ML19351E827

Amend 4 to License DPR-75,approving Organizational Change to Facility Operation & Support Staff & Revising Related Tech Specs

ML19351E827
Person / Time
Site:	Salem
Issue date:	12/08/1980
From:	Miraglia F Office of Nuclear Reactor Regulation
To:
Shared Package
ML19351E828	List: ML19351E827 ML19351E829 ML19351E833
References
NUDOCS 8012190400
Download: ML19351E827 (16)

Text

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h, UMTED STATES

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NUCLEAR REGULATO.s / COMMISSION j,k;sy;%

" j WASHINGTON, D. C. 20555 p

PUBLIC SERVICE ELECTRIC AND GAS COMPANY

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PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNITS NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 4 License No. DPR-75 1.

The Nuclear Regulatory Commission (the Comnission) 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 November 20, 1980 complies with the standards and requirements of the Commission's 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 regulations of the Commission; 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 Commission's regulations; D.

The issuance of this amendment will not be inimical to the common 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 Commission'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 t

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amended to read as follows:

0 801219 O

2 (2) Technic al Snorifications The Technical Specifications contained in Appcodices A and B, as revised through Amendment No. 4, are hereby incorporated in the license. Public Service Electric and Gas Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR T!iE NUCLEAR REGULATCRY C0b'.'iiSSIC':

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Mdfld z. /f K# t.L Frank J. M19ag[i, Ac$ing Chief Licensing Branch flo. 3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 8, 1980

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December 8, 1980 I

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ATTACEMENT TO UCEISE AMENETT NC. i i

f FACILITY UCENSE NO. DFR 75 DOCKET NO. 50-3 n Esvise Appendix A as fonews:

Remove hres Insert Pages b2 b2 6-3 6-3 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 bn bu l

6-12 6-12 Revise Appendix 3 as fonows:

Remove Page Insert Page l

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 CRGANIZATION OFFSITE 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 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.

c.

At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

d.

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

i e.

All CORE ALTERATIONS shall be directly supervised by a licensed Senior l

Reactor Operator who has no other concurrent responsibilities during this operation.

f.

A site Fire grigade of at least 5 memoers shall be maintained onsite at all times. The Fire Brigada 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.

1. Fire Brigade composition say be 1

, than the minimum requirements for a period of time not to exceed 2 hcors in order to accommodate unexpected absence of Fire Brigade memcers provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.

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SALEM - UNIT 2 6-2 AMENDMENT NO. 4

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FIGuitE 4 2 2 F ACILIIV OHGANIZATION-SALLM GENEftAllNG ST AilON

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION Condition of Unit 2 - No Fuel in Unit 1 l

APPLICABLE MODES LICENSE CATEGORY 1, 2, 3 & 4 5&6 SQL 2

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9 SALEM - UNIT 2 6-4

4 TABLE 6.2-1 (Continued)

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• Coes not include the licensed Senior Reactor Operator supervising CORE ALTERATIONS.

• • Each unit will be supervised by a shift supervisor who is a licensed SRO on that unit; or by a single individual if he is licensed on both units.

The second senior operator licensed for each unit must be stationed in l

the control room area at all times when the unit is in operating modes 1 through 4; and could also be a single individual if he is licensed on r

Units I ar.d 2.

• • • A reactor operator licensed for each unit must be at the controls of that unit at all times when fuel is in the reactor.

Also, a relief reactor operator licensed for each unit must be available on-shift.

This could be a single individual if he is licensed for both units.

1. Shift crew composition may be less than the minimum recuirements for a period of time not to exceso 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomodate unexpected absence of on-duty shift crew semoers provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

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3 SALEM - UNIT 2 6-5

h8NISTRATRVECONTROLS

6. 3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall eeet or exceed the minimum cualif! cations of ANSI N18.1-1971 for comparable posi* ions except fcc the Radiation Protection Enginees who shall :neet or exc2ed tne qualifications of Regulatory Guide 1.8, September 1975.

6. 4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff sna11 he cooroinated by each functional level manager (Department Head) at the facility and maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N13.1-1971 and Appendix "A" of 10 CFR Part 55.

6.5 REVIEW AND AUDIT

6. 5.1 STATICN CPERATIONS REVIEW CCMMITTEE (50RC)

FUNCTION 6.5.1.1 The Station Operations Review Committee shall function to advise the Station Manager on all matters related to nuclear safety.

CCMPOSITION 6.5.1.2 The Station Operations Review Committee shall be composed of the:

Chaiman:

Chief Engineer Vice Chairman:

Assistant to Manager Vice Chairman:

Station Performance Engineer Vice Chaiman:

Maintenance Engineer Member:

Station Operating Engineer Me;nter:

Reactor Engineer Member:

Senior Shift Supervisor Member:

Senior I & C Supervisor Member:

Senior Chemistry Supervisor Member:

Radiation Protection Engineer Member:

Senior Maintanance Supervisor

{TERNATES 6.3.1.3 All alternate members shall be appointed in writing by the SCRC Chairman to serve on a temporary basis; however, no more than two alternates saali participate as voting members in 50RC activities at any one time.

MEETING FRECUENCY 6.5.1.4 The 50RC shall meet at least once per calendar month and as convenec by the SCRC Chairnan or his designated alternate.

SALEM - UNIT 2 6-6 AMENOMENT.'ic. L

ADMINISTRATIVE CONTROLS QUCRUM 6.5.1.5 The minimum quorum of the 50RC necessary for the performance of the 50RC responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate and four memcers including alternates.

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

Review of 1) all procedures required by Specification 6.8 and changes a.

thereto, 2) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety, b.

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

c.

Review of all proposed changes to Appendix "A" Technical Specifications.

d.

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

e.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the General Manager - Nuclear Production and to the Chairman of the Nuclear l

Review Board.

f.

Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.

.g.

Review of facility operations to detect potential nuclear safety ha:ards.

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h.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Nuclear Review Board.

i.

Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Nuclear i

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Review Board.

j.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Nuclear Review Board.

l AMENDMENT NC. a SALEM - UNIT 2 6-7 O

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ACMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The Station Operations Review Co =ittee sna11:

Reco:nmend to the Station Manager written accroval or disa;croval of a.

items consicere uncer 6.5.1.6(a) nrough (d) a ove.

Render ceterminations in.riting wita regarc to onetner or not eaca 3.

item consicered under 6.5.1.6(a) through (e) acove constitutes an unreviewec safety question.

Provice writ:,en notification -itnin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the General w c.

anager Nuclear Production and the Nuclear Review Boarc of cisagreement l

Detween the 50RC and the Station Manager; however, tne Station Manager snall have responsibility for resolution of such cisagree-ments pursuant to 6.1.1 above, RECOR05 1

6.5.1.8 The Station Occrations Review Co=mittee snall =aintain written minutes of each meeting snat, at a mini =um, coc=cnt the results of all SCRC activ ';ies performed under the responsibility and autnority provisions of these tecnnical scecifications. Copies small te provided to tne General Manager-Nuclear l

Procuction anc Chair an of tne Nuclear Review Boarc.

6. 5. 2 NUCLEAR REVIEW BOARD (NRSI FUNCTICN 6.5.2.1 The Nuclear Review Boarc snail function to crovice incecencent revie.

anc aucit of aesignatec activities in the areas of:

a.

nuclear power plant operations 3.

nuclear engineering c.

chemistry and raciocnemistry c.

metallurgy e.

instrumentation anc control f.

radiological safety g.

secnanical and electricai engineering n.

Quality assurance practices SALE.M - UNIT 2 5-8 DE3

ADMINIST".ATIVE CONTROLS i

CCMPOSITION 6.5.2.2 The NRB shall be composed of the:

Chairman:

Assistant Vice President - Production I

Vice Chairman:

Assistant to General Manager-Fuel Supply Member:

General Manager-Licensing and Environment Member:

Manager-Nuclear Operations Support Member:

General Manager-Corporate QA Member:

General Manager-Nuclear Production Member:

Manager-Salem Generating Station Member:

Principal Engineer Memoer:

Manager-Hope Creek Generating Station ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the NR8 Cnairman to serve on a temporary basis; however, no more than two alternates shall participate as voting memcers in NRS activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NRS Chairman to provide expert advice to the NRB.

MEETING FRE00ENCY 6.5.2.5 The NRB shall meet at least once per calendar quarter during tne initial year of unit operation following fuel loading and at least once per six months thereafter.

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

REVIEW 6.5.2.7 The NRB shall review:

The safety evaluations for 1) changes to procedures, equipment or a.

l systems and 2) tests or experiments completed under the provision of l

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

SALEM - UNIT 2 6-9 AMENCriENT NC. L U

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ADMINISTRATIVE CONTROLS b.

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

c.

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

d.

Proposed changes to Technical Specifications or this operating license.

e.

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

f.

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

g.

Events requiring 24 nour written notification to the Commission.

h.

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

i.

Reports and meetings minutes of the Station Operations Review Committee.

O AUDITS 5.5.2.8 Audits of facility activities shall be performed under the cognizance of the NRB. These audits shall encompass:

a.

The conformance of facility coeration to provisions contained within i

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the 'echnical Specifications and applicable license conditions at least once per 12 months.

b.

The performance, training and qualifications of the entire facility l

l staff at least once per 12 months.

I 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.

l d.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "S",10 CFR 50, at least once per 24 months.

e.

The Facility Emergency Plan and implementing procedures at least once per 24 months.

l f.

The Facility Security Plan and implementing procedures at least once l

per 24 months.

l SALEM - UNIT 2 6-10 i

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ACHINISTRATIVE CMTROLS Any other area of facility operation considered appropriate by the g.

CN NRB or the Vice President-Production.

The Facility Fire Protection Program and implementing procecures at h.

least once per 24 months.

,i.

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

AUTHORITY 6.5.2.9 The NRB snall report to and advise the Vice President-Production on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of NR8 activities shall be prepared, approved and distributed as indicated below:

Minutes of each NRB meeting shall be prepared, approved and forwarded a.

to the Vice President-Production within 14 days following eacn meeting.

b.

Reports of reviews encompassed by Section 6.5.2.7 above, snall be prepared, approved and fonvarded to the Vice President-Production within 14 days following completion of the review.

Audit reports encompassed by Section 6.5.2.8 above, shall be forwarced c.

to the Vice President-Production and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE GCCURRENCES:

The Commission shall be notified and/or a report submittec pursuant a.

to the requirements of Specification 6.9.

b.

Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to tne Commission shall be reviewed by the 50RC and submitted to the NRB and the Genefal Manager-Nuclear Production.

l SALEM - UNIT 2 6-11 AMENDMENT NO. k

ADMINXSTRATfVE CCNTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall oe taken in the event a Safety Limit is violated:

a.

The unit shall be placed in at least HOT STANOBY within one nour.

b.

The Safety Limit violation shall be reported to the Commission, the General Manager-Nuclear Production and to the NRB witnin 24 nours.

l c.

A Safety Limit Violation Report shall be prepared.

The report snall be reviewed by the SCRC.

This report snali descrice (1) applicaole 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 suomitted to the Commission, the NRB and the General Manager-Nuclear Production within 14 days l

of the violation.

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

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

Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

c.

Surveillance and test activities of safety related ecuipment, d.

Security Plan implementation.

.e.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

6.3.2 Each procedure and administrative policy of 6.8.1 above, and enanges thereto, shall be reviewed by the 50RC and approved by the Station Manager prior to implementation and reviewed periodically as set forth in adminis-trative procedures.

6.8.3 Temporary 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.

SALEM - UNIT 2 6-12 AMENDMENT NO. a

5.

ADMINISTRATIVE CONTPOLS Acministrative controls below apply to Appendix B - Part 11 only.

s 51 Resconsibility 5.1.1 The implementation of the surveillance programs external to the plant, including samp. ling, sample analysis, evaluation of results and the preparation of required recorts is the resoonsibility of the Licensing and Environment Department. This Department is responsible for the assignment of personnel to the above functions, for assurance that appropriate written procedures are utilized in the surveillance program activities and for assuring the quality of surveillance program results.

5.1. 2 The Station Manager or his delegated alternate is responsible for operating the plant in compliance with the limiting conditions for operation as soecified in the Environmental Technical Specifications and for the in plant monitoring necessary to ensure such operation.

His responsibility incluces assurance that plant activities are Conducted in suCn a manner as to provide continuing protection to the environment and that personnel performing such activities use appropriate written procedures as described in Section 5.5.

5.2 Review and Audit 5.2.1 Nuclear Review Board (NRB)

The NRB shall have tne following responsibilities concerning the environmental impact of the plant:

1.

NRS shall review:

a.

Proposed Environmental Technical Specifications enanges or license amendments.

b.

Violations of Environmental Tecnnical Specifications.

c.

Environmental Monitoring Program and Evaluations.

d.

Routine and non-routine reports required by the Environmental Technical Specifications.

2.

The NRB shall, at least once each year, conduct (or cause to have conducted) and evaluate audits of:

Plant operation to assure Environmental Technical Specificat inn a.

compliance.

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