ML17139B211

Amend 5 to License NPF-14,authorizing Operation at 100% Rated Power & Deferring Full Qualification Documentation on Interim Gas Pipeline Procedures to Dec 1982

ML17139B211
Person / Time
Site:	Susquehanna
Issue date:	11/12/1982
From:	Eisenhut D Office of Nuclear Reactor Regulation
To:
Shared Package
ML17139B212	List: ML17139B211 ML17139B213
References
NUDOCS 8211220497
Download: ML17139B211 (12)

Text

PENNSYLVANIA POllER

& LIGHT COMPANY AA NC.

SUS(}UEHANNA S AN t;

C TION, UNIT 1 Amendment No.

5 License No. NPF-14 1.

The Nuclear Regulatory Commission (the Commission or the NRC) having found that:

A.

The application, as amended for a license filed by the Pennsylvania Power

& Light Company and the Allegheny Electric Cooperative, Inc. (the 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, 8.

The facility will operate in conformity 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 comnon 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 in paragraphs 2.C.(1), 2.C.(5),

2.C.(13), 2.C.(16), 2.C.(18)(a), 2.C.(19),

2.C.(20), 2.C.(23),

2.G.(a), 2.I and the addition of paragraphs 2.C.(18)(d), 2.C.(18)(e), 2.C.(29), 2.C.(30),

2.C.(31), 2.C.(32),

and 2.J to the Facility Operating License No. NPF-14 to read as follows:

(1)

Maximum Power Level Pennsylvania Power

& Light Company (PP&L) is authorized to operate the facility at reactor core power levels not in excess of 3293 megawatts thermal in accordance with the conditions specified herein and in Attachment 1 to this license.

The preoperational

tests, startup tests and other items identified in Attachment 1 to this license shall be completed as specified.

Attachment 1 is hereby incorporated into this license.

(5) gualification of Purge Valves (Section 6.2.4, SSER81; 22, SSER84) a)

PP&L shall block valves HV-15703 and HV-15713 o a n t o

opening by

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diameter, pending satisfactory qualification of the affected val ves.

b) By December 31, 1982, PP8L shall submit purge valve qualification documentation which shows the maximum opening of 18-in.

and 24-in.

valves for which the top pin shear stress will be within conser-vative allowables

(<0.4 Sy) during the maximum torque loads of a lOCA and seismic event.

PP8L shall implement changes approved by the staff after the completion of the staff's review of these documents.

(13)

Ilearby Facilities (Section 2.2.2,

SSER03, SSER84)

(a)

PP8L shall submit a complete report for NRC review and approval delineating interim gas line flow restrictions to 39 m3/sec of natural gas.

(b)

By December 31, 1982, the approved interim gas line flow restrictions and procedures addressing system configuration changes shall be implemented.

(c)

By February 28, 1983, PPGL shall submit a report for HRC review and approval describing either:

(1)

Permanent modifications which limit flow to 39 m3/sec, or (2)

Relocation of the pipeline to a safe distance from the facility.

(d)

By September 30, 1984, the selected modification or relocation of the pipeline shall be completed.

(16) lletwell to Drywell Vacuum Breakers (Section 6.2.1.8,

SSER83, SSERP4)

Prior to startup following the first refueling outage, PP8L shall implement design modification on the wetwell/drywell vacuum breaker valves that include:

a) installation of new disc assemblies, new shaft bearing caps; and b) replacement of the shaft, keys and turnbuckle with stronger materials.

(18)

Environmental (}uglification (Section 3.11,

SER, SSERPl,

SSERk2, SS R

SER (a)

PP8L shall complete all actions related to environmental qualification of equipment on a schedule specified in Section 3.11 and Appendix 3.B of Supplement No.

3 of the Safety Evaluation Repor t with the exceptions of Section 3.11.5. (1) and Section 3.11.5.(2)(e).

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(d)

By April '15, 1983, PPBL shall implement the maintenance and surveillance schedule for components requiring initial maintenance and surveillance after the first year of operation.

(e)

Prior to startup following the first refueling outage, PP8L shall implement the required equipment qualifications for equipment pursuant to Section 5.3 of NUREG-0803 for and SDV break environment.

(19)

Assurance of Proper Design and Construction (Section 17.6, SSER 83, SSER P4)

(a)

By December 31, 1982, PP8L shall review and categorize discrepancies on large pipe anchors outside containment.

(b) By December 31, 1982, PP8L shall restore to their original design requirements, discrepancies in large pipe anchors outside containment requiring more complex analysis than used in the original design.

(20)

Emergency Preparedness (Appendix D, SSER 81, SSER 82; 13.3, SSER 04)

By March 1, 1983, PP8L shall certify to the NRC staff the completion of the following offsite emergency preparedness items:

(a) Adequate supplies of KI for offsite emergency workers are obtained by the State of Pennsylvania to fulfill the existing State plan or a contingency plan is developed that reflects the inability to obtain supplies to support the existing State plan.

(b) Adequate supplies of dosimetry for offsite emergency workers are obtained by the State of Pennsylvania to implement the existing State plan or the State plan is revised accordingly.

(c) State and county plans are modified as necessary to account for the abandonment of the field Emergency Operations Center concept.

(23)

Seismic and Dynamic (}uglification (Section 3.10,

SER, SSERd1, SSER SSER (b) Prior to commencement of the first refueling outage, PP8L shall perform the nonlinear analysis to qualify the In-Vessel Rack (F22-E006) to the S(RT criteria and provide the qualification documentation to the NRC staff for review and approval.

(c) By December 31, 1982, PP8L shall provide the completed final qualification report for Main Steam Isolation Value Actuator (HV-1F022A through D, flV-1F028 A through 0) to the NRC staff for review.

(d)

PP8L shall implement the NRC staff's requirements after completion of the staff's review of the final qualification report for the Main Steam Isolation Valve Leakage Control OFFICES SURNAME/

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(e) Before the 25-cycle operational limit is reached, PP&L shall replace Recirculation Discharge Valve assembly (HV-1F031 A and B) with fully qualified new assemblies including a new Limitorque actuator.

The replacement actuators shall be wired for torque seating type operation.

(f) Prior to startup following the first refueling outage, PP8L shall fully qualify the following items, to the SgRT criteria and provide the final qualification reports to the NRC staff for review.

1)

CRD vent and drain valves (C12-F010/F011) 2)

Power Range hionitor Cabinet (H12-P608) 3)

Level Switch (E41-N014) 4)

Level Switch - Condensate Storage Tanks, Suppression

Pool, HCPI Turbine Exhaust Drain Pot (E41-N002/N003, N015, N018) 5)

High Pressure Coolant Injection Turbine (15-211)

(29)

SRV Inplant Test (Section 6.2.1.8, SER; 6.2.1.5, SSER81)

Within 90 days following the staff receipt of the report providing

. the results of the inplant SRV test at the LaSalle, Unit 1 facility, PP&L shall furnish the results of its evaluation and application of the LaSalle data to assure that for Susquehanna Unit 1, )he

~T between bulk and local pool temperatures will not exceed 10 F.

(30)

Dynamic Testing and Analysis of Systems, Components, and E uipment ec on (a)

By April 1, 1983, PP8L shall provide to the NRC staff detailed analysis or testing results which demonstrate that the feed>>ater isolation valves can adequately perform their intended function and satisfy the requirements of General Design Criteria (GDC) 54 and 55 following a feedwater line break outside containment."

I (b)

Prior to exceeding five percent of full power, PP&L shall verify that all check valves relied upon for containment isolation, either within or outside containment, are dynamically qualified or PP8L shall provide a basis for continued operation and a program for qualifying such valves.

(31)

Control Room Design Revie~ (Section 22, SSER 84)

Prior to startup following the first refueling outage, PP8L shall provide a report discussing the experience, including demonstrated reliability, of the Display Control System.

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(32)

Emergency Service Water System (Section 6.3.4, SSER 84)

Prior to startup following the first refueling outage, PP8L shall complete design modifications to the emergency service water (ESW)

system, approved by the staff, to eliminate single failure in the ESW system which leads to the need for an uncooled residual heat removal (RHR) pump.

G.

Reporting to the Commission:

(a)

PP&L shall report any violations of the requirements contained in Section 2, Items C(1), C(3) through C(32),

and F of this license within twenty-four (24) hours by telephone and confirm by telegram, mailgram, or facsimile transmission to the HRC Regional Administrator, Region I, or designee, not later than the first working day following the violation, with written followup report within fourteen (14) working days.

I.

In accordance with the Commission's direction in its Statement, of Policy, Licensing and Regulatory Policy and Procedures for Environmental Protection; ran um ue yc e

mpacts, cto er

', t s

cense is su Ject to t e na reso ution o t e pending litigation involving Table S-3.

See, Hatural Resources Defense Council v. HRC, Ho. 74-1586 (April 27, 1982).

J.

This license is effective as of the date of issuance and shall expire at midnight on July 17, 2022.

FOR THE NUCLEAR REGULATORY COSIISSIOH Date of Issuance:

3 198K Darrell G. Eisenhut, Director Division of Licensing Office of Huclear Reactor Regulation

• SEE PREVI US ORC FOR CONCURRENCES, DL; LB Ili'2 OFFICE)

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G.

Reporting to the Commission:

(a)

PP8L shall report any violations of the requirements contained in Section 2, Items C(1), C(3) through C(31),

and F of thiMicense within twenty-four (24) hours by telephone and confirrp4y telegram, mailgram, or facsimile transmission to the NRC Regional Administrator, Region I, or designee, not later than the first working day following the violation, with written followup report wit in fourteen (14) working days.

I.

In accordance with the Commission's direction i its Statement of Policy, Licensing and Regulatory Policy and Procedures or Environmental Protection; ran um ue yc e mpac s, cto er is cense s su gec o

the fina reso ution o t e pending litiga on involving Table S-3.

See, Natural Resources Defense Council v. NRC,

o. 74-1686 (April 27, 1982).

J.

This license is effective as of the d

e of issuance and shall expire at midnight on July 17, 2022.

F THE NUCLEAR REGULATORY COWISSION Date of Issuance:

Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation OFFICEI SURNAME/

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