ML18092A351

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Proposed Tech Specs Updating Nuclear Dept Organization, Station Operations Review Committee Membership & Quorum Requirements,Technical Review & Control & Nuclear Safety Review
ML18092A351
Person / Time
Site: Salem  PSEG icon.png
Issue date: 10/26/1984
From:
Public Service Enterprise Group
To:
Shared Package
ML18092A350 List:
References
LCR-84-24, NUDOCS 8411050326
Download: ML18092A351 (39)
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Text

PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS SALEM UNITS 1 AND 2 DESCRIPTION OF CHANGE LCR 84-24 Revise Section 6.0, Administrative Controls, to incorporate a change in Nuclear Department organization, Shift Complement clarification, Station Operations Review Committee (SORC) membership, quorum requirements, and responsibilities.

Additionally, replace the Nuclear Review Board (NRB) with Section 6.5.2, Nuclear Safety and Review, and add Section 6.5.3, Technical Review and Control.

REASON FOR CHANGE This amendment request incorporates recent Nuclear Department organizational changes addressing our September 1983 commitment to an in-depth analysis of the roles of the Vice President -

Nuclear and his Direct Reports.

The revised organizational structure which resulted from this analysis is shown on Figure 6.2-lo This revised organizational structure reduces the number of Direct Reports to the Vice President -

Nuclear and provides increased senior management direction, coordination and control to support Salem operations.

The key functions of Quality Assurance and Nuclear Safety Review will report directly to the Vice President -

Nuclear to provide independent authority in the execution of Department-wide quality assurance and safety review activities and to ensure ongoing senior management awareness and support of these programs.

The modification of SORC membership and quorum requirements will improve the quorum/membership ratio.

Pursuant to the NRC order dated May n, 1983, an Action Plan to improve Safety Review Management (SRM) activities was undertaken.

An evaluation of the existing SRM process and an examination of similar activities at several utilities was performed.

Based on the recommendations resulting from the above effort a restructured organization (as described below) was adopted by PSE&G.

The restructured SRM process provides for a designated safety review organization to perform the independent review and audit functions that were previously performed by NRB and SRG.

It also streamlines SORC activities.

This is expected to result in more timely, in-depth, independent reviews and to enhance safety review capability and accountability.

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The independent review and audit functions will be performed by the Station Operations Review Committee, and the General Manager -

Nuclear Safety Review who reports to the Vice President -

Nuclear.

The Nuclear Review Board will be discontinued.

The Nuclear Safety Review Department (NSR) will be responsible for the independent safety review program consisting of the Independent Safety Engineering Group (ISEG) functions and the standard technical specification functions that are generally performed by a company Nuclear Review Board.

NSR consists of a General Manager, a Manager of the On-Site Safety Review Group (SRG) supported by at least four dedicated, full-time engineers located on-site at Salem, and a Manager of the Off-Site Review Group (OSR) supported by at least four dedicated, full-time engineers located off-site.

The SRG will be primarily responsible for ISEG functions and the OSR will be primarily responsible for functions that are generally performed by a Nuclear Review Board.

However, depending on the need the resources of both SRG and OSR will be utilized, without organizational restrictions, in discharging overall review responsibilitie~ of NSR.

Another aspect of restructuring the safety review process is to streamline the SORC review process.

Important elements include:

1. Routine periodic review of procedures and changes thereto will be performed within the station organization, and only those items that have a safety significance will be referred to SORC for review.
2. SORC reviews will concentrate on consideration of safe and reliable operation of the station.

Independent reviews for determination or verification of USO will be performed by NSR and the results of NSR reviews will be provided to SORC.

3. A system of qualified reviewers within the station organization will be established to assist SORC review effort.

SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION This change is administrative in nature in that it provides an improved organization, clarification of shift coverage, adds a new full-time safety review*concept (which has the effect of improving the effectiveness of SORC Reviews and makes more efficient use of technical expertise available).

3 -

There are no changes in the probability or consequences of any previously evaluated accident nor in any margin of safety since review of all proposed changes to plant systems or equipment and review of safety evaluations for procedures, and changes thereto, completed under the provisions of 10CFR50.59 will continue to be th~ responsbility of SORC.

There are no modifications to plant equipment or operating procedures; therefore, the possibility of a new or different accident from any previously evaluated is not created.

The Commission has provided guidance concerning the application of the standards for a No Significant Hazards determination by providing examples of actions not likely to involve a Significant Hazards Consideration in the Federal Register (48FR14870).

One of the examples (ii) relates to changes that constitute an additional control not presently included in the technical specifications.

This change adds a Technical Review and Controls section that more clearly defines review responsibilities.

Example (i) related to purely administrative changes.

This change is basically a shifting of administrative responsibilities and improves the qualitative and quantitative effectiveness of the review functions.

Based on the above, and since the proposed change involves actions that conform to referenced examples in 48FR14870, we have determined that this application for amendment involves no Signf icant Hazards Consideration.

CHANGED PAGES FOR SALEM UNIT 1

ADMINISTRATIVE CONTROLS SECTION 6.1 RESPONSIBILITY

6. 2 ORGANIZATION 6.3 Offsite Facility Staff *****

Shift Technical Advisor FACILITY STAFF QJALIFICATIONS INDEX PAGE 6-1 6-1 6-1 6-6 6-6 6.4 TRAINING * * * * * * * * * * * * * * * * * * * * * * * * *

  • 6-6 6.5 REVIEW AND AUDIT 6.5.l STATION OPERATIONS REVIEW COMMITTEE Function Co mpo s i t i o n
  • Alternates Meeting Frequency
  • Q.Jorum **********

Responsibilities Review Process Authority

  • Records ****

6.5.2 NUCLEAR SAFETY REVIEW Function Compo s i ti o n * * * * * *

  • Consultants **********

Off-Site Review Group

  • Review *******.*****
  • Audits ********

On-Site Safety Review Group Responsibilities Authority ******

SALEM - UN IT 1 XVI II 6-7 6-7 6-7 5-_7 6-7 6-8 6-9 6-9 6-9 6-9 6-9 6-9a 6-9a 6-9a 6-10 6-11 6-11 6-11

INDEX ADMINISTRATIVE CONTROLS SECTION 6.5.3 TECHNICAL REVIEW AND CONTROL.

6.6 REPORTABLE EVENT ACTION 6.7 SAFETY LIMIT VIOLATION

  • 6.8 PROCEDURES AND PROGRAMS 6.9 REPORTING REOOIREMENTS 6.9.l ROUTINE REPORTS
  • 6.9.2 SPECIAL REPORTS 6.10 RECORD RETENTION *.....................

6.11 RADIATION PROTECTION PROGRAM................

6.12 HIGH RADIATION AREA 6.13 PROCESS CONTROL PROGRAM..................

6.14 OFFSITE DOSE CALCULATION MANUAL..............

6.15 MAJOR CHANGES TO RADIOACTIVE LIQJID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS *****

6.16 ENVIRONMENTAL C(JALIFICATION ***.............

SALEM - UN IT 1 XIX PAGE 6-12 6-12a 6-12a 6-13 6-15 6-19 6-19 6-21 6-21 6-22 6-22 6-23 6-24

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.l The General Manager - Salem Operations shall be responsible for overall facility operation and shall delegate in writing the succession to this respon-sibility 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 manageJTEnt directive to this effect, signed by the Vice President - Nuclear, shall be reissued to all station personne_l on an annual basis.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility manageJTEnt 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 composed of at least the minimum shift crew composition shown in Table 6.2-1.

b.

At least one licensed 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 tiJTEs.

c.

A health physics technician# shall be on site wh~n 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.

A site Fire Brigade of at least 5 members shall be maintained onsite at all tifllE!s#.

The Fire Brigade shall not include 4 JTEmbers of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

f.

The annunt of overtime ~rked by pl ant staff rrembers performing safety-related functions must be limited in accordance with the NRC Policy Statement on ~rking hours (Generic Letter No. 82-12).

  1. The health physics technician and Fire Brigade composition rnay be less than the minimum requireJTEnts for a period of tirre 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 accomnndate unexpected absence of the health physics technician and/or Fire Brigade members provided immediate action is taken to restore the health physics technician and/or Fire Brigade to within the minimum requirements.

SALEM -

UN IT 1 6-1

IWWEJI SAi.Eli SYSTEMS ENGlfERNl PERSINll..lfFAIBS MAHAG£R-MJa.EAR ASSISTANT va: PRES1!£NT NUCLEAR lfERA l10NS SlffGIT lllllAWI IEClwtCAL I Cll ENQNEERNl lllllAWI llC/El.ECTRt.11.

lllllAtEI ftJCl.EAR ENHmNG DESIGN ENGNEERNl MANAGER ME1lt00S Nil SYST!llS lllllAtEI ftJCl.EAR EMHERING CONTROL liEllERAl. MANACER IW.E.IR ASSllWU.

AND REGlUllON W:E PllESDEliT ENGl££RING ANO CON5'TRUtTl)j

___________ -~T~~T~~R~- __

  • ARTFU. ISLAlill

~PRESIDENT

. NUCl£AR Si'EaAI. l'Rll.6TS ADllHSTRA TllR PIJBUC AFFAIRS MAHA!IER-KJO.EAR MANA<EI HO!'E~

SYSTEMS EHGlfERNl IWWIER NUCLEAll USCENSriG Ntl Ra.JAllUTY lllllAWI LICENSNl l RElllAllON HOPE CRW.

WETY REVIEW GROUP llAHAl£R IW.E4R FUB.

MANACEH NICI.EAR IUMtHANCE SER\\1CES ASSISTANT ICE: l'RESDOO NUCLEAR IJ'EJllllONS BIR TECH!IOl.OGT ST.lfF GENERAL MANAf£R rt.a.ENI INDUSTRIAi.

N.Cl.EAR :iER\\li::ES RB.AllDNS MANAGER llANACEH RA!llAT~

PROID:TION SER\\1CES IUNAWI NUCLEAR SllE PROTECTION FIGURE 6.2-1 CORPORA TE HEADQUARTERS AND OFF-SITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT'----~

en I

&RD - Wi!OR mcftl! !J'ERl\\TDll Ill - R£talll !J'ERl\\TtR 6 EITHER T1£ lfERATllHi fM'UER Ill 1t£ lfERl\\lJl(j Eltl!ltiR 1111.L HEET T1£ WllflCATllHi OF ANSI Nl8H'111 FlJ! T1£ PllSITIIll IF lfERATIONS HNWE!. ALL SENllJ! liHIFT lilfERY!SlllS SHALL REPORT TO #l IMllVlll.W.. 'Ml 6WLL lll.D A liENllJl ~CTOR ll'ERATCR'S UtElliE ANl WIVE 6IX YEAR& OF RESPDH618LE l'tMR PlJWI EXPERIE!a IF WlllCH A llJlllNM IF li'D Y<MS 6WLL SE NUCLEAR POWER PLANT Elil'ERIENCE. A HAXllt.tt IF 11£ REHAINIMi Ml IF 1t£ l'EIWNING FlUI YEARS IF PMll PlNlr Elll'ER!Ela HAY BE FIUIUED BY 6ATISFACllJlY QffLETIGN OF Actal!IC DR RELATm TEDNCIL TIWNING DN A IJ£ TIME BASIS.

REil'INilll£ FOi Fll£ Pllll1'EC1DI l'llllliWI IKPlfl'ElflATllh tUTA llllUFIED AND FULFILLS liTA RWREHENTS IF TABLE i>N IF 6RD UtENSED llll.J.. BE AS&lliEl till.EAR SHIFT SUPERVI!illlY JlJ1IES.

OFFltt Nml!STRATtR OFFEE lilfER'llSIJI 6Tlff IWl!AlUJi PRGTECTIOM ElllllHfH llA!HlENANCE IWIAGER ftAWIEMNCE ENGINEER

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'TEOtiltlL A111180R *t GrutiAL ltlNAGER iWDt ll'ERATIONS A6SlllTIM' GENERAL llANAGER UTD.JIY ll'ERAllJlS

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ENGi!£ ER SENIOR IEICTlll SlfER'llSIJl ST ff ll c ENGINEER 1mtilCN..

WORKERS FIGURE 6

  • 2 - 2 FACILITY ORGANIZATION Q£MICllL ENGINEER SENIOR CllENISTAT SLPER\\'15111 TEDtllC.t.

WORKERS ND.ENI fl1£ AND UFETY

~STRllTIJI lllJliM FIRE PROTECTION 9J'E!MSalS FIRE IJllGl:lE STATl!Ji ll.llilTV llSS.IWa EllGINEER lfF*W:

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION SALEM UNIT 1 WITH UNIT 2 IN MODES 5 OR 6 OR DE-FUELED POSITION NUMBER OF INDIVIDUALS REQJIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 SNSS 1a 1a SRO 1b none STA 1b none NCO 2

1 EO/UO 3

2c Maintenance E l e ct r i c i an 1

none WITH UNIT 2 IN MODES 1, 2, 3 OR 4 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 SNSS 1a 1a SRO 1b none STA 1b none NCO 2

1 EO/UO 3d 1

Maintenance Electrician 1a none

~ Individual may fill the same position on Unit 2

'r]j Individual who fulfills the STA requirement may fill the saITE position on Unit 2.

The STA, if a licensed SRO, may concurrently fill the SRO insition on one unit; the other unit also requires a qualified SRO on shift.

~ One of the two required individuals may fill the insition on Unit 2, such that there are a total of three EO/UO's for both units.

Qi One of the three required individuals may fill the same position of Unit 2, such that there are a total of five EO/UO's for both units.

SALEM - UNIT 1 6-4

\\

SNSS SRO NCO STA EO/UO e

TABLE 6.2-1 (Continued)

Senior Nuclear Shift Supervisor with a Senior Reactor Operator License on both units.

Individual with a Senior Reactor Operator License on both units (normally, a Nuclear Shift Supervisor ).

Nuclear Control Operator with a Reactor Operator License on both units.

Shift Technical Advisor (if licensed as SRO, may be assigned duties as a Nuclear Shift Supervisor).

Equipment Operator or Utility Operator.

Except for the Senior Nuclear 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 accomrrodate the unexpected absence of on-duty shift crew members provided that 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 crewperson 's being late or absent.

During any absence of the Senior Nuclear Shift Supervisor from the Control Room area while the unit is in any MODE, an individual with a valid SRO License shall be designated to assume the Control Room command function.

SALEM - UNIT 1 6-5

ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall serve in an advisory capacity to the 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 1s 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 rrember of the facility staff shall JTEet or exceed the minimum qualifications of ANSI Nl8.l-1971 for comparable positions and the supplerrental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Radiation Protection Engineer who shall 11Eet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING 6.4.1 A retraining and replace11Ent training program for the facility staff shall be coordinated by P.ach functional level manager (Department Head) at the facility and maintained under the direction of the Manager - Nuclear Training and shall 11Eet or exceed the requirements and recommendations of Section 5.5 of ANSI Nl8.1-1971 and Appendix 11A 11 of 10 CFR Part 55 and the supple11Ental 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 program for the Fire Brigade shall be maintained under the direction of the Manager - *Nuclear Training and shall meet or exceed the requirements of Section 27 of NFPA Code-1975, except for Fire Brigade training sessions which shall be held at least quarterly.

SALEM - UNIT 1 6-6

ADMINISTRATIVE CONTROLS 6.5.1.l The Station Operations Review Committee shall function to advise the General Manager - Salem Operations on operational matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Station Operations Review Committee (SORC) shall be composed of:

Chairman:

Member and Vice Chairman:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

  • ALTERNATES Assistant General Manager - Salem Op~rations Maintenance Manager Operating Engineer I & C Engineer Senior Nuclear Sh.ift Supervisor Technical Engineer Maintenance Engineer Radiation Protection Engineer Chemistry Engineer Manager - On Site Safety Review Gro.up or his designee.

6.5.1.3 All alternate members shall be appointed in writing by the SORC Chairman.

a.

Vice Chairmen shall be members of Station management.

b.

No fl'Ore than two alternates to members shall participate as voting J!lE!mbers in SORC activities at any one meeting.

c.

Alternate appointees will only represent their respective depart1TEnt.

d.

Alternates for members will not make up part of the voting quorum when the members the alternate represents is al so present.

MEE TI NG FRE QJENC Y 6.5.1.4 The SORC shall meet at least once per calendar rronth and as convened by by the SORC Chairman or his designated alternate.

QJORUM 6.5.1.5 The minimum quorum of the SORC 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 five members including alternates.

SALEM - UNIT 1 6-7 I

i l !

  • I I

\\

ADMINISTRATIVE CONTROLS RESPONSIBILITIES

  • 6.5.1.6 The Station Operations Review Committee shall be responsible for:
a.

Review of: (1) Station Administrative Procedures and changes thereto and (2) Newly created procedures or changei to existing procedures that involve a significant safety issue 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 ~hanges to Appendix "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 10CFR50.59.
f.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports.covering eva 1 uatio n and recommendations to prevent recurrence to the Vice President - Nuclear and the General Manager - Nuclear Safety Review.

g.

Review of all REPORTABLE EVENTS.

h.

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 or General Manager - Nuclear Safety Review.

j. Review of the Facility Security Plan and implementing procedures and submittal of recommended changes to the General Manager - Nuclear Safety Review.
k.

Review of the-Facility Emergen~y Plan and implementing procedures and submittal of recommended changes, to the General Manager - Nuclear Safety Review.

1. Review of the Fire Protection Program and implementing procedures and submittal of recommended. changes to the General Manager - Nuclear Safety Review.
m.

Review of all unplanned on-site releases of radioactivity to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President - Nuclear and the General Manager - Nuclear Safety Review.

n.

Review of changes to the PROCESS CONTROL MANUAL and the OFF-SITE DOSE CALCULATION MANUAL.

SALEM UNIT 1 6-8

ADMINISTRATIVE CONTROLS SORC REVIEW PROCESS 6.5.1.7 A technical review and control system utilizing qualified reviewers shall function to perform the periodic or routine review of procedures and changes thereto. Details of this technical review process are provided in Se ct ion 6. 5. 3.

AUTHORITY 6.5.1.8 The Station Operations Review Committee shall:

a.

Recommend to the General Manager - Salem Operations written approval or disapproval of items considered under 6.5.1.6 (a) through (e) above.

b.

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 Vice President -

Nuclear and the General Manager -

Nuclear Safety Review of disagreement between the SORC and the General Manager - Salem Operations; however, the General Manager - Salem Operations shall have responsibility for re so 1 ut ion of such di sagreerrents pursuant to 6.1.1 above.

RECORDS 6.5.1.9 The Station Operations Review Committee shall maintain written minutes of each rreeting and copies shall be provided to the Vice President - Nuclear, the General Manager - Nuclear Safety Review and the Manager - Off-Site Review.

6.5.2 NUCLEAR SAFETY REVIEW FUNCTION 6.5.2.1 The Nuclear Safety Review Department (NSR) shall function to provide the independent safety review program and aud1t of designated activities.

COMPOSITION 6.5.2.2 NSR shall consist of the General Manager - Nuclear Safety Review, the Manager - On-Site Safety Review Group (SRG), who is supported by at least four dedicated, full-time engineers located on-site, and the Manager Off-Site Review Group (OSR) who is supported by at least four dedicated, full-tirre engineers located off-site.* The OSR staff shall possess experience and competence in the general areas listed in Section 6.5.2.4.

The General Manager and Managers shall determine when additional technical experts should assist in reviews of complex pro bl ems.

NSR shall utilize a system of qualified reviewers from other technical organizations to augmenf its expertise in the disci~lines of Section 6.5.2.4.

Such qualified reviewers shall meet the sarre qualification requirements as. the NSR staff, and will not have been involved with performance of the original WJrk.

    • Since the Nuclear Department is located on Artificial Island site, the terms "on-site" and 11off-site 11 convey the distinction between inside and outside the station fence, respectively SALEM - UNIT 1 6-9 r

I l

  • 1 I I i

I l

ADMINISTRATIVE CONTROLS The Manager - Off-Site Review and Staff shall meet or exceed the qualifications described in Section 4.7 of ANS 3.1(1981) and shall be guided by the provisions for independent review described in Section 4.3 of ANSI Nl8.7 (1976) (ANS 3.2).

The Manager - On Site Review and staff will rtEet or exceed the qualifications described in Section 4.4 of ANS 3.1 (1981).

CONSULTANTS 6.5.2.3 Consultants shall be utilized as determined by the General Manager -

Nuclear Safety Review to provide expert advice to the NSR.

OFF-SITE REVIEW GROUP 6.5.2.4 The Off-Site Review Group (OSR) 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.

~a 1 ity Assurance

j. Nondestructive Testing
k.

Emergency Preparedness The OSR shall also function to examine plant operating characteristics, NRG issuances, industry advisories, Licensee Event Reports, and other sources which may indicate areas for improving plant safety.

REVIEW 6.5.2.4.l The OSR shall review:

a.

Safety Evaluations for

1)

Changes* to procedures, equipment, or systems and

2)

Tests or exp_eriments completed under the provisions of Section 50.59, 10CFR, to verify that such actions did not constitute an unreviewed safety question.

SALEM - UNIT 1 6-9a

ADMINISTRATIVE CONTROLS

b.

Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in Section 50.59, 10CFR.

c.

Proposed tests or experiments that involve an unreviewed safety question as defined in Section 50.59, 10CFR.

d.

Proposed changes to Technical Specifications or to the 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~ All REPORTABLE EVENTS.

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 meeting minutes of the Station Operations Review Committee.

AUDITS 6.5.2.4.2 Audits of facility activities that are required to be performed under the *cognizance of OSR are listed below:

a.

The conformance of facility operation to prov1s10ns contained within the Technical Specifications and applicable license conditions at least o nee per 12 months.

b.

The performance, training, and qualifications of the entire facility staff at least once per 12 roonths.

c.

The results of actions.taken to correct deficiencies occurring in facility equipment, structures, syste111s, or method of operation that affect nuclear safety at least once per 6 rronths.

d.

The performance of activities required by the Operational Q.iality Assurance Program to meet the Criteria.of Appendix 118 11

, 10CFR50, at least o nee per 24 months *.

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

f.

Th!=! Facility Security Plan and implementing procedures at least once per 12 months.

g.

Any other area of facility operation considered appropriate by the General Manager - Nuclear Safety Review or the Vice President - Nuclear.

SALEM - UNIT 1 6-10 I

I

\\

i I

1.

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ADMINISTRATIVE CONTROLS

k.

The radiological environnEntal nnnitoring program and the results thereof at least once per 12 roonths.

The above audits shall be conducted by the Nuclear ()Jal ity Assurance Department or an independent consultant as required.

Audit results and recomnEndations shall be reviewed by OSR.

ON-SITE SAFETY REVIEW GROUP 6.5.2.5 The On-Site Safety Review Group (SRG) shall function to provide:

the review of plant design and operating experience for potential opportunities to improve plant safety; the evaluation of plant operations and maintenance activities; and advice to management on the overall quality and safety of plant operations.

The SRG sha*ll make recomrrEndat ions for revised procedures, equi prrEnt nndifi cations, or other rrEans of improving pl ant safety to appropriate station/

corporate managerrEnt.

RESPONSIBILITIES 6

  • 5
  • 2
  • 5
  • 1 The SR G s ha 11 be re s po n s i b 1 e fa r :
a.

Review of selected plant operating characteristics, NRC issuances, industry advisories, and other appropriate sources of plant design and operating experience information that may indicate areas for improving pl ant safety.

b.

Review of selected facility features, equipment, and systems.

c.

Review of selected procedures and plant activities including maintenance, nndification, operational problems, and operational analysis.

d.

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

NSR AUTHORITY 6.5.2.6 NSR shall report to and advise. the Vice President - Nuclear on those areas of responsibility specified in Sections 6.5.2.4 and 6.5.2.5.

6.5.2.7 Records of NSR activities shall be prepared and maintained.

Reports of reviews and audits shall be distributed as follows:

a.

Reports of reviews encompassed by Section 6.5.2.4.1 above, shall be prepared, approved and forwarded to the Vice President - Nuclear, within following completion of the review.

  • Not responsible for sign-off function SALEM - UNIT 1 6-11 i -

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ADMINISTRATIVE CONTROLS

b.

Audit reports encompassed by Section 6.5.2.4.2 above, shall be forwarded to. the Vice President - Nuclear and to the management ix>sitions responsible for the areas audited within 30 days after completion of the audit.

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Programs required by Technical Specification 6.8 and other procedures which affect nuclear safety as determined by the General Manager - Salem Operations, other than editorial or typographical changes, shall be. reviewed as fallows:

PROCEDURE RELATED DOCUMENTS 6.5.3.2 Procedures, Program and changes thereto shall be reviewed as follows:

a.

Each newly created. procedure, program or change thereto shall be independently reviewed by an individual knowledgeable in the subject area other t_han the individual who prepared the procedure, program or procedure change, but who may be from the same organization as the individual/group which prepared the procedure or procedure change.

Procedures other than Station Administrative procedures will be approved by the appropriate Station Department Manager or by the Assistant.

General Manager - Salem Operations.

Each Station Department Manager shall be responsible for a predesignated class of procedures.

The General Manager - Salem Operations shall approve Station Administrati~e Procedures, Security Plan implementing procedures and Emergency Plan implementing procedures.

b.

On-the-spot changes to procedures which clearly cb 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 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
  • 2
  • a a bo ve *
c.

Individuals responsible for reviews performed in accordance with item shall be approved by the SORC Chairman and designated as Qualified Reviewers.

A system of Qualified Reviewers shall be maintained by the SORC Chairman.

Each review shall include a written determination of whether or not additional cross-disciplinary review is necessary. *If deemed necessary, such review shall be performed by the appropriate designated review perso~nel.

d.

If the Department Manager determines that the documents involved contain significant safety issues, the documents shall be forwarded for SORC review and also to NSR for an independent review to deter.mine whether or not an unreviewed safety question is involved.

Pursuant to 10CFR50.59, NRC approval of items i nvo 1 vi ng unrevi ewed safety questions or Technica 1 Specification changes shall be obtained prior to impl ementat ion.

SALEM -

UN IT 1 6-12

)

ADMINISTRATIVE CONTROLS.

NON-PROCEDURE RELATED DOCUMENTS 6.5.3.3 Tests or experiments, changes to Technical Specifications, and changes to equipment or systems shall be reviewed as described in items 6.5.3.2a, c, and d above.

Recommendations for approval are made by SORC to the General Manager Manager - Salem Operations.

Pursuant to 10CFRS0.59, NRC approval of items involving unreviewed safety questions or requiring Technical Specification changes shall be obtained prior to implementation.

RECORDS 6.5.3.4 Written records of reviews performed in accordance with itme 6.S.3.2a above, including recommendations for approval or disapproval, shall be maintained. Copies shall be provided to the General Manager - Salem Operations, SORC, NSR and/or NRC 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 Report submitted to NSR and the Vice President - Nuclear.

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 pl aced 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 Vice President - Nuclear and General Manager - Nuclear Safety Review 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 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.

The Safety Limit Violation Report shall be submitted to the Commission, the ~eneral Manager - Nuclear Safety Review and the Vice President -

Nuclear within 14 days of the violation.

SALEM - UN IT 1 6-12a I

I 1

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 11A 11 of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

d.

Security Pl an implementation.

e.

Emergency Plan implementation.

f.

Fi re Protect ion Pro gram implementation.*

g.

PROCESS CONTROL PROGRAM im.plementation.

h.

OFFSITE DOSE CALCULATION MANUAL implementation.

i.

~ality Assurance Program for effluent and environmental nonitoring.

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 appropriate, prior to implementation and reviewed periodically as set forth in ad mini strati ve 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 ci>cumented and receives the same level of re 5

view 2

and I __

approval as the original procedure under Specification 6 ** 3. a within 14 days of implementation.

SALEM - UNIT 1 6-13

CHANGED PAGES FOR SALEM UNIT 2

INDEX ADMINISTRATIVE CONTROLS SECTION 6.1 RESPONSIBILITY ***********************

~~~~~~~~-

6.2 ORGANIZATION 6.3 Offsite Facility Staff *****

Shift Technical Advisor FACILITY STAFF QJALIFICATIONS...............

6.4 TRAINING * * * *......................

6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE Function Co mpo sit i o n Alternates Meeting Frequency QJorum.....

Responsibilities...

Review Process....

Authority....

Records.....

6.5.2 NUCLEAR SAFETY REVIEW Function ****

Compo s it i o n * *

  • Consult ants * **
  • Off-Site Review Group
  • Review Audits 0

On-Site Safety Review Group Res pons i bil it i es Authority ******

SALEM -

UN IT 2 XVI II PAGE 6-1 6-1 6-1 6-6 6-6 6-6 6-7 6-7 6-7 6-7 6-7 6-8 6-9 6-9 6-9 6-9 6-9 6-9a 6-9a 6-9a 6-10 6-11 6-11 6-11

INDEX ADMINISTRATIVE CONTROLS SECTION 6.5.3 TECHNICAL REVIEW AND CONTROL................

6.6 REPORTABLE EVENT ACTION..................

6.7 SAFETY LIMIT VIOLATION

  • 6.8 PROCEDURES AND PROGRAMS. * * *
  • 6.9 REPORTING REQJIREMENTS 6.9~1 ROUTINE REPORTS....

6.9.2.SPECIAL REPORTS

  • 6~10 RECORD RETENTION......

6.11 RADIATION PROTECTION PROGRAM 6.12 HIGH RADIATION AREA 6.13 PROCESS CONTROL PROGRAM..................

6.14 OFFSITE DOSE CALCULATION MANUAL..............

6*.15 MAJOR CHANGES TO RADIOACTIVE LIQJID, GASE.OLIS AND SOLID WASTE TREATMENT SYSTEMS *****

SALEM -

UN IT 2 XIX PAGE 6-12 6-12a 6-12a

  • 6-13 6-15 6-19 6-19 6-21 6-21 6-22 6-22 6-23

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager - Salem Operations shall be responsible for overall facility operation and shall delegate in writing the succession to this respon-sibility 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 Vice President - Nuclear, shall be reissued to all station personnel on an annual basis.*

6.2 ORGANIZATION OFF SITE 6.2.1 The offsite organization for facility management 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 shal 1 be composed of at least the mini mum shift crew composition shown in Table 6.2-1.

b.

At 1 east one 1 i censed Operator shall be in the control room when fue 1 is in the reactor.

In addition, at least one licensed Senior Reactor I

Operator shall be in the Control Room area at all times.

l

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 1 i censed Senior Reactor Operator who has no other concurrent responsi-bilities during this operation.

e.

A site Fire Brigade of at least 5 members shall be maintained onsite at all times#.

The Fire Brigade shall not include 4 members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

f.

The amount of overtime 'l.Orked by plant staff members performing safety-related functions must be limited in accordance with the NRC Policy Statement on 'l<<>rking hours (Generic Letter No. 82-12).

  1. The health physics technician and Fire Brigade composition may be less than the minimum requirements for a period of tirre 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 accomrmdate unexpected absence of the health physics technician and/or Fire Brigade members providec:t immediate action is taken to restore the health physics technician and/or Fire Brigade to within the minimum requirements.

SALEM - UNIT 2 6-1.

llAIWEI llANAIEJI SAi.Eii llCllNfCAL I CYL SYSTEllS EHGHERl<<l ENCINEERW ASSISTAHT.

VEE PIEllOO NutlEAR <l'EJIATIOHS SffOIT llAHAGER llETHOOS NlJ SYSTEllS flJBUC AFFAIRS MANl.GEIHtXlW llANAIEJI MANAra MANMiER MW.IE!

I l C I El..ECTRCIJ.

MJCl.EAR ~G MJCl.EAR oomtlG Hllf'l ~

WE PR£SIEIT EllGWRING AllO COMSTRUCTOI

___________ -~T~~~~R~- __

  • AllTFC>.L !SUND W:E PAESIDOO lllCL!AR ll'EaAL l'RWTS AllllHSTRA TOR llANAIEI NUru:AA USCENSfjG NG REIJABUIY HOPE CRE.E.K SAFETY REVIEW GROUP Bl R TECltNOLOGT STAFF lllNAGal OUTMI SERYEES ASSISTANT Yl:E P!ESllOO NUCLEAR IFERIT10HS GEllERll. ~ N.a.EAR lllDUSTRIA!.

N.a.EAR SEllVW REI.A TIO NS MANAGER ENCINEERW DESl(IN CONTROL SYSTEMS EHGHERl<<l liW\\4f£A LWSHl l RE!UATlON M.IHl.C£R N.a.EAR FUEL llANAIER NJClfAR llAM'ElllNCE SEIMCES llANAGEJl RADIATOI PROJECTION SEIMCES MW.WI NUCLEAR SITE PRam:TlON IWW£R IW.EAR TRAINHl FIGURE 6.2-1 CORPORATE HEADQUARTERS AND OFF-SITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT,

Sii

  • SENIOR REACTtll CfERATtll ill - ROCTlll IJ'EIA!lJI

& EITHER 11£ ll'ERATill6 ~

Ill 11£ ll'ERAllMl EIGIEEH W.L HEEi 11£ !lA.IFICAllIHi OF ANSI h19J-l'i7l FIJI 11£ PDSllllli IF IHMTIDNS HtHaR. fil &eillll SHIFT SlfER'llStRS SHALL REPORT ID #j INJIWJll.W.. ~

SWil lllll A SEN!tll REAC!aR IJ'ERAllJl'S LIWiE ANl WIVE SIX YEARi OF RElil'ONSlSLE PIMR PllM EXPERIEll:E IF lfftH A "IN!ltJ4 IJ' lW YE/IRS SWil BE NUCLEAR POWER Pl.ANT ElfERIEMCE. A HAXlltl1 IJ' 11£ REHAINOO lW IF 11£ REi.\\lhlNG FUR wtMi IF PIMR PUHi' Elll'ElllE!a: HAY SE Fl.lFJl..l..EO SY 6ATlifACllJfl CllflE1IDN OF AetafflC DR RELATED TEDta. IRAINING DN A 11£ TIHE BASIS.

R£51Q,Slll£ Fiii FlRE ~

PRIDW! IHl'WfHTAll!Ji.

H liTA llWJFIED AND FULFD.lS li!A R£IlJIREHENl6 IF TAlll..E S.Z*L IF SR!l WISED WIU. BE ASSIBD Nn£AR SHIFT SUPERVISlllY W1lE6.

&EllERAL MANAGER Slilll IJ'ERAIJONS

+------1 SORC lffl:E Nlli&IRATlll IWIJATJ!Jj PRDIECTIQN ENlilllEER MAIMIENANCE IWIABER l!AIKIENNICE EllGlNEER 9ilFT 1mtllCA.

ICMIOR H UID.lTY ll'£RA llllS TEDtaI:IL WORKERS FIGURE -6_

  • 2 - 2 FACILITY ORGANIZATION Cl£MittL ENGlNEEA _

SENIOR CHEnlSTRT SlfERVJSal TEDtaI:IL WORKERS HAHAGER-llUCLENI SITE PllllWD

  • lllWft Fff AND SAFETY NCNISIRATIJI FIRE EllIGta STATllJj llVilTY "5\\UWa EJIGJNEER STlfF

POSITION SNSS SRO STA NCO EO/UO Maintenance POSITION SNSS SRO STA NCO EO/UO Maintenance TABLE 6. 2-1 MINIMUM SHIFT CREW COMPOSITION SALEM UNIT 2 WITH UNIT 1 IN MODES 5 OR 6 OR DE-FUELED NUMBER OF INDIVIDUALS REWIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 la la lb none lb none

  • 2 1

3 2C E 1 e ctr i c i an 1

none WITH UNIT 1 IN MODES 1, 2, 3 OR 4 E 1 e ctr i c i an NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2' la*

lb lb 2

3d la 3 & 4 MODES 5 & 6 none none 1

1 none y

Individual may fill the same position on Unit 1 Q_/

Individual who fulfills the STA requirement may fill the same position on Unit 1.

The STA, if a licensed SRO, may concurrently fill the SRO position on one unit; the other unit also requires a qualified SRO on shift.

£1 One of the two required individuals may fill the position on Unit 1, such that there are a total of three EO/UO 's for both units.

~ One of the three required individuals may fill the same position of Unit 1, such that there are a total of five EO/UO 's for both units.

SALEM - UNIT 2 6-4

SNSS SRO NCO STA EO/UO TABLE 6.2-1 (Continued)

Senior Nuclear Shift Supervisor with a Senior Reactor Operator License on both units.

Individual with a Senior Reactor Operator License on both units (normally, a Nuclear Shift Supervisor ).

Nuclear Control Operator with a Reactor Operator License on both units.

Shift Technical Advisor (if licensed as SRO, may be assigned duties as a Nuclear Shift Supervisor).

Equipment Operator or Utility Operator.

Except for the Senior Nuclear 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 accomrrndate the unexpected absence of on-duty shift crew members provided that 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 crewperson 1s being late or absent.

During any absence of the Senior Nuclear Shift Supervisor from the Control Room area while the unit is in any MODE, an tndividual with a valid SRO License shall be designated to assume the Control Room command function.

SALEM - UNIT 2 6-5

  • ~

\\

I ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1. The.Shift Technical Advisor shall serve in an advisory capacity to the 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 scientifi~ or engineering discipline with specific training in plant design.and response and analysis of the plant for transients and accidents.

6.3 FACILITY STAFF QJALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI Nl8.l-1971 for comparable positions and the supplemental requirements specifted in *Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Radiation Protection Engineer who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING 6.4.l A retraining and replacement training program for the facility staff shall be coordinated by each functional level 111anager (Department Head) at the facility and maintained under the direction of the Manager - Nuclear Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.l-1971 and Appendix 11A 11 of 10 CFR Part 55 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 program for theFire Brigade shall be maintained under the direction of the Manager - Nuclear Training and shall meet or exceed the requirements of Section 27 of NFPA Code-1975, except for Fire Brigade training sessions which shall be held at least quarterly.

SALEM -

UN IT 2 6-6

ADMINISTRATIVE CONTROLS 6.5.1.l The Station Operations Review Committee shall function to advise the General Manager - Salem Operations on operational matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Station Operations Review Committee (SORC) shall be composed of:

Chairman:

Member and Vice Chairman:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

ALTERNATES Assistant General Manager - Salem Operations Maintenance Manager Operating Engineer I & C Engineer Senior Nu cl ear Shift Super visor Technical Engineer Maintenance Engineer Radiation Protection Engineer Chemistry Engineer Manager - On Site Safety Review Group or his designee.

6.5.1.3 All alternate members shall be appointed in writing by the SORC Chairman.

a.

Vice Chairmen shall be members of Station management.

b.

No nnre than two alternates to members shall participate as mting

.members in SORC activities at any one meeting.

c.

Alternate appointees will only represen~ their respective department.

d-.

Alternates for members will not make up part of the voting quorum when the members the alternate represents is also present.

MEETING FRE QJENC Y 6.5.1.4 The SORC shall meet at least once per calendar rronth and as convened by by the SORC Chairman or his designated alternate.

QJORUM 6.5.1.5 The minimum quorum of the SORC necessary for the performance of the SORC res pons i bil ity and authority provisions of these techni ca 1 specifi cations shall consist of the Chairman or his designated alternate and five members including alternates.

SALEM -

UN IT 2 6-7

ADMINISTRATIVE CONTROLS RESPONSIBILITIES 6.5.1.6 The Station Operations Review Committee shall be responsible for:

a.

Review of: (1) Station Administrative Procedures and changes thereto and (2) Newly created procedures or changes to existing procedures that involve a significant safety issue 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 Appendix 11A 11 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 l

provisions of 10CFR50.59.

f.

Investigation of all violations of the Technical Specifications i-ncluding the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President - Nuclear and l the General Manager - Nu cl ear Safety Review.

g.

Review of all REPORTABLE EVENTS.

h.

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 - Sal em Operations or General Manager - Nuclear Safety Review.

j. Review of the Facility Security Pl an and implementing procedures and l

submittal of recommended changes to the General Manager - Nuclear Safety Review.

k.

Review of the Facility Emergency Plan and implementing procedures and submittal of recommended changes to the General Manager - Nuclear Safety Review.

1. Review of the Fire Protection Program and implementing procedures and submittal of recommended changes to the General Manager - Nu cl ear Safety Review.
m.

Review of all unplanned on-site releases of radioactivity to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President - Nuclear and the I*

General Manager - Nuclear Safety Review.

I

n.

Review of changes to the PROCESS CONTROL MANUAL and the OFF-SITE DOSE CALCULATION MANUAL.

SALEM - UNIT 2 6-8

,_,. f ADMINISTRATIVE CONTROLS SORC REVIEW PROCESS 6.5.1.7 A technical review and control system utilizing qualified reviewers shall function to perform the periodic or routine review of procedures and changes thereto. Details of this technical review process are provided in Se ct i o n 6

  • 5 ~ 3
  • AUTHORITY 6.5.1.8 The Station Operations Review Committee shall:
a.

Recommend to the General Manager - Salem Operations written approval or disapproval of items considered under 6.5.1.6 (a) through (e) above.

b.

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 Vice President -

Nuclear and the General Manager -

Nuclear Safety Review of disagreement between the SORC and the General Manager - Salem Operations; however, the General Manager - Salem Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.9 The Station Operations Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Vice Presi"dent - Nuclear, the General Manager - Nuclear Safety Review and the Manager - Off-Site Review.

6.5.2 NUCLEAR SAFETY REVIEW FUNCTION 6.5.2.1 The Nuclear Safety Review Department (NSR) shall function to provide the independent safety review program and audit of designated activities.

COMPOSITION 6.5.2.2 NSR shall consist of the General Manager - Nuclear Safety Review, the Manager - On-Site Safety Review Group (SRG), who is supported by at least four dedicated, full-time engineers located on-site, and the Manager Off-Site Review Group (OSR) who is supported by at least four dedicated, full-titre engineers located off-site.* The OSR staff shall possess experience and competence in the general areas listed in Section 6.5.2.4.

The General Manager and Managers shall determine when additional technical experts should *assist in reviews of complex problems.

NSR shall utilize a system of qualified reviewers from other technical organizations to augment its expertise in the disciplines of Section 6.5.2.4.

Such qualified reviewers shall meet the sarre qualification require1TEnts as the NSR staff, and will not have been involved with performance of the original 't.Ork.

  • Since the Nuclear Departll'Ent is located on Artificial Island site, the terms "on-site" and 11off-site 11 convey the distinction between inside and outside the station fence, respectively.

SALEM - UN IT 2 6-9 r

i l I

  • j j

i

'I

ADMINISTRATIVE CONTROLS The Manager - Off-Site Review and Staff shall meet or exceed the qualifications described in Section 4.7 of ANS 3.1(1981) and shall be guided by the provisions for independent review described in Section 4. 3 of ANSI Nl8. 7 ( 1976) (ANS 3. 2).

The Manager - On Site Review and staff will 11Eet or exceed the qualifications described in Section 4.4 of ANS 3.1 (1981).

CONSULTANTS 6.5.2.3 Consultants shall be utilized as determined by the General Manager -

Nuclear Safety Review to provide expert advice to the NSR.

OFF-SITE REVIEW GROUP 6.5.2.4 The Off-Site Review Group (OSR) 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.

Metal 1 urgy

e.

Instrumentation and Control

f.

Radiological Safety

g.

Mechanical Engineering

h.

Electrical Engineering

i.

Q.ial ity Assurance

j. Nondestructive Testing
k.

Emergency Preparedness The OSR shall also function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources which may indicate areas for improving plant safety.

REVIEW 6.5.2.4.1 The.OSR shall review:

a.

Safety Evaluations for

1)

Changes to procedures, equipment, or systems and

2)

Tests or experiments completed under the pro visions of Section 50. 59, 10CFR, to verify that such actions did not constitute an unreviewed safety question.

SALEM - UNIT 2 6-9a l

\\.

I..

    • .~-~*

~!

.e ADMINISTRATIVE CONTROLS

b.

Proposed changes to procedures, equipment, or systems that involve an unreviewed safety question as defined in Section 50.59, 10CFR.

c.

Proposed tests or experiments that involve an unreviewed safety question as defined in Section 50.59, 10CFR.

d.

Proposed changes to Technical Specifications or to the 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 pl ant equipment that affect nuclear safety.

g.

All REPORTABLE EVENTS.

h.

All recognized indications of an unanticipated deficiency in some* aspect of *design or operation of safety-related structures, systems or co mpo ne nt s *

i. Reports and meeting minutes of the Station Operations Review Committee.

AUDITS 6.5.2.4.2 Audits of facility activities that are required to be performed under the.cognizance of OSR are listed below:

a.

The conformance of faciTity operation to prov1s1ons contained within the Technical Specifications and* applicable license conditions at least once per 12 nnnths.

b.

The performance, training, and qualifications of the entire facility staff at least once per 12 nnnths.

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 roonths.

d.

The performance of activities required by the Operational Quality Assurance Program to meet the Criteria of Appendix 118 11

, 10CFR50, at least o nee per 24 nnnths.

e.

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

f.

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

g.

Any other area of facility operation considered appropriate by the General Manager -

Nu cl ear Safety Review or the Vice President - Nu cl ear.

SALEM - UNIT 2 6-10

ADMINISTRATIVE CONTROLS

k.

The radiological environrrental 11Dnitoring program and the results thereof at least once per 12 rrnnths.

The above audits shal 1 be conducted by the Nuclear ~al ity Assurance Department or an independent consultant as required. Audit results and recomrrendations shall be reviewed by OSR.

ON-SITE SAFETY REVIEW GROUP 6.5.2.5 The On-Site Safety Review Group (SRG) shall function to provide:

the review.of plant design and operating experience for potential opportunities to improve plant safety; the evaluation of plant operations and maintenance activities; and advice to management on the overall quality and safety of plant o pe r at i o n s

  • The SRG shall make recomrrendations for revised procedures, equi prrent 11Ddifications, or other rreans of improving plant safety to appropriate station/

corporate management.

RESPONSIBILITIES 6.5.2.5.l The SRG shall be responsible for:

a.

Review of selected plant operating characteristics, NRC issuances, industry advisories, and other appropriate sources of plant design and operat i n.g experience information that may iildi cate areas for i mpro vi ng pl ant safety.

b.

Review of selected facility features, equipment, and systems.

c. Review of selected procedures and plant activities including maintenance, 11Ddification, 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.

NSR AUTHORITY 6.5.2.6 NSR shall report to and advise the Vice President - Nuclear on those areas of responsibility specified in Sections 6.5.2.4 and 6.5~2.5.

6.5.2.7 Records of NSR activities shall be prepared and maintained.

Reports of reviews and audits shall be distributed as follows:

a. Reports of reviews encompassed by Section 6.5.2.4.1 above, shall be prepared, approved and forwarded to the Vice President - Nuclear, within fol lowing completion of the review.
  • Not responsible for sign-off function SALEM - UNIT 2 6-11 I

I I i \\

i !

I

-,a..-,.

\\:)

ADMINISTRATIVE CONTROLS

b.

Audit reports encompassed by Section 6.5.2.4.2 above, shall be forwarded to the Vice President - Nuclear and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Programs required by Technical Specification 6.8 and other procedures which affect nuclear safety as determined by the General Manager - Salem Operations, other than editorial or typographical changes, shal 1 be reviewed as follows:

PROCEDURE RELATED DOCUMENTS 6.5.3.2 Procedures, Program and changes thereto shall be reviewed as follows:

a.

Each newly created procedure, program or change thereto shall be independently reviewed by an individual knowledgeable in the subject area other than the individual who prepared the procedure, program or procedure change, but who may be from the* same organization as the individual/group which prepared the procedure or procedure change.

Procedures other than Station Administrative procedures will be approved by the appropriate Station Department Manager or by the Assistant General Manager - Salem Operations.

Each Station Department Manager shall be responsible for a predesignated class of procedures.

The General Manager - Salem Operations shall approve Station Administrative Procedures, Security Plan implefll!nting procedures and Emergency Plan*

implementing procedures.

b.

On-the-spot changes to procedures which clearly do not change the intent of the approved procedures shal 1 be approved by t'V.Q members of the plant management staff, at least one of whom ho 1 ds a Senior Reactor Operator 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
  • 2
  • a a bo ve *
c.

Individuals responsible for reviews performed in accordance with item shall be approved by the SORC Chairman and designated as Qualified Reviewers.

A system of Q.lal ified Reviewers shall be rnai ntai ned by the SORC Chairman.

Each review shall include a written determinatio-n of whether or not additional cross-disciplinary review is necessary. *If deemed necessary, such review shall be performed by the appropriate designated review personnel.

d.

If the Department Manager determines that the documents involved contain significant safety issues, the documents shal 1 be forwarded for SORC review and also to NSR for an independent review to determine whether or not an unreviewed safety question is involved.

Pursuant to 10CFR50.59, NRC approval of items involving unreviewed safety questions or Technical Specification changes shall be obtained prior to implementation.

SALEM - UNIT 2 6-12 l

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.P.

).*:.

ADMINISTRATIVE CONTROLS NON-PROCEDURE RELATED DOCUMENTS 6.5.3.3 Tests or experiments, changes to Technical Specifications, and changes

  • to equipment or systems shall be reviewed as described in items 6.5.3.2a, c, and d above.

Recommendations for approval are made by SORC to the General Manager Manager - Salem Operations.

Pursuant to 10CFR50.59, NRC approval of items involving unreviewed safety questions or requiring Technical Specification changes shal 1 be obtained prior to implementation.

RECORDS 6.5.3.4 Written records of reviews performed in accordance with itme 6.5.3.2a above, including recommendations for approval or disapproval, shall be maintained. Copies shall be provided to the General Manager - Salem Operations, SORC, NSR and/or NRC 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 Report submitted to NSR and the Vice President - Nuclear.

6.7 SAFETY LIMIT VIOLATiON 6.7.1 The following actions shall be taken in the event a Safety Limit is via 1 ated:

a.

The unit shall be placed in at least HOT STANDBY within one hour.

b.

The NRC Operations Center shall be notified possible and in all cases within one hour.

and General Manager - Nuclear Safety Review hours.

by telephone as soon as*

The Vice President - Nuclear shall be notified within 24

c. A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the SORC.

This report shal 1 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 Commission, the General Manager - Nuclear Safety Review and the Vice President -

Nuclear within 14 days of the violation.

SALEM - UNIT 2 6-12a

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

a.

The appl i cable procedures recommended in Appendix 11A 11 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.

Fi re Protect ion Pro gram implementation.

g*.

PROCESS CONTROL PROGRAM implementation.

h.

OFFSITE DOSE CALCULATION MANUAL implementation.

i.

QJal ity Assurance Program for effluent and environmental rmnitori ng.

6.8.2 Each procedure and administrative policy of 6.8.l above, and changes thereto, shall be reviewed and approved in accordance with Specification 6.5.L6 J.

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 pl ant 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 Specification 6.5.3.2a within 14 days of implementation.

SALEM -

UN IT 2 6-13

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