ML20244E069

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Requests Proposed License Conditions & Revs (W/Supporting Sser Inputs) to Encl Proposed License NPF-56 Be Submitted by 860708.Issuance of License Expected on or About 860710
ML20244E069
Person / Time
Site: Seabrook, 05000000
Issue date: 07/11/1986
From: Novak T
Office of Nuclear Reactor Regulation
To: Cunningham R
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20235T530 List: ... further results
References
FOIA-87-51 NUDOCS 8607220230
Download: ML20244E069 (9)
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11 JUL 586 MEMORANDUM FOR: Richard E. Cunningham, Director Division of Fuel Cycle and Material Safety, NMSS j FROM: Thomas M. Novak, Acting Director  !

Division of PWR Licensing-A g-Q

SUBJECT:

SEABROOK STATION UNIT 1 OPERATING LICENSE STATUS l

A copy of the proposed license for Seabrook Station, Unit I without attachments is provided in Enclosure 1. The proposed license has been l l:

modified to reflect all coments received from the staff to date. A draft of Attachment I to the license has been requested from Region I.

All proposed license conditions, and revisions to this license (with supporting SSER inputs) along with your concurrence are needed prior to lj issuance of the license expected on about July 10, 1986. Please provide this information no later than July 8( 1986.

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Original signed by7 Thocas M. Novak -

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Thomas M. Novak, Acting Director Division of PWR Licensing-A

Enclosures:

As stated j Distribution:

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MEMORANDUM FOR: Richard E. Cunningham, Director Division of 1 Fuel Cycle and Material Safety, NMSS l FROM: Thomas M. Novak, Acting Director i Division of PWR Licensing-A l

SUBJECT:

SEABROOK STATION UNIT 1 OPERATING LICENSE STATUS  ;

l 1 A copy of the proposed license for Seabrook Station, Unit I without i attachments is provided in Enclosure 1. The proposed license has been modified to reflect all coments received from the staff to date. A draft of -

Attachment I to the license has been requested from Region I. 4 l All proposed license conditions, and revisions to this license (with supporting SSER inputs) along with your concurrence are needed prior to issuance of the license expected on about July 10, 1986. Please provide this  !

information no later than July 8, 1986.

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Thomas M. Novak, Acting Director i Division of PWR Licensing-A l

Enclosures:

As stated l l

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ENCLOSURE I

/ap usgjog UNITED STATES

! % ,., g NUCLEAR REGULATORY COMMISSION g  :; W ASHINGTON, D. C. 20656 A.....' DRAFT PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE, ET At.*

DOCKET NO. 50-443 SEABROOK STATION, UNIT NO. 1 FACILITY OPERATING LICENSE l.icense No. NPF-56

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1. The Nuclear Regulatory Comission (the Commission) has found that: .

A. The application for license filed by Public Service Company of New Hampshire, as agent and representative of 12 utilities listed below and hereafter referred to as licensees, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I, and all required notifications to o_ther agencies or bodies have been duly made;

8. Construction of the Seabrook Station, Unit No.1 (the facilityl has been substantially completed in conformity with Construction Permit No. CPPR-135 and the application, as amended, the provisions of the Act, and the regulations of the Commission; E

C. The facility will operate in confomity with the application, as amended, the provisions of the Act, and the regulations of the Commission, (except as exempted from compliance in Section 2.D below);

D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (iil that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I, (except as exempted from compliance in Section 2D below):

  • Public Service Company of New Fampshire is authorized to act as agent for the: Canal Electric Company, Central Maine Power Company, Central Vermont Public Service Corporation, Connecticut I.ight and Power Company, Fitchburg Gas & l.ight Company, Bangor Fydro-Electric Company, Hudson I.ight & Power Company, Maine Public Service Corporation, Massachusetts Municipal Wholesale riectrJc.Lompany,JontaupJ4Mdc. Company,.SewhM fP werhpaDy..!W d-**" famps.. . , s . m wvm Ptve r4ne:Mubl R Mice %...; J L byAire, #-

Taunton Municipal L.ighting Plant, the United Illuminating Company, and Vermont Electric Generation and Transm!ssion Cooperative, Inc., and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

DRAFT  :

E. Public Service Company of New Hampshire is technically qualified to engage in the activities authorized by this license in accordance with 4 the Comission's regulations set forth in 10 CFR Chapter I; F. The licensees have satisfied the applicable provisions of 10 CFR Part 140 " Financial Protection Requirements and Indemnity Agreements" of the Commission's regulations; G. The issuance of this license will not be inimical to the coninon de-fense and security or to the health and safety of the public; F. After weighing the environmental, economic, technical and other bene-fits of the facility against environmental and other costs and '

considering available alternatives, the issuance of Facility Operating I.icense No. NPF-56, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicabic requirements have been satisfied; and I. The receipt, possession, and use of source, byproduct and special l nuclear material as authorized by this license will be in accordance I with the Comission's regulations in 10 CFR Parts 30, 40 and 70.

2. Based on the foregoing findings regarding this facility, Facility Operating l t.icense No. NPF-56 is hereby issued to Public Service Company of New  :

Fampshire et al. (the licensees) to read as follows: j A. This license applies to the Seabrook Station, Unit 1, a pressurized water nuclear reactor and associated equipment (the facility), owned by the licensees. The facility is located in Seabrook Township, Rockingham County, New Fampshire on the southeastern coast of the State of New Fampshire and is described in the licensees' " Final Safety Analysis Report", as supplemented and amended, and in the licensees' Environmental Report, as supplemented and amended.

B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses; (1) Public Service Company of New Fampshire (PSNH) pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the designated location in Rockingham County, New Fampshire in accordance with the procedures and limitations set forth in this license; (2) The licensees, to possess the facility at the designated wo4an in Rocki.nghe= r~=+y. Mempshite irLaccordance.with--

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(3) PSNF, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;

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(4) PSNH, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to re-ceive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) PSNH, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to re-ceive, possess, and use in" amounts as reovired any byproduct, source or special nuclear material without restriction to chemical or physical fortn, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and .

(6) PSNP, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to pos-sess, but not separate, such byproduct and special nuclear materials as may be produced by the operations of the facility.

C.. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations, set forth in 10 CFR Chapter I

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and is subject to all applicable provisions of the Act and to the rules, i regulations, and orders of the Commission now or hereafter in effect; and I is subject to the additional conditions specified or incorporated below:

(11 Maximum Power level Public Service Company of tew Hampshire is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100% rated power) in accordance with the conditions specified herein. Pending Comission approval, this  ;

license is restricted to power levels not to exceed 5 percent of rated power (170 megawatts thermal). The items identified in Attachment 1 to this license shall be completed as specified.

Attachment 1 is hereby incorporated into this license.

(2) Technical Specification and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 8, both of which are attached hereto, are hereby incorporated into this license. Public Service Company of New Hampshire shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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DRAFT (3) Inservice Inspection Program (Section 5.2.4, 6.6.1, SER, 55ER 3, 55ER 4 55ER 5)*

PSNH shall submit the inservice inspection program which conforms to the ASME code in effect 12 months prior to the date of this license, in accordance with 50.55a(g)(4), for NRC staff review and approval within six months from the date of this license.

(4) Fire Protection (Section 9.5.1, SER, SSER 4 and SSER 5)

PSNH shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report, the Fire Protection Program report, and the Fire Protection of Safe Shutdown Capability report for the facility, as supplemented and amended, and as approved in the Safety Evaluation Report, dated March 1983 and Supplement 4, dated May 1986 and Supplement 5 dated June 1986, subject to the following provision:

PSNH may make changes to the approved fire protection program without prior approval of the Comission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(5) Operating Staff Experience Requirements _(Section 13.1.2.2, SSER 11 Seabrook shall have a licensed senior operator on each shift who has had at'least 6 months of hot operating experience on a same type plant, including at least 6 weeks at power levels greater than 20 percent of full power, and who has had start-up and shutdown experience.

(6) Emergency preparedness (Section 13.3, SER, SSER 4)

In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emer CFR Section 50.54 (s)(gency preparedness, the provisions of 10

2) will apply.

(7) Initial Test Program (Section 14, SER) l Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR cn (04heU B ze r i^d '

E FM A 4 1nonth-ef $6th" change. #r MMdace* " ~ * 'wi.th

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  • The parenthetical notation following the title of many license conditions de-notes the section of the Safety Evaluation Report and/Or its supplements wherein the license condition is discussed.

MAFT 1

(8) Salem ATWSEvent, Generic l.etter 83-28 (Section 15.8, SEp.

55ER 5 PSNH shall submit response to and implement the requirements of f I

Generic letter 83-28 on a schedule which is consistent with I that given it its letter dated .

(9) Safety Parameter Display System (Section 18, SER, SSER 4, SSER 5)

Prior to restart following the first refueling outage, PSNP shall have operational a Safety parameter Display System (SPDS) as described in PSNP's submittals dated January 6,1986 and April 2,1986, that shall include the following modifications:

1. Crantinuous display of the top level critical safety function summary at the assigned SPDS control room location.
2. Addition of, or satisfactory justification for, not adding i RPR flow and hydrogen concentration parameters to l appropriate SPDS screens,
3. Addition of a containment isolation status screen on SPDS, or improvement to the current containment isolation display to be satisfactorily recognizable froe the assigned SPDS location in the control room.

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4. Addition of a radiation monitoring screen to display at l least steam generator (or steam line) and stack radiation,
5. Improvement of the Heat Sink screen for consistency in labelino, and the Subcriticality screen for mode dependency so as not to mislead operators, and
6. Addition of approved isolation devices between the Reactor Vessel level Instrumentation System (N.IS) and SPOS.

1' PSNP is exempted from the Section III.D.2(b)(ii) containment airlock D.

testing requirements of Appendix J to 10 CFR Part 50, due to the )

special circumstance described in Section 6.2.6 of SER Supplement 5 authorized by 10 CFR 50.12(a)(2)(iii). This exemption is authorized by law, will not present an undue risk to the public health and safety and is consistent with the common defense and security. The l exemption is hereby granted pursuant to 10 CFR 50.12. With the granting of this exemption, the facility will operate, to the extent v.w a ,a u . <.

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Commission.

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DRAR  :

In addition; an exemption was previously granted pursuant to 10 CFR 50.12. A. partial exemptien from those portions of General Design Criteria 4 of Appendix A to 10 CFR Part LO which require protection i of structures, systems and components important to safety against dynamic effects associated with postulated reactor coolant system pipe breaks was granted on November 22, 1985, for a period ending with the completion of the second refueling outage for Seabrook Station, Ur.it 1 or the adoption of the proposed rulemaking for modification of GDC-4 whichever occurs first. Effective May 12, 1986, GDC-4 has been modified to exclude from the design basis the protection of structures, systems and components against dynamic effects associated with postulated pipe ruptures of primary coolant loop piping in PWRs when analyses demonstrate the probability of .

rupture of such piping to be extremely low under design basis conditions (51 FR 12502 April 11,1986).

E. Public Service Company of New Fampshire shall fully implement and maintain in effect all provisions of the physical security, guard trsining and qualifica :on, and safeguards contingency plans, previously approved '- the Comission and,,all amendments and revisions r.ade put a. to the authority of 10 CFR 50.90 and 10 CFR The plans, which .ain Safeguards Information protected under 10 CFR 73.21, are er.. .tled: "Seabrook Station Physical Security Plan",

with revisions submitted through March 21,1986, "Seabrook Station Security Training and Qualification Plans", with revisions submitted through August 31, 1982, and "Seabrook Station Safeguards Contingency Plan", with revisions submitted through November 30, 1981.

F. Except as otherwise provided in the Technical Specification or Environ-mental Protection Plan, Public Service Company of New Hampshire shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c) .

and (e).

G. The licensees shall have and maintain financial protection of such type l and in such arrounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

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y ENCLOSURE 2 DRAFI l

1. Radiation Data Management System - Qualified non-fuse dependent isolation devices be installed and operational (SSER5-7.5.2.21.

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2. Fire Protection - Applicant must provide an analysis which justifies the lack of any fire suppression system for the charcoal adsorbers (SSER 5

-9. 5.1. 4 ) ,

i 3. Solid Waste Management System - Applicant shall submit an acceptable description of the spill control methods of the cement solidification system (SSEE 5- 11.4.... -

4. TMI Action Flan Item II.F.1, Accident Monitoring Instrumentation -

Demonstrate that the iodine / particulate sampling system is operable and will perfors its intended function (SSER 5-11.5.2).

5. le'akage Reduction Measurement Program - The applicant shall submit the

, result of leak note measurements sufficient to show that its leakage reduction program has been successfully implemented (SSER 5 - 15.9.15).

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