ML20128D242

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Amends 62 & 33 to Licenses DPR-70 & DPR-75,respectively, Changing Tech Specs to Update Nuclear Dept Organization & Station Operations Review Committee Responsibilities, Membership & Quorum Requirements
ML20128D242
Person / Time
Site: Salem  PSEG icon.png
Issue date: 05/13/1985
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20128D245 List:
References
NUDOCS 8505280538
Download: ML20128D242 (40)
v • d • e


Text

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WEQ jo UNITED STATES g

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NUCLEAR REGULATORY COMMISSION t

j WASHINGTON, D. C. 20655

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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELEGIRIC LOMPANY DELMARVA POWER AND LIGHI COMPANY ATLANTIC CITY ELEGINIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. DPR-70 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated October 26, 1984 and supplemented November 6, 1984, complies with the standards and requirements of the Atomic Erergy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-70 is hereby amended to read as follows:

8505280538 850513 PDR ADOCK 05000272 p

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- (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 62, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendrent is effective as of the date of its issuance, to be implemented within 6 months after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION f

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' Operating Reac1 ors anch #1 Division of Licensin

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 13, 1985 J

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- ATTACHMENT TO LICENSE AMENDMENT N0. 62 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:

Remove Pages Insert Pages XVIII XVIII XIX XIX 6-1 6-1 6-2 6-2 6-3 6-3 6-4 6-4 6-5 6-5 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6-9a 6-9a 6-10 6-10 6-11 6-11 6-12 6-12 6-12a 6-12a

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' INDE X ADMINISTRATIVE CONTROLS PAGE SECTION 61 6.1 RES PONSIBILIT Y.......................

6.2 ORGANIZATION 6-1 Offsite 61 Facility Staff.......................

6-6 Shift Technical Advisor 6-6 6.3 FACILITY STAFF QUALIFICATIONS...............

6-6 6.4 TRAINING...........................

6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE 67 Function.........................

67 Co mpo s i t i o n........................

67 Alternates 6-7

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Mee t i n g F reque ncy.....................

6-7 Quorum..........................

6-8 Responsibilities 6-9 Review Process 6-9 Au t ho r i ty.........................

6-9 R e co r d s..........................

6.5.2 NUCLEAR SAFETY REVIEW 6-9 Function.........................

69 Co mpo s i t io n........................

6 9a Co n s u l t a nt s........................

6 9a

- Of f-S i te Re vi ew Gro up...................

6-9a Review..........................

6 10 Audits..........................

6-11 On-Site Safety Review Group................

6 11 Responsibilities 6-11 Aut ho r i ty.........................

SALEM - UNIT 1 WIII Amendment No. 62 l

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. INDE Xs ADMINISTRATIVE CONTROLS SECTION PAGE f

6.5.3 TECHNICAL REVIEW AND CONTROL................

6 12 t

6.6 REPORTABLE EVENT ACTION 6-12a 6.7 SAFETY LIMIT VIOLATION....................

6-12a 6.8 PROCEDURES AND PROGRAMS 6-13 6.9 REPORTING REOUIREMENTS 6.9.1 R OUT I NE R E POR TS......................

6-15 6.9.2 S PE C I AL R E PORTS......................

6-19 6.10 RECORD RETENTION......................

6 19 6.11 RADIATION PROTECTION PROGRAM................

6-21 6.12 HIGH RADIATION AREA 6-21 6.13 PROCESS CONTROL PROGRAM 6-22 6.14 0FFSITE DOSE CALCULATION MANUAL 6-22 6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASE0US AND SOLID WASTE TREATMENT SYSTEMS 6-23 6.16 ENVIRONMENTAL QUALIFICATION 6-24 SALEM - UNIT 1 XI X Amendment No. 62 1

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ADMINISTRATIVE CONTROLS

~e 6.1 RESPONSIBILITY n>

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 OFFSITE

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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 shovn on Figure 6.2-2 and:

4.

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 l

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

j

-c.

A health physics technician # shall be on site when fuel is in the

reactor, d.

ALL CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsi-bilities during this operation.

e.

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 emer gency.

f.

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).

  1. The health physics technician and-Fire Brigade composition rey be less than the l

minimum requirements for a period of tine not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of 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 - UNIT 1 6-1 Amendment No. 62

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TABLE 6.2-1

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MINIMUM SHIFT CREW COMPOSITION SALEM UNIT 1 WITH UNIT 2 IN MODES 5 OR 6 OR DE-FUELED POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 SNSS la la SR0 lb none STA lb none NC0 2

1 E0/U0 3

2C Maintenance Electrician 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 la la SR0 lb none STA lb none NCO 2

1 E0/U0 3d 1

Maintenance Electrician la none af Individual may fill the same pnsition on Unit 2 b]

Individual who fulfills the STA requirement may fill the sane position on Unit 2.

The STA, if a licensed SRO, may concurrently fill the SR0 position on one unit; the other unit also requires a qualified SR0 on shift.

-c/ One of the two required individuals may fill the position on Unit 2, such that there are a total of three E0/U0's for both units.

I d_ /_ One of the three required individuals may fill the same position of Unit 2, such that there are a total of five E0/U0's for both units.

I SALEM - UNIT 1 6-4 Amendment No. 62

Y TABLE 6.2-1 (Continued)

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

. Individual with a Senior Reactor Operator License on both units SR0 (normally, a Nuclear Shift Supervisor ).

Nuclear Control Operator with a Reactor Operator License on NC0 both units.

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

Equipment Operator or Utility Operator.

E0/U0 Except for the Senior Nuclear Shift Supervisor, the Shift Crew Composition nay be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 'in order to accommodate the unexpected absence of on-duty shift crew members provided that immediate action is taken to restore the Shift Crew Composition to within the nininum requirements of Table 6.2-1.

This provision does not pernit any shift crew position to be unmanned upon shift change due to an oncoming shift crewperson's being late or absent.

Durihg any absence of the Senior Nuclear Shift Supervisor from the Control Room l

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.

l SALEM - UNIT 1 6-5 Amendment No. 62

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

6.2.3.2 The Shif t 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 *ne facility staf f shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for conparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter te all licensees, except for the Radiation Protection Engineer who shall meet or exceed the qualifications of Regulatory Guide 1.8 September 1975.

6.4 TRAINIP;G 6.4.1 A retraining and replacenent training program for the facility staff shall be coordinated by each functional level manager (Department Head) at the facility and naintained under the direction nf the Nanager - Nuclear Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" 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 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.

SALEd - UNIT 1 6-6 Amendment No. 62

ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT

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6.5.1 STATION OPERATIONS REVIEW COMMITTEE (SORC)

FUNCTION 6.5.1.1 The Station Operations Review Committee shall function to advise the General Manager - Salen Operations on operational matters related to nuclear i

safety.

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

Chairman:

General Manager - Salem Operations Member and Vice Chairman: Assistant General Manager - Salem Operations Member and Vice Chairman: Maintenance Manager Member and Vice Chairman: Operations Manager Member and Vice Chairman: Technical Manager Member:

Operating Engineer Member:

I & C Engineer 2

Member:

Senior Nuclear Shift Supervisor Member:

Technical Engineer Member:

Maintenance Engineer Member:

Radiation Protection Engineer Menber:

Chemistry Engineer Member:

Manager - On Site Safety Review Group or his designee.

ALTERNATES

6. 5'.~1. 3 All alternate members shall be appointed in writing by the SORC
Chairman, a.

Vice Chairnen shall be members of Station managenent.

b.

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

c.

Alternate appointees will only represent their respective department.

d.

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

MEETING FREQUENCY 6.5.1.4 The 50RC shall meet at least once per calendar month and as convened by by the 50RC Chairnen or his designated alternate.

QUORUM 6.5.1.5 The minimum quorum of the 50RC necessary for the perfornence of the SORC responsibility and authority provisions of these technical spec 4/ Nations shall consist of the Chairnen or his designated alternate and five members including alternates.

SALEM -' UNIT 1 6-7 Amendment No. 62

's 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 "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 l

provisions of 10CFR50.59.

f.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation 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.

1.

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

Review.

1.

Review of the Fire Protection Progran and implementing procedures and submittal of recommended changes to the General Manager - Nuclear I

Safety Review.

Review of all unplanned on-site releases of radioactivity to the environs m.

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.

Review of changes to the PROCESS CONTP.0L MANUAL and the OFF-SITE DOSE n.

CALCULATION MANUAL.

SALEM - UNIT 1 6-8 Amendment No. 62

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 providtd in Section 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 -

l Nuclear and the General Manager - Nuclear Safety Review of disagreement i

between the SORC and the General Manager - Salen 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 President - Nuclear, the

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General Manager - Nuclear Safety Review and the Manager - Off-Site Review.

6.5.2 NUCLEAR SAFETY REVIEW FUNCTION l

l 6.5.2.f The Nuclear Safety Review Department (NSR) shall function to provide the I

independent safety review program and audit of designated activities.

l 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 (0SR) who is supported by at least four dedicated, full-tine engineers i

located off-site.* The OSR staff shall possess experience and competence in the j

general areas listed in Section 6.5.2.4 The General Manager and Managers shall 3

determine when additional technical experts should assist in reviews of complex pro blems.

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 same qualification requirements as the NSR staf f, and will not have been involved with performance of the original erk.

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  • Since the Nuclear Department is located on Artificial Island site, the terms "on-site" and "of f-site" convey the distinction between inside and outside the station fence, respectively SALEM - UNIT 1 6-9 Amendment No. 62

ADMINISTRATIVE CONTROLS I

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 N18.7 (1976) (ANS 3.2).

The Manager - On Site Review and staff will meet 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 (0SR) shall function to provide independent review and audit of designated activities in the areas of:

a.

Nuclear Pbwer Plant Operations b.

Nuclear Engineering c.

Chemistry and Radiochemistry d.

Metallurgy e.

Instrumentation and Control f.

Radiological Safety g.. Mechanical Engineering h.

Electrical Engineering 1.

Wality Assurance J.

Nondestructive Testing k.

Emergency Preparedness l

The OSR shall also function to examine plant operating characteristics, NRC l

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 provisions of Section 50.59, 10CFR, to verify that such actions did not constitute an unreviewed safety question.

SALEM - UNIT 1 6-9a Amendment No. 62

ADMINISTRATIVE CONTROLS 4

b.

Proposed changes to procedures, equipment, or systems that involve an

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unreviewed safety question as defined in Section 50.59, 10CFR.

Proposed tests or experiments that involve an unreviewed safety question c.

as defined in Section 50.59, 10CFR.

l 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 i

nuclear safety significance.

f.

Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect ~ nuclear safety.

l g.

All REPORTA8LE EVENTS.

h.

All recognized indications of an. unanticipated deficiency in some aspect of design or operation of safety-related structures, systems or compo nents.

1.

Reports and mieting minutes of the Station Operations Review Committee.

AUDITS p

6.5.2.4.2 Audits of f&cility activities that are c' quirfd to be performed under e

\\,

the cognizance of OSR art, listed below:

a.

The conformence of f acility operation to provisions contained within ths Technical Specifications and applicable license conditions at least once per 12 mnths.

b.

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

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 months.

' d.

The performance of activities required by the Operational (hality Assurance Program to meet the Criteria of Appendix "B",10CFR50, at least once per 24 mnths.

e.

The Facility Emergency Plan and implementing procedures at least once per 12 nenths, f.

The Facility Security Plan and implenenting procedures at least once per 12 nontns.

g.

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

h.

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

SALEM - UNIT 1 6-10 Amendment No. 62

ADMINISTRATIVE CONTROLS 1.

Am independent fire protection and loss prevention program inspection and audit shell be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire -

protection firm.

j.

An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

The radiological environnental nonitoring program and the results k.

thereof at least once per 12 nenths.

The above audits shall be conducted by the Nuclear Osality Assurance Department or an independent consultant as required. Audit results and reconmendations shall be reviewed by OSR.

ON-SITE SAFETY REVIEW Gt00P 6.5.2.5 The On-Site Safety Revien 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 actisitics; and advict to msnagemant on the overall quality and safety of plant operations.

The SRG shall make reconmendations for revised procedures, aquipaunt nodifications, or other means of improving plant safety to appropriate station /

corporate management.

RESPONSIBILITIES 6.5.2.5.1 The SRG shall be responsible for:

Review of selected plant operating characteristics, NRC issuances, a.

industry advisories, and other appropriate sources.of plant design and operating exptrience inforretion that may indicate areas for improving plant safety, b.

Review of selected facility features, equipment, and systems.

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

nodification, operational problems, and operational analysis, Surveillance of selected plant operations and maintenance activities to d.

provide independent verification

  • that they are performed correctly and that human errors are reduced to as low as reasonably achievable.

NSR AUTHORITY i

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

l

  • ftet responsible for sign-off function Amendment No. 62 6-11 SALEM - UNIT 1

ADMINISTRATIVE CONTROLS 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 14 days folloxing completion of the review.

b.

Audit reports encogassed 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 cogletion 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 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 i

shall be responsible for a predesignated class of procedures. The l

General Manager - Salem Operations shall approve Station Administrative Procedures, Security Plan implementing procedures and Emergency Plan t

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, et least one of whom holds a Seninr 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 abo ve.

c.

Individuals responsible for reviews performed in accordance with item 6.5.3.2a above shall be approved by the SORC Chairman and designated as Station Qualified Reviewers. A system of Station Qualified Reviewers, each of whom shall possess qualifications that meet or exceed the requirements of Section 4.4 of ANSI N18.1 - 1971, 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 de'signated review personnel.

SALEM - UNIT 1 6-12 Amendment No.'62

ADMINISTRATIVE CONTROLS

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d.

If the Department Manager determines that the documents involved contain significant safety issues, the documents shall be forwarded for S0RC 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.

NON-PROCEDURE RELATED DOCUMENTS 6.5.3.3 Tests or experiments, changes to Technical Specifications, and changes-to equipment or systems shall be forwarded for SORC review and also to NSR for an independent review to determine whether or not an unreviewed safety question is invol ved. The results of NSR reviews will be provided to S0RC.

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

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

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 takca for REPORTABLE. EVENTS:

a.

The Comnission 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 50RC 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 placed in at least HOT STANDBY within one hour.

i 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 i

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 50RC. This report shall describe (1) applicable circunstances preceding the violation, (2) effects of the violation upon I

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.

SALEhMIT1 6-12a Amendment No. 62

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

4 The applicable procedures recommended in Appendix "A" of Regulatory a.

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.

QJality Assurance Program for effluent and environmental ponitoring.

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 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 rembers of the plant management staf f, 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 - UNIT 1 6-13 Amendment No. 62 l

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UNITED STATES g

f'UCLEAR REGULATORY COMMISSION i

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WASHINGTON, D. C. 20555

  • %...../

PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELEGIRIC COMPANY DELMARVA POWER AND LIGHT CUMPANY

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ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STA110N, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No. DPR-75 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Public Service Electric and Gas Company, Dhiladelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated October 26, 1984 and supplemented November 6, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission;

~

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will.be conducted in compliance with the Comission's regulations; D.

The issuance of this anendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:

t

, (2) Technical Specifications The Technical Specifications. contained in Appendices.-

A and B, as revised through; Amendment No. 33, are hereby incorporated in the license. The licensee shall operate the facility ~1n accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance, to be implemented within 6 months after issuance.

FOR THE NUCLEA GULATORY COMMISSION k _f)

Oh,Ch f Operating Reactors r nch #1 Division of Licensin

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 13, 1985 e

.pY

ATTACHMENT TO LICENSE AMENDMENT NO. 33 FACILITY OPERATING LICENSE N0. DPR-75 DOCKET NO. 50-311 4

Revise Appendix A as follows:

Remove Pages Insert Pages XVIII XVIII XIX XIX 6-1 6-1 6-2 6-2 6-3 6-3 6-4 6-4 6-5 6-5 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6-9a 6-9a 6-10 6-10 6-11 6-11 6-12 6-12a 6-12 6-12a 6-13 6-13

'INDE X ADMINISTRATIVE CONTROLS SECTION PAGE 6.1-RES PONSIBILITY.............

6-1 6.2 ORGANIZATION Offsite 6-1 Facility Staff.......................

6-1 Shift Technica1' Advisor 6-6 6.3 FACILITY STAFF OUALIFICATIONS 6-6 6.4 TRAINING..........................

6-6 6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE l

f Function 6-7 Co mpo s i t i o n........................

6-7 Alternates 6-7 Meeting Frequency.....................

67 Quorum 6-7 6-8 Responsibilities Review Process 6-9 A u t ho r i ty.........................

6-9 R e co r d s..........................

6-9 6.5.2 NUCLEAR SAFETY REVIEW Function 6-9 Co mpo s i t i o n........................

6-9 Co n s u l t a nt s........................

6-9a Off-Site Review Group...................

6-9a Review 6-9a Audits 6-10 On-Site Sa fety Review Group................

6-11 Resp)nsibilities 6-11 A u t ho r i ty.........................

6-11 SALEM - UNIT 2 XVIII Amendment No. 33

INDE X ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.3 TECHNICAL REVIEW AND CONTROL................

6 12 6.6

-REPORTABLE EVENT ACTION 6-12a 6.7 SAFET Y LIMIT VIOLATION...................

6-12a 6.8 PROCEDURES AND PROGRAMS 6-13 i

6.9 REPORTING REQUIREMENTS 6.9.1 ROUT I NE R E PORTS......................

6-15 6.9.2 S PEC I AL R E PORTS......................

6-19 6.10 RECORD RETENTION......................

6 19 6.11 RADI ATION PROTECTION PROGRAM................

6-21 6.12 HIGH RADIATION AREA 6-21 6.13 PROCESS CONTROL PROGRAM 6 22 I

6.14 0FFSITE DOSE CALCULATION MANUAL 6 22 r

t 6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASE0US AND SOLID WASTE TREATMENT SYSTEMS 6-23 SALEM - UNIT 2 XI X Amendment No. 33 e

+.

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 snall 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 OFFSITE 6.2.1 The offsite organization for facility managerent 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 times.

j c.

A health physics technician # shall be on site when fuel is in the reacto r.

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 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 worked by plant staf f menbers performing safety-related functions must be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).

  1. The healtn physics technician and Fire Brigade composition nay be less than the

[

minimum requirements 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 acconnadate 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 - UNIT 2 6-1 Amendment No. 33

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TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION SALEM UNIT 2 WITH UNIT 1 IN MODES 5 OR 6 OR DE-FUELED POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 SNSS la la SR0 lb none STA lb none NC0 2

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Maintenance Electrician 1

none WITH UNIT 1 IN MODES 1, 2, 3 OR 4 POSITION NUMBER OF INDIVIDUALS RE0VIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 SNSS la la f

SR0 lb no ne STA lb none NC0 2

1-E0/U0 3d 1

i Maintenance Electrician la none a_/ Individual may fill the same position on Unit 1 b] Individual who fulfills the STA requirement may fill the same position on I

Unit 1.

The STA, if a licensed SRO, may concurrently fill the SR0 position on one unit; the other unit also requires a qualified SR0 on shift.

c_/ One of the two required individuals may fill the position on Unit 1 such that there are a total of three E0/UO's for both units.

d_/. One of the three required individuals may fill the same position of Unit 1, such that there are a total of five E0/,00's for both units.

SALEM - UNIT 2 64 Amendment No. 33 iir

TABLE 6.2-1 (Continued)

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

SR0 Individual with a Senior Reactor Operator License on both units (normally, a Nuclear Shift Supervisor ).

NC0 Nuclear Control Operator with a Reactor Operator License on both units.

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

E0/U0 Equipment Operator or Utility Operator.

Except for the Senior Nuclear Shift Supervisor, the Shift Crew Composition nay l

be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate the unexpected absence of on-duty shift crew members provided that immediate action is taken to restore the Shift Crew Composition tn 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 SR0 License shall be designated to assume the Control Room command function.

SALEM - UNIT 2 6-5 Amendment No. 33

9 ADMINISTRATIVE CONTROLS e

6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift T(chnical 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 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 QJALIFICATIONS 6.3.1 Each rember of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions and the supplemental requirements specified in Sections A snd 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 6.4.1 A retraining and replacement training program for the facility staff shall be coordinated by each functional level manager (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 N18.1-1971 and Appendix "A" 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 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.

I l

l SALEM - UNIT 2 6-6 Amendment No. 33 l

o ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE (SORC)

FUNCTION 6.5.1.1 The Station Operations Review Comittee 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 (50RC) shall be composed of:

Chairman:

General Manager - Salem Operations Member and Vice Chairman: Assistant General Manager - Salem Operations Member and Vice Chairman: Maintenance Manager Member and Vice Chairman: Operations Manager Member and Vice Chairman: Technical Manager Member:

Operating Engineer Member:

I 8 C Engineer Member:

Senior Nuclear Shift Supervisor Member:

Technical Engineer Member:

Maintenance Engineer Member:

Radiation Protection Engineer Member:

Chemistry Engineer Member:

Manager - On Site Safety Revier Group or his designee.

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

a.

Vice Chairmen shall be rembers of Station management.

b.

Pb more than two alternates to members shall participate as voting members in SORC activities at any one meeting.

c.

Alternate appointees will only represent their respective department.

l d.-

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

I MEETING FREQUENCY i

6.5.1.4 The SORC shall meet at least once per calendar month and as convened by by the 50RC Chairman or his designated alternate.

QUORUM 6.5.1.5 The minimum quorum of the 50RC necessary for the performance of the SORC responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate ano five members including alternates.

SALEM - UNIT 2 6-7 Amendment No. 33 i

1 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 "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

_l provisions of 10CFR50.59.

f.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation 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.

1.

Performance of special reviews, invest'igations 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 Emergency Plan and implementing procedures and submittal of recommended changes to the General Manager - Nuclear Safety Review.

3 1.

Review of the Fire Protection Program and implementing procedures and submittal of recommended changes to the General Manager - Nuclear b

'l Safety Review.

Review of all unplanned on-site releases of radioactivity to the environs m.

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 l'

General Manager - Nuclear Safety Review.

l j-Review of changes to the PROCESS CONTROL MANUAL and the 0FF-SITE DOSE n.

CALCULATION MANUAL.

SALEM. UNIT 2 6-8 Amendment No. 33

l i

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 nf this technical review process are provfded in Section 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 Stathn Operations Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Vice President - Nuclear, the General Manager - Nuclear Safety Review and the Manager - Off-Site Review.

g 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 l

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-tine 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 l

determine when additional technical experts should ' assist in reviews of complex l

problems.

f NSR shall utilize a system of qualified reviewers from other technical i

organizations to augment its expertise in the disciplines of Section 6.5.2.4.

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

  • Since the Nuclear Department is located on Artificial Island site, the terms i

"on-site" and "off-site" convey the distinction between inside ar.1 outs.de the l

station fence, respectively.

l SALEM - UNIT 2 6-9 Amendment No. 33 t

~

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 N18.7 (1976) (ANS 3.2).

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

l I

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

i

-Nuclear Safety Review to provide expert advice to the NSR.

i 1

0FF-SITE REVIEW GROUP i

6.5.2.4 The Off-Site Review Group (OSR) shall function to provide independent i

review and audit of designated activities in the areas of:

a.

Nuclear Power Plant Operations b.

Nuclear Engineering l

c.

Chemistry and Radiochemistry d.

Metallurgy f

e.

Instrumentation and Control i

f.

Radiological Safety j

g.

Mechanical Engineering h.

Electrical Engineering 1.

QJality 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 pror.edures, equipment, or systems and l
2) Tests or experiments corpleted under the provisions of Section 50.59, 10CFR, to verify that such actions did not constitute an unreviewed safety question.

SALEM - UNIT 2 6-9a Amendment No. 33

ADMINISTRATIVE CONTROLS koposed changes to procedures, equipnent, or systens that involve an b.

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

as defined in Section 50.59, 10CFR.

koposed changes to Technical Specifications or to the Operating License.

d.

Violations of codes, regulations, orders, Technical Specifications, e.

license requiresents, 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 REPORTA8LE EVENTS.

h.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems or compo nents.

j

. Reports ar.d me(ting (91nuid of'the Station Operations Review Committee.

i i.

AVOITS 6.5.2.4.2 'dudits" of' facility activities that are required to be performed under the cognizance of OSR are l'isted below:

The conformance of facility operation to provisions contained within a.

the Technical Specifications and applicable license conditions at least once per 12 enths.

b.

The performance, tr.aining, and qualifications of the entire facility staff at least once per 12 enths.

The results of actions taken to correct deficiencies occurring in c.

facility equipment, structures, saterts, or rathod of operation that affect nuclear safety at least ont a per 6 months.

d.

The performance of activities required by the Operational QJality Assurance kogram to meet the Criteria of Appendix "B",10CFR50, at least once per 24 mnths.

e.

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

f.

The Facility Security Plan and implenenting procedures at least once per 12 e ntns.

g.

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

h.

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

Amendment No. 33 m

(vst@

ADMINISTRATIVE CONTROLS 1.

An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection fire.

An inspection and audit of the fire protection and loss prevention j.

program shall be performed by a qualified outside fire consultant at least once per 36 months.

The radiological environnental nonitoring program and the results k.

thereof at least once per 12 penths.

The above audits shall be conducted by the Nuclear Quality Assurance Department or an independent consultant as required. Audit results and recomnandations shall be reviewed by OSR.

ON-SITE SAFETY REVIEW Gt00p The On-Site Safety Review Group (SRG) shall function to provide:

the 6.5.2.5 revice of plant design and operat,ing experience for potential opportunities to plant safety; the evaluation of plant operations and maintenance ingrov:

activities; snd aceict tn sotgssnt orr tht-overall quality and safety of plant operations.

The SRG sh611 make recommendation; for revised procedures, equipment nodifications, or othte sans of incroving plant safety to appropriate station /

w corporate management.

RESPONSIBILITIES 6.5.2.5.1 The 'SRG shal-1 be responsibic for:

Review of seletted plant operating characteristics, NRC issuances, a.

industry advisories, and oth6r appropriate scurces of plant design and operating experience information that may indicate areas for improving plant safety.

Review of selected facility features, equipment, and systems.

l b.

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

nodification, operational problems, and operational analysis.

Surveillance of selected plant operations and maintenance activities to d.

provide independent verification

  • that they are performed correctly and that hunon errors are reduced to as low as reasonably achievable.

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

  • Not responsiole for sign of f function Amendment No. 33 6-11

. ADMINISTRATIVE CONTROLS 7

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 - Nurlear, within m

14 days following cogletion of the review.

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, shall 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 i

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 proced0res. The General Manager - Salem Operations shall approve Station Administrative Procedures, Security Plan iglementing 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 twn nenbers of the plant management stuff, 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 above.

c.

Individuals responsible for reviews performed in accordance with item 6.5.3.2a above shall be approved by the SORC Chairman and designated as Station Walified Reviewers. A system of Station Walified Reviewers, r

each of whom shall possess qualifications that meet or exceed the requirements of Section.4.4 of ANSI N18.1 - 1971, shall be maintained by the 50RC Chairman. Each review shall include a written determination of whether or not additional cross-disciplinary review is necessary.

If i

. deemed necessary, such review shall be performed by the appropriate designated review personnel.

SALEM -' UNIT 2 6-12 Amendment No. 33

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kDMINISTRATIVECONTROLS d.

If the Department Manager determines that the documents involved contain significant safety issues, the documents shall be forwarded for 50RC 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.

NON-PROCEDURE RELATED DOCUMENTS

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6.5.3.3 Tests or experiments, changes to Technical Specifications, and changes to equipment or systems shall be forwarded for SORC review and also to NSR for an independent review to determine whether or not an unreviewed safety question is invol ved. The results of NSR reviews will be provided to SORC.

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

Pursuant to 10CFR50.59, 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 6.5.3.2a 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 a're required.

6.5 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 tn 10CFR Part 50, and b.

Each REPORTABLE EVENT sha'i be reviewed by the SORC and the resultant Licensee Event Report sJbmitted to NSR and the Vice President - Nuclear.

l 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 Operationg 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 General Manager - Nuclear Safety Review and. the Vice President -

Nuclear within 14 days of the violation.

SALEM - UNIT 2 6-12a Amendment No. 33

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' ADMINISTRATIVE CONTROLS-

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

The applicable procedures recommended in Appendix "A" of Regulatory a.

Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

Surveillance and test activities of safety related equipment.

c.

d.

Security Plan implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

g.

PROCESS CONTROL PROGRAM implementation.

h.

OFFSITE DOSE CALCULATION MANUAL implementation.

1.

Wality Assurance Program for effluent and environmental tronitoring.

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 administrative procedures.

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

The intent of the original procedure is not altered.

i a.

b.

The change is approved by two members of the plant management staf f, j

at least one of whom holds a Senior Reactor Operator's License on the l

unit af fected.

}

The change is documented and receives the same level of review and c.

approval as the original procedure under Specification 6.5.3.2a within 14 days of implementation.

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SALEM - UNIT 2 6-13 Amendment No. 33 i

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