ML19261C073

Amend 13 to License DPR-70,changing Surveillance Requirement for Fire Detection Instrumentation,Changing Offsite & Station Organizations, & Miscellaneous Administrative Changes

ML19261C073
Person / Time
Site:	Salem
Issue date:	02/12/1979
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML19261C074	List: ML19261C073 ML19261C087 ML19261C091
References
NUDOCS 7903140526
Download: ML19261C073 (19)

Text

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION g

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,j WASHINGTON, D. C. 20555 e

49*****

,o PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.13 License No. DPR-70 1.

The Nuclear Regulatory Commirsion (the Commission) has found that:

A.

The application for amendment by Public Service Electric and Gas Company, et al. (the licensee) dated December 21, 1977 as supplemented April 12, August 18, Septe.nber 25, and October 17, 1978, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activites 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.

W O W.4 o f g

2-2.

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-70 is hereby amended to read as follows:

"(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.13, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications."

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION VA &

A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: February 12, 1979 k

ATTACHMENT TO LICENSE AMENDMENT NO.

13 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET N0. 50-272 Revise Appendix "A" and "B" as follows. The revised pages are identified by Amendment number and vertical lines indicating the area of change. The corresponding overleaf pages arc also provided to maintain document completeness.

Remove Existing Insert Revised Appendix "A" 3/4 3-49 3/4 3-49 3/4 3-50 3/4 3-50 3/4 3-51 3/4 3-51 3/4 3-52 6-2 6-2 6-3 6-3 6-5 6-5 6-6a 6-8 6-8 Appendix "B" 5.1-1 5.1-1 5.2-1 5.2-1 5.2-2 5.2-2 5.2-3 5.2-4 v

v

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: Whenever equipment in that fire detection zone is required to be OPERA 3LE.*

ACTION:

With the number of OPERABLE fire detection instruments less than required by Table 3.3-10:

a.

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, and b.

Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by Speci-fication 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status, c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.6.1 Each of the above required fire detection instruments which are accessible during operation shall be demonstrated OPERABLE at least once per 6 months by performance of a functional test which includes subjecting the detector to smoke or heat, as applicable. Fire detection instruments which are not accescible during operation shall be demonstrat-

• The fire detection instruments within the containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.

SALEM - UNIT 1 3/4 3-49 Amendment No. 77, 13

INSTRUMENTATION FIRE DE'iECTION INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued) ed OPERABLE by performance of this functional test during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> except that such demonstration need not be performed more of ten than once per 6 months. A shutdown outage need not be extended solely for the performance of the fire detection instru-ments functional tests. The reactor coolant pump heat detectors are exempt from this requirement.

4.3.3.6,2 The circuits between the above required detection instruments and the control room shall be demonstrated OPERABLE at least once per 92 days per approved procedures.

SALEM - UNIT 1 3/4 3-50 Amendment No.13

TABLE 3.3-10 FIRE DETECTION INSTRUMENTS Installed Installed ME, Instrument Location Thermal Smoke Reg'd 1.

Containment A.

Main Coolant Pumps

1. 11 2

1

1. 12 2

1

1. 13 2

1

1. 14 2

1 B.

Iodine Removal System 1

1 C.

Pressure Relief System 1

1 2.

_ Control Room A.

Ceiling Void 6

4 B.

Control Console 2

1 C.

Aux. Equip. Room 8

6 D.

Computer Room 2

1 3.

Cable Vaults

1. 1C&D el 113 3

2

1. 2A&B el 113 3

2

1. 2C&D el 113 3

2 4.

Switch Gear Rooms A.

Relay Room el 100 18 16 B.

Switch Gear el 84 18 16 C.

Vital Bus el 64 18 16 D.

Elec. Pent el 78 13 11 5.

Battery Rooms A.

1. 1A 125 V el 100 2

1 B.

1. 1 250 V el 100 3

2 C.

1. 1B 125 V el 100 2

1 D.

1. 1C 125 V el 64 2

1 SALEM - UNIT 1 3/4 3-51 Amendment No. 77, 13

TABLE 3.3-10 (Continued)

FIRE DETECTION INSTRUMENTS Installed Installed Min.

Instrument Location Thermal Smoke Reg'd.

6.

Diesel Generators A.

1. 1A 5

4 B.

1. 1B 5

4 C.

1. 1C 5

4 7.

Diesel Fuel Storage A.

1. 11 Tank el 84 2

1 B.

1. 12 Tank el 84 2

1 C.

1. 11 Fuel Trans' er Qi,7 1

1 D.

1. 12 Fuel Tran fer Pump 1

1 8.

Aux. Bldg. Vent 53 stem - El. 122 Elec. Penetration Area 2

2 Switch Gear Room 1

1 Relay Room & Control Room 3

3 9.

Fuel Handling Blc h Vent Equip. Room 3

2 Elec. Control Area 2

1 10.

Diesel Gen. Control Room 1

1 A.

1. 11 1

1 B.

1. 12 1

1 C.

1. 13 SALEM - UNIT 1 3/4 3-52 Amendment No. 7/, 13

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 responsi-bility during his absence.

6.2 ORGANIZATION 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:

Each on duty shift shall be composed of at least the minimum a.

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.

At least two licensed Operators shall be present in the c.

control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

d.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

All CORE ALTERATIONS after the initial fuel loading shall be e.

directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f.

A Fire Brigade of at least 3 members shall be maintained onsite at all times. The Fire Brigade shall not include 4 members of the minimum shift crew necessary for safe s~nutdown of the unit or any personnel required for other essential functions during a fire emergency.

SALEM-UNIT 1 6-1

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Z SENIOR VICE PRES! DENT -

ENERGY SUPPLY &

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VICE PRESIDENT -

VICE PRESIDENT -

VICE PRESIDENT -

PRODUCTION FUEL SUPPLY AND N RUCTION NUCLEAR REVIEW BOARD GENER AL MANAGER -

GENERAL MANAGER -

GENER AL MANAGER -

MAN L SUPP Y CEN GUALI Y ASSURANCE P DUCTION

• ENGINEERING q R ENT mb M AN AGE R -

MANAGER -

NUCLEAR SALEM GENERATING

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FIGURE 6.21. OFFSITE ORGANIZ ATION FOR FACILITY MANAGEMEivT AND TECHNICAL SUP90RT s

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a A$$l$ TANT Chit F MAIN TE N A NCE TO E NGtNE E R t ENGINE E R MANAGER STATION ST ATION ST ATION OF FICE REACTOR OPE R ATfMG PE R F OR MANCE AOhm asts-OU ALIT V On ASSUR ANCE E NGINE E R E NGINE E R '

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W SE NIOR SE NiOR SENIOR 5HIFT SE NIOR StN1OR RF MAIN Tf N ANCE SE CURI TY SAFETY P RWSOR-SUPE RVISOR

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f f athee the Ch.ef E nyneer or the Statoen Opereime Enyne,e w a meet the speeldientions of Ro iLE CT RICI ANS ANSI N18 1 1971for the pomeen of Operet.ons Menesee. All Sensor fhdt Superesars shed 7

report to en endie dual erho shall hold a $ensor Reactor Operatoe's 1.cenes and hee

• sen years o

of sespone tde power plant esponence of eshech a menemum of twG years shan tie nuclear MACHINISTS e

power plant emperience. A mensmune of two of the someineng fw years of power psont esperience may be fidf>Med try satisf actory conisnetion of academ c oe retand wchn. cal E OUt PUE N T TE CHN1 CAL 5TATiON troeneng on e one h>r1pne hme bens.

OPE R AY OR AssesTANTS ME CH ANICS Responsetde for the Fee Protocoon Ptoyom N

lenpiementat.on FIGURE 6.2.2 F ACILITY ORGANIZATION - b3LEM GENER ATING STATION U

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #

LICENSE APPLICABLE MODES CATEGORY 1, 2, 3 & 4 5&6 50L 1

1*

OL 2

1 Non-Licensed 2

1

• Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS after the initial fuel loading.

1. Shif t crew composition may 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 accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

SALEM-UNIT 1 6-4

ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Senior Performance Supervisor - Chemistry /HP 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 maintained under the direction of the Assistant to Manager 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, 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Safety Supervisor and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975, except for Fire Brigade training sessions which shall be held st least quarterly.

6. 5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE (SORC)

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

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

Chairman:

Chief Engineer Vice Chairman:

Assistant to Manager Member:

Station Operating Engineer Member:

Station Performance Engineer Member:

Reactor Engineer Member:

Senior Shift Supervisor Member:

Senior Performance Supervisor - I&C Member:

Senior Performance Supervisor - Chem /HP Member:

Maintenance Engineer ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the SORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in 50RC activities at any one time.

SALEM-UNIT 1 6-5 Amendment No. J$, 77, 13

ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.).4 The 50RC shall meet at least once per calendar month and as convened by the SORC Chairman or his designated alternate.

QUORUM 6.5.1.5 A quorum of the SORC shall consist of the Chairman or his designated alternate and four members including alternates.

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

a.

Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the 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 od forwarding of reports covering evaluation and recommenda.lons to prevent recurrence to the General Manager - Electric Production and to the Chairman of the Nuclear 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 Comission.

g.

Review of facility operations to detect potential nuclear safety hazards, h.

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

SALEM-UNIT 1 6-6

ADMINISTRATIVE CONTROLS 1.

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

J.

Review of the Emergency Plan and implementing procedures and shall submit recommendec :hanges to the Chairman of the Nuclear Review Board.

, AUTHORITY 6.5.1.7 The Station Operations Review Committee shall:

a.

Recommend to the Station Manager written approval or disapproval of items considered under 6.5.1.6(a) through (d)above.

b.

Render detenninations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the General Manager-Electric Production and the Nuclear Review Board of disagreement between the S0RC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The Station Operations Review Committee shall maintain written minutes of each meeting and copies shall be provided to the General Manager-Electric Production and Chairman of the Nuclear Review Board.

6.5.2 NUCLEAR REVIEW BOARD (NRB)

FUNCTION 6.5.2.1 The Nuclear Review Board shall function to provide independent review and audit of designated activities in the areas of:

a.

nuclear power plant operations b.

nuclear engineering SALEM-UNIT 1 6-7

ADMINISTRATIVE CONTROLS c.

chemistry and radiochemistry d.

metallurgy e.

instrumentation and control f.

radiological sa'ety g.

mechanical and electrical engineering h.

quality assurance practices COMPOSITION 6.5.2.2 The NRB shall be composed of the:

Chairman:

General Manager-Electric Production Vice Chairman:

Assistant to General Manager-Fuel Supply Member:

General Manager-Licensing and Environment Member:

Manager-Nuclear Operations Member:

Manager-Quality Assurance Member:

Project Manager-Hope Creek Member:

Manager-Salem Generating Station Member:

Principal Engineer Member:

Manager - Hcpe Creek Generating Station ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the NRB Chairman to serve on a temporary basis; however, no morL than two alternates shall participate as voting members in NRB activities at any one time.

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

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

SALEM-UNIT 1 6-8 Amendment No. E, g, 13

LIST OF FIGURES Figure No.

Title Pm 3.1-1 Biological Sampling Stations in the Vicinity of Artificial Island...........................

3.1-25 5.2-1 Organization Chart Showing Corporate Interrelationships....

5.2-2 Amendment No.13 v

5.0 ADMINISTRATIVE CONTROLS 5.1 RESPONSIBILITY 5.1.1 The implementation of the surveillance programs external to the plant, including sampling, sample analysis, evalua-tion of results and the preparation of required reports is the responsibility of the Licensing and Environment Department in the Engineering and Construction Department.

This Department is responsible for the assignment of personnel to the above functions, for assurance that appropriate written procedures, as described in Sectio:.1. 5.1, are utilized in the surveillance program activities and for _ assuring the quality of surveillance program results, as described in Section 5.5.3.

5.1.2 The Station Manager or his delegated alternate is re-sponsible for operating the plant in compliance with the limiting conditions for operation as specified in the Environmental Technical Specifications and for the in-plant monitoring necessary to ensure such operation.

His re-ponsibility " includes assurance that plant activities are c or.d uc ted in such a manner as to provide continuing pro-tection to the environment and that personnel performing such activities use appropriate written procedures as described in Section 5.5.

5.1-1 Amendment No. 13

5.2 Organization 5.2.1 Figure 5.271 identifies the corporate relationship between the Licensing and Environmental Department and the station Manager and also shows the organization of the Licensing and Enviromment Department.

Figure 6.2.2 of the Radiological Safety Technical Specifications identifies the Production Department Station Organization.

5.2.2 The Nuclear Review Board (NRB) and Station Operations Rr-iew Committee (SORC) are shown in Figure 5.2-1.

They are advisory groups to the Vice President -

Production and the station Manager respectively.

5.2-1 Amendment No.13

Un>

M M CZ H

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SE NIOR VICE PREllOENT -

ENERGY StFPLY &

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VICE PREllDENT -

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P OOUCilON ND TRMIM NUCEEAR REVIEW 80ARD 9

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MAN AGE R -

SALEM GE NE R ATING NUCLEAR OPE R ATIONS 5TAilON HEAI.TH NUCLEAR NUCLE AR FUEL ENIISICIST 0.A.

PLANT CYCLE ENGINEER ENGINEER E NGINE E R p

RESPONSIBLE FOR OVERALL on-sin STATION Q.A.

FIRE PROTECTION PROGRAM

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e FIGURE 5.2-1 y

OFFSITE ORGANIZATION FOR FACILITY MANAGEMENT AND TECilNICAL SUPPORT w"