ML18081A995

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Proposed Changes to Tech Specs Apps a & B Pertaining to Administrative Controls
ML18081A995
Person / Time
Site: Salem 
Issue date: 01/31/1980
From: Schneider F
Public Service Enterprise Group
To:
Shared Package
ML18081A994 List:
References
79-15, NUDOCS 8002040261
Download: ML18081A995 (11)
v • d • e


Text

Ref. LCR 79-15 U.S. NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-272 PUBLIC SERVICE ELECTRIC AND GAS COMPANY FACILITY OPERATING LICENSE NO. DPR-70 NO. 1 UNIT SALEM GENERATING STATION Public Service Electric and Gas Company hereby submits proposed changes~to Facility Operating License No. DPR-70 for Salem Gen-erating Station, Unit No. 1.

This change request relates to the Safety and Environmental Technical Specifications (Appendices A & B) of the Operating License, and pertains to changes in the corporate and station organization.

Respectfully submitted, PUBLIC SERVICE ELECTRIC AND GAS COMPANY By: ~J~*b.

FREDERICK W. SCHNEIDER VICE PRESIDENT

Ref. LCR 79-15 STATE OF NEW JERSEY)

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FREDERICK W. SCHNEIDER, being duly sworn according to law deposes and says:

I am a Vice President of Public Service Electric and Gas Company, and as such, I signed the request for change to FACILITY OPERATING LICENSE NO. DPR-70.

The matters set forth in said change request are true to the best of my knowledge, information, and belief.

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FREDERICK W. SCHNEIDER Subscribed and this J/&i{ day Not~ry Public of /~ew Jersey

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PROPOSED CHANGE CORPORATE AND STATION ORGANIZATION SALEM UNIT NO. l TECHNICAL SPECIFICATIONS Description of Changes Change 1.

Change 2.

Change 3.

The title of an NRB member has been changed from Principal Staff Engineer to Principal Engineer.

The duties of the Senior Performance Supervisor -

Chemistry/HP have been split and are now assigned to two individuals, the Senior Performance Super-visor -

Chemistry and the Senior Performance Super-visor ~ Radiation Protection.

The additional in-dividual will be added to the SORC membership.

The training organization, presently under the Assistant to Manager, will be reassigned to the Manager - Methods.

The Assistant to Manager will maintain responsibility for coordination of the retraining and replacement training pro-gram and for ensuring the qualification of sta-tion personnel.

The management of the retrain-ing and_ replacement training program will be as-signed to the Training Engineer who reports directly to the Manager -

Methods.

The Training Engineer will be assisted by the Senior Nuclear Curriculum Supervisor who maintains an SRO license.

Reason for Changes Change 1.

Change 2.

Change 3.

The NRB member was given a promotional title change.

The duties associated with the chemistry/health physics program had come to the point where in order to maintain satisfactory effectiveness and control, separating the functions was desirable.

The functions of chemistry and radiation protect-tion (health physics) are now being performed by two distinct groups each under the control of a Senior Supervisor.

In the aftermath of TMI, increased emphasis is being placed on training by the Company.

In order to accomplish this training, a strong centralized organization is necessary.

The Company has recently committed to building a new training center which will house classroom facilities and two nuclear plant simulators, one for Salem and one for Hope Creek.

Management of this facility and responsi-bility for performance of the training will be assigned to the Training Engineer who reports to the Manager - Methods.

The station management in

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the person of the Assistant to Manager, will main-tain full responsibility for ensuring all station personnel are qualified in accordance with both NRC and Company requirements.

Safety Evaluations Change 1.

Change 2.

Change 3.

This change involves a title change.

The in-dividual continues to contribute the necessary expertise to the NRB.

No Unreviewed Safety Questions are involved.

Separation of the chemistry and radiation protection functions under two Senior Super-visors strengthens the control of both pro-grams.

Each of the Senior Supervisors will continue to meet NRC qualification require-ments.

This change is administrative in nature and no Unreviewed Safety Question is involved.

This change is organizational in nature.

The Training Engineer who reports to the Manager -

Methods, will be the manager of the new train-ing center.

He will have overall responsibility for meeting and accomplishing commitments for training at PSE&G nuclear stations.

The Senior Nuclear Curriculum Supervisor who will maintain an SRO license, will report directly to the Train-ing Engineer and be responsible for the content and conduct of the training program for licensed operators.

The Assistant to Manager -

Salem Gen-erating Station will be responsible for coordina-tion of training at the station, will review training course content and act as the interface between the training center and the individual station departments to ensure performance object-ives are being met.

This organization is considered stronger than the present scheme and will be better able to exercise control and maintain high standards of training.

No Unreviewed Safety Question is involved.

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SEE FIGURE 6.2-1 TRAINING ENGINEER SEE FIGURE 6.2-2 ASSISTANT TO MANAGER-SALEM

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DENOTES STATION MANAGEMENT NUCLEAR TRAINING PROGRAM e

INTERFACE FIGURE 6.2-3 TRAINING ORGANIZATION

ADMINISTRATIVE CONiROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member cf the fac11ity staff shall meet or exceed the minimu~

qualifications of ANSI N18. 1-1971 for comparable positions, except for the Senior Perfonnance Supervisor -

Radiatiqn Protection who shall ~eet or exceed the qua11f1cations of Regulatory Guide 1.8, September 1975.

6.4 TRAINING 6.4.1 The Assistant to Manager shall be responsible for the coordinatio'n of the retraining and replacement training program and for ensuring the qualification of the facility staff. The retraining and replacement training program shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI NlB.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-19i5, except for Fire Brigade training sessions which shall be held at least quarterly.

6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW CO~ITTEE (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 Stat1on Operations Review Committee sha11 be composed of the:

Chainnan:

Vice Chainnan:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

Merr.ber:

Member:

ALTERNATES Chief Engineer Assistant to Manager Station Operating Engineer Station Perfonnance Engineer Reactor Engineer Senior Shift Supervisor Senior Perfonnance Supervisor - I&C Senior Perfonnance Supervisor -

Chemistry Senior Maintenance Supervisor Maintenance Engineer Senior Performance Supervisor - Radiation Protection 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 SORC activities at any one time.

SALEM-UN!i 1 6-5 Amend~ent Ne. 70. 77, 13

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ADMINISTRATIVE CONTROLS

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chemistry and radiochemistry

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metallurgy

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instrumentation and control

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radiological safety

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mechanical and electrical engineering

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

Chainnan:

Vice Chainnan:

Member:

Member:

Member:

Member:

Member:

Member:

Member:

ALTERNATES General Manager-Electric Production Assistant to General Manager-Fuel Supply General Manager-Licensing and Environment Manager-Nuclear Operations Manager-Quality* Assurance Project Manager-Hope Creek Manager-Salem Generating Station Principal Engineer

~~nager - Hope Creek Generating Station 6.5.2.3 All alternate members shall be appointed in writing by the NRB Chairman to serve on a temporary basis; however. no more than two alternetes shall participate as voting members in NRB activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as detennined by the NRB thainnan 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. '* '

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REACTOR COOLANT SYSTEM BASES The reactor vessel materials have been tested to determine their initial RTNDT; the results of these tests are shown in Table B 3/4.4-1.

Reactor operation and resultant fast neutron (E>l Mev) irradiation will cause an increase in the RTNoT*

Therefore, an adjusted reference temperature, based upon the fluence and copper content of the material in question, can be predicted using Figures B 3/4.4-l and B 3/4.4-2.

The heatup and cooldown limit curves (Figures 3.4-2 and 3.4-3) include predicted adjustments for this shift in RTNDT at the end of 13 EFPY, as well as adjustments for possible errors in the pressure and temperature sensing instruments.

The actual shift in RTNDT of the vessel material will be established periodically during operation by removing and evaluating, in accordance with ASTM El85-70, reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area. Since the neutron spectra at the irradiation samples and vessel inside radius are essentially identical, the measured transition shift for a sample can be applied with confidence to the adjacent section of the reactor vessel.

The heatup and cooldown curves must be recalculated when the ~RTNDT determined from the surveillance capsule is different from the calcu ated ~RTNDT for the equivalent capsule radiation exposure.

The pressure-temperature limit lines shown on Figure 3.4-2 for reactor criticality and for inservice leak and hydrostatic testing have been provided to assure compliance with the minimum temperature require-ments. of Appendix G to 10 CFR 50.

The number of reactor vessel irradiation surveillance specimens and the fre ncies for removing and testing these specimens are provided in

--T"t"""'-'""""L.W:e~~* 4I-~ to assure compliance with the requirements of Appendix H to lo CFR art 50.

The limitations imposed on pressurizer heatup and cooldown and spr~y water temperature differential are provided to assure that the pre$Surizer is operated within the design criteria assumed for the fatigue analysis performed in accordance with the ASME Code requirements.

SALEM - UNIT 1 B 3/4 4-7

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