involve an unreviewed safety question as eefined in 10 CFR 50.59,

c. Proposed changes to Technical Sf:3ccifications or this Operating License,

d. Violations of cedes, regulations, orders, 'Pechnical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance,

e. Significant operating abnormalities or deviations from normal and eJEf:3CCted performance of facility equif:3ment that affect nuclear safety, HOPE CREEK 6-10 Amendment No. 5 ADMINISTRATIVE CONTROLS

f. All REPORTABLE EVEPFPS.

g. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety, and

h. Reports and meeting minutes of the SORG.

AUDITS G.5.2.4:.3 Audits of facility activities shall he performed under the cognizance of the OSR staff. 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,

h. The performance, training ana E!'J:alifications of the entire facility staff at least once per 12 months,

c. The results of actions taken to correct deficiencies occurring in facility eeyuipment, structures*, systems, er method of operation that affect nuclear safety, at least once per G months,

d.

e.

The performance of activities reeyuired hy the Operational Quality Assurance Program to meet the criteria of AppendiJE B, 10 CFR Part 50, at least once per 24: months, The Facility Emergency Plan and implementing procedures at least once per 12 months,

f. The Facility Security Plan and implementing procedures at least once per 12 months,

g. Any other area of facility operation considered appropriate sy the Director Quality Assurance and Nuclear Safety Review or the Chief Nuclear Officer and President nuclear Business Unit.

h. The facility Fire Protection Program and the implementing procedures at least once per 24: months,

i. The fire protection and loss prevention program implementation at least once per 12 months utilizing either a eyualified off site licensee fire protection engineer(s) or an outside independent fire protection consultant. An outside independent fire protection con sultant shall he utilized at least once per 36 months, and

j. The radiological environmental monitoring program and the results thereof at least once per 12 months .

le. The OFFSITE DOSE CALCULATION HANU.'\L and implementing procedures at least once per 24: months, HOPE CREEK 6-11 Amendment No. ::t-=7-

ADMINISTRATIVE CONTROLS f)) 1. The PROCESS CONTROL PROGR.7\J1 and implementing procedures for process ing and packaging of radioactive wastes at least once per Z!4 months, aftd,-

m. The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per lZ!

months.

The above audits shall be conducted by the Quality Assurance Department or an independent consultant. Audit plans and final audit reports shall be reviewed by the OBR staff.

RECORDS MID REPORTS 6.5.Z!.4.4 Records of OBR activities shall be maintained. Reports of reviews and audits shall be prepared and distributed as indicated belo\i.

a. The results of reviews performed pursuant to Section 6.5.Z!.4.Z! shall be reported to the Chief Nuclear Officer and President nuclear Business Unit at least monthly .

b. *'\udit reports prepared pursuant to Specification 6.5.Z!.4.3 shall be forwarded by the auditing organization to the Chief Nuclear Officer and President nuclear Business Unit and to the management positions responsible for the areas audited (1) within 30 days after completion of the audit for those audits conducted by the Nuclear Quality Assurance Department, and (Z!) within GO days after completion of the audit for those audits conducted by an independent consultant.

6.5.Z!.5 ONBITE SAFETY REVIEW GROUP (BRO)

FUNCTION 6.5.Z!.5.l The BRO shall function to provide. the review of plant design and operating CJeperience for potential opportunities to improve plant safety, evaluation of plant operations and maintenance activities, and advice to management on the overall quality and safety of plant operations.

The BRO shall malee recommendations for revised procedures, equipment modifica tions, or other means of imprmring plant safety to appropriate station/corporate management.

REBPONBIBILITIEB G.5.Z!.5.2 The BRO shall be responsible for.

a. Review of selected plant operating characteristics, NRG issuances, industry advisories, and other appropriate sources of plant design and operating CJeperience information which may indicate areas for improving plant safety.

b. Review of selected facility features, equipment, and systems.

c. Review of selected procedures and plant activities including main tenance, modification, operational problems, and operational analysis.

HOPE CREEK 6-12 Amendment No. =7-f

ADMINISTRATIVE CONTROLS

~I 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 .

.tlJ'fHOR I TY 6.5.Zl.6 The N'uclear Safety Department shall report to and advise the Chief Nuclear Officer and President *Nuclear Business Unit on those areas of responsibility specified in Sections 6.5.Zl.i and 6.5.23:5.

6. 5 . 3 TECIIlHCAL REVIEW MID CONTROL ll:CTIYITIES 6.5.3.1 All programs and procedures required by Technical Specification 6.8 and changes thereto, and any other proposed procedures or changes thereto, which affect plant nuclear safety as determined by the General Manager Hope Creek Operations, other than editorial or typographical changes, shall be reviewed as follows.

PROCEDURE RELATED DOCUMENTS 6.5.3.Zl Procedures, Programs and changes thereto shall be reviewed as follo.,,,s.

a. Each newly created procedure, program or change thereto shall be

~

independently reviewed by an individual knowledgeable in the area affected other than the individual who prepared the procedure, pro gram or procedure change, but who may be from the same' organil2lation as the individual/group which prepared the procedure or procedure change. Procedures other than Station Administrative procedures will be approved by the appropriate station Department Manager or by the General Manager Hope Creek Operations. Each station Department Manager shall be responsible for a predesignated class of procedures.

The General Manager Hope Creek Operations shall approve Station ll:dministrative Procedures, Security Plan implementing procedures and Emergency Plan implementing procedures.

b. On the spot changes to procedures which clearly do not change the intent of the approved procedures shall be approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License. Revisions to procedures which may involve a change in intent of the approved procedures, shall be reviewed in accordance with Section 6.5.3.Zl.a above.

c. Individuals responsible for reviews performed in accordance with it :m 6.5.3.Zl.a above shall be approved by the SORG Chairman and designat:d as a Station Qualified Reviewer. A system of Station Qualified Reviewers shall be maintained by tfie SORG CB.airman. Eacfi review sfiall include a written determination of wfietfier or not additional

+ Ue'e l'.e:!r>eP.t:!iele :Eer :!ign off function.

HOPE CREEK 6-13 Amendment No. =

J

ADMINISTRATIVE CONTROLS cross disciplinary review is necessary. If deemed necessary, sueh review shall be performed by the appropriate designated review personnel. 'fhe Station Qualified Reviewers shall meet or meeeed the qualifications described in Section 4.1 and 4.7 of ANS 3.1, 1981.

d. If the Department Manager determines that tfie documents involved require a 10 CFR 50.59 safety evaluation, the documents sfiall be forwarded for SORG review and also to tfie OSR staff for an independent review to determine wfietfier or not an unreviewed safety question is involved. Pursuant to 10 CFR 50.59, "NRG approval of items involving unreviewed safety questions or requiring 'feehnieal Speeifieation changes sfiall be obtained prior to implementation.

NON PROCEDURE RELA'fED DOCUHEN'fS 6.5.3.3 'fests or e3Ef!eriments, and efianges to equipment or systems sfiall be forwarded for SORG review and also to tfie OSR staff for an independent review to determine wfietfier or not an unreviewed safety question is involved. 'fhe results of OSR staff reviews will be provided to SORG. Recommendations for approval are made by SORG to the General Han.ager Hope Creele Operations.

Pursua:at to 10 CFR 50. 59, NRG approval of items involvi:ag unrevim.*ed safety questio:as or requiring 'feehnieal Speeifieation eha:ages shall be obtained prior to impleme:atatio:a.

RECORDS MID REPOR'fS

6.5.3.4 Written records of reviews performed in aeeordanee witfi item 6.5.3.Z!a above, in.eluding recommendations for approval or disapproval, shall be maintained. Copies shall be provided to the General Han.ager Operations, SORG, the OSR staff, and/or NRG as necessary wfien tfieir reviews are required.

Hope Creek 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 submittal pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the SORC, and the results of this review shall be submitted to the OSR staff and the efti..ef.

Nuclear Officer and President "Nuclear Business Uflit~~~;:pp:]p§#gppijp§.

98'#~!@:;]?,f,;iif:i?~I

6.7. SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The NRC Operations Center shall be notified b tele hone as soon as

\

possible and in all cases within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The Chief Nuclear Officer and President N"uelear Business Unitsefribh:t&6E '::\diHfrk'htibte@iifbf:EiceT and the Director Quality Assurance aaclq J:iti~lear B~f;;"ti)* Review$¢'1;i:t(;)r "111111111111il~lllll~ll~l~~ll=~i,i.tll-~~1~1~1111illil~l.ll notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

8

'~!~*~******~*~**

HOPE CREEK 6-14 Amendment No. :::;..::;..

ADMINISTRATIVE CONTROLS

b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SORC. 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.

c. The Safety Limit Violation Report shall be submitted to the Commission, the Director Quality Assurance and Nuclear Safety

~~;.~~;lilllll~llllllllllllillll~illllllll~'~ll~l!~!l!~!l~::::::111::11:1111;11~11.*1:

andq t:.h.e Chief Nuclear Offieerq andqqPresidcntq Nuclear Business

~$.~#.~i#W##;ff]i#~~#.~Jj#.)i#:iWii#h#J#.$~~$$.~1# within 30 days of the violation.

d. Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

b. The applicable procedures required to implement the requirements of NUREG-0737 and supplements thereto.

c. Refueling operations.

d. Surveillance and test activities of safety-related equipment.

e. Security Plan implementation.

f. Emergency Plan implementation.

g. Fire Protection Program implementation.

h. PROCESS CONTROL PROGRAM implementation.

i. OFFSITE DOSE CALCULATION MANUAL implementation.

j. Quality Assurance Program for effluent and environment monitoring.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes t ereto, s a e reviewe and approved in accordance with specification 6 ..s. 1. 6 or 6. S. 3, as appropriate, prior to implementation and reviewed periodically as set forth in administrative procedures.

6.8.3 On-the-Spot changes to procedures of Specification 6.8.1 may be made provided:

a. The intent of the original procedure is not altered;

b. The change is approved by two members of the unit management staff, at least one of whom holds a Senior Reactor Operator license on the unit affected; and HOPE CREEK 6-15 Amendment No. ::+.:+

ADMINISTRATIVE CONTROLS

==================================================================

PROCEDURES AND PROGRAMS (Continued)

c. The chan e is documented and receives the same level of review and approval as the original procedure under Specification 6.5.3.2a within 14 days of implementation.

6.8.4 The following programs shall be established, implemented, and maintained:

a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the HPCI, CS, RHR, RCIC, Containment Hydrogen Recombiner, H2/02 analyzer, Post-Accident Sampling, Control

~ Rod Drive Hydraulic (Scram Discharge portion) systems. The program

\[;---,~I !\hall !'include the following:

1. Preventive maintenance and periodic visual inspection requirements, and

2. A service pressure leak test 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 vital areas under accident conditions. This program shall include the following:

1. Training of personnel,

2. Procedures for monitoring,. and

3. Provisions for maintenance of sampling and analysis equipment.

c. Post-accident Sampling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions.

The program shall include the following:

1. Training of personnel,

2. Procedures for sampling and analysis, and

3. Provisions for maintenance of sampling and analysis equipment.

HOPE CREEK 6-16

c.. *-

ADMINISTRATIVE CONTROLS

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6.13 PROCESS CONTROL PROGRAM (PCP) (Continued) 6.13.2 Licensee initiated changes to the PCP:

1. Shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information;

a. Sl:lffieie:atly detailed ififon1atio:a te totally support the

ratie:aale fer the eha:a~e without ee:aef it of additie:aal er L~~~~~~s~u~p~p~l~e=m:::..=.e~:a~t~a~l:__;i~:a~f~e~r~m~a::..:::t=i~e~R~j~~~~~~~~~~~~~~~~~~~~~~~

b. A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and

c. Documentation of the fact that the change has been reviewed and found acceptable by the SORC.

2. Shall become effective upon review and acceptance by the SORC.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2.Licensee initiated changes to the ODCM:

1. Shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);

b. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determination; and

c. Documentation of the fact that the change has been reviewed and found acceptable by the SORC.

2. Shall become effective upon review and acceptance by the SORC.

6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.15.1 Licensee initiated major changes to the radioactive waste system (liquid, gaseous and solid) :

1. Shall be reported to the Commission in the UFSAR for the period in which the evaluation was reviewed by SORC. The discussion of each change shall contain:

HOPE CREEK Amendment No. G-=t-

ML18101B178

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ML18101B178

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