ML20215N292

License NPF-56 for Facility

ML20215N292
Person / Time
Site:	Seabrook
Issue date:	10/17/1986
From:	Vollmer R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20215N294	List: ML20215N292 ML20215N296 ML20215N309
References
NUDOCS 8611050191
Download: ML20215N292 (9)

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UNITED STATES 8

NUCLEAR REGULATORY COMMISSION o

WASHINGTON. D. C. 20555

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PUBl.IC SERVICE COMPANY OF NEW FAMPSHIRE, ET AL.*

DOCKET NO. 50-443 SEABROOK STATION, UNIT NO. 1 FACII.ITY OPERATING LICENSE I.icense No. NPF-56 1.

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

A.

The application for license filed by the Public Service Company of New Hampshirc (PSNP), as agent and representative of the utilities listed below (and hereafter the utilities listed below includino PSNP collectively referred to as licensees) complies with the standards and

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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 other agencies or bodies have been duly made; 8.

Construction of the Seabrook Station, Unit No.1 (the facility) 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 Comission; C.

The facility will operate in conformity 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 (ii) 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 2.0 below):

• Public Service Company of New Hampshire is authorized to act as agent for the: Canal Electric Company, Connecticut I.ight and Power Company, EUA Power Corporation, Pudson I.ight & Power Company, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, New Fampshire Electric Cooperative, Inc., Taunton Municipal lighting Plant, the United Illuminating Company, and Vermont Electric Generation and Transmission Cooperative, Inc., and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

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i E.

PSNP is technically oualified.to engage in the activities authorized by this license in accordance with the Comission's regulations set forth in 10 CFR Chapter I; F.

The licensees have satisfied the applicable provisions of 10 CFR 140

" Financial Protection Requirements.and Indemnity Agreements" of the Commission's regulations; G.

The issuance of this license will not be inimical to the comon de-fense and security or to the health and safety of the public; P.

After weighing the environmental, economic, technical and other bene-fits of the facility against esivironmental and other costs and considering available alternatives, the issuance of Facility Operating l.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 51 of the Comission's regulations and all applicable requirements have been-satisfied; and I.

The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Comission's regulations in 10 CFR 30, 40 and 70.

2.

Based on the foregoing findings regarding this facility, Facility Operating t.icense No. NPF-56 is hereby issued to Public Service Company of New Hampshire et al. (the licensees) to read as follows:

A.

This licente applies to the Seabrook Station, Unit 1, (the facilityl a pressurized water nuclear reactor and associated equipment owned by the licensees. The facility is located in Seabrook Township, Rockingham County, New Hampshire on the southeastern coast of the State of New Hampshire 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 Comission hereby licenses:

(1)

PSNP, pursuant to Section 103 of the Act and 10 CFR 50, to possess, use and operate the facility at the designated location in Rockingham County, New Hampshire in accordance with the procedures and limitations set forth in this license; (2)

The licensees, to possess the facility at the designated location in Rockingham Ccunty, New Hampshire in accardance with the procedures and limitations set forth in this license; 9

(3)

PSNH, pursuant to the Act and 10 CFR 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with limitations herein and in accordance with the limitations for storage and amounts reouf red for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)

The following criteria apply to the storage and handling of new fuel assemblies in the new fuel storage vault, spent fuel pool (when dry) and shipping containers:

a.

1.

No more than two fuel assemblies shall be out of approved shipping containers or fuel assembly storace racks at any one time.

2.

PSNH shall maintain edge-to-edge distance of 12 inches:

a.

Between the above two fuel assemblies, b.

Between fuel assemblies (out of storage) and the shipping container array, and c.

Between fuel assemblies (out of storage) and the storage rack arrays.

b.

No more than 60 loaded shipping containers shall be allowed onsite at any one time.

c.

No shipping container loaded with fuel shall be outside for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of receipt onsite.

These criteria do not apply to those fuel assemblies in the process of being transported to or from the reactor vessel.

(5)

PSNH, pursuant to the Act and 10 CFR 30, 40 and 70, to receive, 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;

(6)

PSNH, pursuant to the Act and 10 CFR 30, 40 and 70, to receive, possess, and use in amounts as recuired any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and j

(7)

PSNP, pursua'nt to the Act and 10 CFR 30, 40 and 70, to possess, 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 and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power f.evel The licensee is authorized to load fuel and perform precriti-cality tests in accordance with the conditions specified herein for fuel loading and precritical operations.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix-A and the Environmental Protection Plan contained in Appendix B, 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.

(3)

Inservice Inspection Procram (Section 5.7.4, 6.6.3, SER, SSER 3, SSER 4, SSER 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 10 CFR Section 50.55afo)(4),

for NRC staff review and approval within six months from the date of this license.

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(4)

Radiation Data Management System (Section 7.5.7.2, SER, SSER 5)

Qualified non-fuse dependent isolation devices shall be installed and shall be operational before startup after the first refueling outaae.

• The parenthetical notation followino 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.

A

. (5)

Fire Protection (Section 9.5.1.4, SER, SSER 4, SSER 5, SSER 6)

The applicant shall have the PVAC charcoal filter unit detection systems and any other modifications dictated by the fire hazards analysis complete and operable before exceeding 5*;

of rated power, and shall update the reports entitled " Fire Protection Program and Comparison to BTP APCSB 9.5-1, Appendix A" and " Fire Protection of Safe Shutdown Capability (10 CFR 50, Appendix R)" by November 30, 1986.

(6)

Accident Monitorina Instrumentation, TMI Action Plan Item II.F.1 (Section 11.5.2, SSER 2, 55ER 51 Before startup following the first refueling outage, PSNP shall demonstrate that the iodine / particulate sampling system is operable and will perform its intended function.

(7)

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 Management Agency's final rule, 44 CFR 350, is an indication that a.ma.ior substantive problem exists in achieving or maintaining an adequate state of emercency preparedness, the provisions of 10 CFR Section 50.54 (s)(I) will apply.

(8)

Initial Test Procram (Section 14, SER)

Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR Section 50.59 shall be reported in accordance with Section 50.59(b) within one month of such change.

(9) leakage Reduction Measurement Program (Section 15.9.15, SER, 55ER 5)

Before proceeding above 5% of rated power, PSNP shall submit the results of leak rate measurements which demonstrate that its leakage reduction program has been sucessfully implemented.

(10)

Safety Parameter Display System (Section 18, SER, SSER 4, SSER 6)

Before restart following the first refueling outage, PSNP shall have operational a Safety Parameter Display System (as described in PSNP's submittals dated January 6, 1986 and April 2, 1986, and as modified by the staff's audit findings) that is acceptable to the NRC.

(11) Inadvertent Boron Dilution PSNP shall maintain a boron concentration of at least 2000 (two thousand) parts per million (PPM) in the reactor coolant and make-up water systems during fuel loading and precriti-cality testing.

PSNP shall take the following special measures

. to verify sources of water borated to less than 2000 ppm will be isolated from the reactor coolant system (RCS) and that the boron concentration level in the RCS shall be maintained at a level of at least 2000 opm:

a.

Grab samples will be manually taken from the reactor coolant and make-up water systems and analyzed at least once per shift to verify that the boron concentration is at least 2000 ppm.

b.

The make-up water system will be sampled and analyzed each time any water is added to the system to verify that the boron concentration is at least 2000 ppm.

c.

The valves listed in Attachment 2 of PSNH'S submittal SBN-1196 dated September 17, 1986 will be mechanically locked closed with chains and padlocks to prevent borated water at concentration levels less than 2000 ppm from flowing into the RCS.

d.

Certain valves identified in Attachment 2 of PSNH's submittal SBN-Il96 dated September 17, 1986 will be locked closed except for the infrequent occasions when an activity required by plant chemistry reouires these valves to be opened for a short time interval.

In order to preclude inadvertent dilution at these times, an independent confirmation of valve positions will be made by a separate person knowledgeable of the systems beino used each time the valves are manipulated, e.

Each time valves are manipulated and water is added to the RCS, the licensee shall sample the RCS both before and after the addition of the water to determine the level of boron concentration of the water in the RCS and to ensure that the level is at least 2000 ppm.

f.

Verify on a daily b' asis that the valves listed in PSNH's SBN 1196 submittal dated September 17, 1986 are chained locked closed (when not open for plant chemistry-related activities as noted in (ll)d above).

- D.

PSNH is exempted from the Section III.D.2(b)(ii) containment airlock testing requirements of Appendix J to 10 CFR 50, due to the special circumstance described in Section 6.2.6 of SER Supplement 5 authorized by 10 CFR Section 50.12(a)(2)(fii). This exemption authorized by law, will not present an undue risk to the public health and-safety and will not be inimical to the common defense and security of the public. The exemption is hereby granted pursuant to 10 CFR Section 50.12 (51 FR 25279 July 11, 1986).' With the granting of this exemption, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

PSNP is hereby exempted from provision of 10 CFR Section 70.24 insofar as this section applies to the storage and handling of new fuel assemblies in the new fuel storage vault, spent fuel pool (when dry) and shipping containers.

E.

PSNP shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification, and safeguards contingency plans, previously approved by the Commission and all amendments and revisions to such plans made pursuant to the authority of-10 CFR Section 50.90 and 10 CFR Section 50.54(p).

The plans, which contain Safeguards Information protected under 10 CFR Section 73.21, are entitled:

"Seabrook Station Physical Security Plan", with revisions submitted through June 16, 1986, "Seabrook Station Security Training and Qualification Plan", with revisions submitted through August 31, 1982; and "Seabrook Station Safeguards Contingency Plan". with revision submitted through November 30, 1981.

F.

PSNP 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, sub. ject to the following provision:

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

G.

Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, PSNH 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 Part 50.73(b), (c) and (el.

H.

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

I.

This license is effective as of the date of issuance and shall expire at Midnight on October 17, 2026.

FOR THE NUCLEAR REGULATORY COMMISSION Richard H. Vollmer, Acting Director Office of Nuclear Reactor Regulation Attachments /Appendice.s:

1. - Work Items to be Completed 2.

Appendix A - Technical Specifications (NUREG-1207) 3.

Appendix B - Environmental Protection Plan Date of Issuance: OCT 171996 Y

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ATTACHMENT 1 TO NPF-56 This attachment identifies preoperational tests and other items which must be completed to NRC's satisfaction and identifies required timing for their completion.

1.

Adopt final approved procedures for Modes 2 through 5 one week prior to entering the mode for which they are required.

2.

Prior to criticality:

a.

Complete preoperational testing and test results review for the following modified systems and components:

(1) Emergency feedwater (ST-51, ST-53, ST-55),

(2) Steam dump and main steam isolation bypass valves (ST-55).

(3) Pressurizer power-operated relief valves (PT 40. I test exception),

b.

Provide satisfactory engineering solutions to outstanding construction deficiencies (10 CFR 50.55(e) reports).

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