ML17139B486

Safety Evaluation Report Related to the Operation of Susquehanna Steam Electric Station,Units 1 and 2.Docket Nos. 50-387 and 50-388.(Pennsylvania Power & Light Company; Allegheny Electric Cooperative,Incorporated)

ML17139B486
Person / Time
Site:	Susquehanna
Issue date:	03/31/1983
From:	Office of Nuclear Reactor Regulation
To:
References
NUREG-0776, NUREG-0776-S05, NUREG-776, NUREG-776-S5, NUDOCS 8304130566
Download: ML17139B486 (24)

Text

NUREG-0776 Supplement No. 5 Ss8e~

KelliUimheiitiRepeW related to the operation of Susquehanna Steam Electric Station, Units 1 and 2 Docket Nos. 50-387 and 50-388 Pennsylvania Power & Light Company Allegheny Electric Cooperative, Inc.

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation March 1983

ABSTRACT In April 1981, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report

{NUREG-0776) regarding the application of the Pennsylvania Power 8 Light Company (the applicant and/or licensee) and the Allegheny Elec-tric Cooperative, Inc. (co-applicant) for licenses to oper'ate the Susquehanna Steam Electric Station, Units 1 and 2, located on a site in Luzerne County, Pennsylvania.

Supplement 1 to NUREG-0776 was issued in June 1981 and addressed several out-standing issues.

Supplement 2 was issued in September 1981 and addressed ad-ditional. outstanding issues..

Supplement 2 also contains NRC staff responses to the comments made by the Advisory Committee on Reactor Safeguards in its report dated August ll, 1981.

Supplement 3 was issued in July 1982 and addressed five items that remained open and closed them out.

On July 17, 1982, Operating License NPF-14 was issued to allow Unit 1 operation at power levels,not to ex-ceed 5X of rated power.

Supplement 4 to NUREG-0776 was issued in November 1982 and discusses the resolution of several license conditions.

On November 12, 1982, Operating License NPF-14 was amended to remove the 5X power restriction, thereby permitting full-power operation of Unit 1.

This supplement to NUREG-0776 addresses several issues that require resolution before licensing operation of Unit 2.

Susquehanna SSER 5

Table of Contents (Continued)

II Siting and Design................

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22 1 II.F. 1 Additional Accident-Monitoring Instrumentation...

22-1 APPENDIX A CHRONOLOGY OF NRC STAFF RADIOLOGICAL REVIEW OF THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 APPENDIX 8 BIBLIOGRAPHY APPENDIX F CONTROL ROOM DESIGN REVIEW, SUSQUEHANNA UNITS 1 AND 2 Susquehanna SSER 5

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TABLE OF CONTENTS ABSTRACT

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1 INTRODUCTION AND GENERAL DISCUSSION...

1.1 Introduction

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1.9 Summary of Outstanding Review Items..................,.

1. 10 License Conditions l-l 1"2 1-2 3

DESIGN CRITERIA FOR STRUCTURES,

SYSTEMS, AND COMPONENTS............

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3. 11 Environmental Qualification 3.11.1 Environmental Qualification of Safety-Related Electrical Equipment..................................

5 REACTOR COOLANT PRESSURE BOUNDARY.................

3-1 3"1 5-1 5.2 Integrity of the Reactor Coolant Pressure Boundary............

5-1 5.2.4 Reactor Coolant Pressure Boundary Inservice Inspection and Testing....

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.3 Reactor Vessel

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5 5"1 5"1 5.3.1 Reactor Vessel Materials.................

5.3.2 Pressure Temperature Limits 5,3.3 Reactor Vessel Integrity.................

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ENGINEERED SAFETY FEATURES 6-1 6.6 Inservice Inspection of Class 2 and 3 Components 13 CONDUCT OF OPERATIONS...............................................

13"1 13.6 Industrial Security 17 QUALITY ASSURANCE.,

17.6 Confirmatory In-Depth Review 22 TMI-2 REQUIREMENTS..............

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P 13"1 17-1 17-1 22"1 22.2 TMI Action Plan Requirements for Applicants for Operating Llicenses 0

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22-1 Susquehanna SSER 5

1 INTRODUCTION AND GENERAL DISCUSSION

1. 1 Introducti on In April 1981, the staff of the Nuclear Regulatory Commission (NRC) (the staff) issued its Safety Evaluation Report (SER)

(NUREG-0776) regarding the applica-tion of the Pennsylvania Power 8 Light Co.

(PP8 L) (the applicant and/or licensee) and the Allegheny Electric Cooperative, Inc. (the co-applicant) for licenses to operate Susquehanna Steam Electric Station, Units 1 and 2.

In June 1981, the staff issued Supplement 1 to NUREG-0776, which documented the resolution of several outstanding issues in further support of the licensing activities.

In September

1981, the staff issued Supplement 2 to NUREG-0776, which addressed the open items identified in the SER and Supplement 1.

In July 1982, the staff issued Supplement 3 to NUREG-0776, which addressed all remaining open issues from previous supplements and closed them out.

On July 17, 1982, Operating License NPF-14 was issued for Unit l.

Operation was restricted to fuel loading and low-power testing at levels not to exceed 5X rated power.

In November

1982, the staff issued Supplement 4 to NUREG-0776, which addressed the resolution of several Unit 1 license conditions that had been met.

On November 12,

1982, Amendment No.

5 to Operating License NPF-14 was issued removing the 5X power restriction, thus allowing Unit 1 operation at power levels not to exceed 100K rated power.

Each issue addressed in this report, Supplement 5 to NUREG-0776, is numbered and titled to correspond to the sections of NUREG-0776 and its earlier supple-ments where they were previously discussed.

This report addresses several issues that require resolution before Unit 2 can be licensed for operation.

Copies of this report are available for public inspection at the Commission's Public Document

Room, 1717 H Street, N.W., Washington, D.C.

and at the Osterhout Free Library, 71 South Franklin Street, Wilkes Barre, PA 18701.

Copies of this report also are available for purchase from the sources indicated on the inside front cover.

The NRC project manager for Susquehanna is Mr. Robert L. Perch.

Mr. Perch may be contacted by writing to the Division of Licensing, U.S.

Nuclear Regulatory Commission, Washington, D.C.

20555.

The following additional NRC staff members contributed to this report, which is a product of the staff.

Barry Elliot Hukam.Garg Martin Hum Dale Kers Material s Engineer Senior El ectri cal Engineer Senior Materials Engineer Plant Protection Analyst Materials Engineering Branch Equipment qualifications Branch Materials Engineering Branch Power Reactor Safeguards Licensing Branch Susquehanna SSER 5

Dennis Serig Phillip,Stoddart Ernest, Syl vester Human Factors Engineer Nuclear Engineer Mechanical Engineer Human Factors Engineering Branch Effluent Treatment Systems Branch Auxiliary Systems Branch 1.9 Summar of Outstandin Review Items In Section 1.9 of Supplement 3 to NUREG-0776, the staff summarized the status of all previously identified outstanding items.

Supplement 3 to NUREG-0776 addressed all remaining open issues from previous supplements and closed them out.

The list of additional items tabulated below are items that the applicant must address specifically for Unit 2.

Item Status Section 110.

Ultimate heat sink performance test for two unit operation ill.

Preservice inspection program 112.

Review of 10 CFR Appendix G and H

113.

TMI Action Plan items 114.

Control of heavy loads 115.

Response

to IE Bulletin 79-27 116.

Environmental qualification of electrical equipment 117.

Seismic qualification Review Team (SgRT) 118.

AC electrical distribution system

1. 10 License Conditions Open Open Open Open Open Open Open Confirmatory Open 5.2.4 5.3.1

3. 11 There were several issues for which a condition was included in Operating License NPF-14 for Unit 1 to ensure that NRC requirements would be met during plant operation.

The staff considers the issues listed below also to require license conditions for Unit 2 unless satisfactory resolution is reached on these issues before licensing.

I (1) thermal and hydraulic design (2) qualification of purge valves (3) operation with partial feedwater heating at end of cycle (4) inservice inspection program Susquehanna SSER 5

1-2

(5) nearby facilities (6) scram discharge system piping (7) environmental qualification

-(8) assurance of proper design and construction (9) seismic and dynamic qualifications (10) containment purge system (ll) additional instrumentation and control concerns (12) surveillance of control blade (13) emergency diesel engine starting systems (14) nuclear steam supply system-vendor review of procedures (15) postaccident sampling (16) instrumentation for detection of inadequate core cooling (17) modification of automatic depressurization system logic (18) effect of loss of power on alternating current pump seals (19) upgrade emergency support facilities (20) safety relief valve inplant test (21) control room design review (22) emergency service water system Susquehanna SSER 5

3 DESIGN CRITERIA FOR STRUCTURES,

SYSTEMS, AND COMPONENTS

3. 11 Environmental ual ification 3.11.1.

Environmental gualification of Electrical Equipment Important to Safety Supplement 3 to NUREG-0776 addressed environmental qualification of safety-related electrical equipment, and Supplement 4 to NUREG-0776 addressed all outstanding issues that had to be resolved before removing the 5X of full-power restriction from the Unit 1 license.

In summary, all environmental qualification evaluations needed to permit opera-tion of Unit 1 have been completed and the issues have been resolved either by full quali.fication or justification for interim operation reflected in a license condition for that unit.

While much of the evaluation done for Unit 1 will b'e fully applicable to Unit 2, the applicant has been requested to submit-environmental qualification information for all safety-related electrical equip-ment located in a harsh environment for Unit 2.

In this submittal the applicant shall identify all the differences between Units 1 and 2 in relation to equip-

ment, systems, environment, and qualification status and shall submit the com-ponent evaluation worksheets for all the equipment that is unique to Unit 2.

Also, in order to comply with 10 CFR 50.49, the following information is re-quired to be submitted by the applicant before an operating license is granted for Susquehanna Unit 2.

(1).In accordance with the scope defined in 10 CFR 50.49, provide A list of all nonsafety-related electrical equipment, located in a harsh environment, whose failure under postulated environmental con-ditions could prevent satisfactory accomplishment of safety functions by the safety-related equipment.

A description of the methods used to identify this equipment also must be included.

The nonsafety-related equipment identified must be included in the environmental qualification program.

(b)

A statement that all safety-related electrical equipment in a harsh environment, as defined in the scope of 10 CFR 50.49, is included in the list of equipment identified in the submittal.

(c)

A list of all postaccident monitoring equipment that is currently installed or that wil'1 be installed before plant operation and that are relied on to provide measurements and indications of the variables listed in Revision 2 of Regulatory Guide (RG) 1.97.

The equipment identified must be included in the environmental qualification program.

When the requested information is submitted for Unit 2; the staff will review the submittal to determine qualification of electrical equipment important to safety and will report its findings in a future supplement to the SER.

Susquehanna SSER 5

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5 REACTOR COOLANT PRESSURE BOUNDARY 5.2 Inte rit of the Reactor Coolant Pressure Boundar 5.2.4 Reactor Coolant Pressure Boundary Inservice Inspection and Testing The staff has previously completed the review 'of the preservice inspection (PSI) program and requests for relief from certain impractical American Society of Mechanical Engineers, "Boiler and Pressure Vessel Code" (ASME Code) examination requirements for Susquehanna Unit 1 in Section 5.2.4 and Appendix K of Supple-ment 4 to the SER.

A PSI program and the initial inservice inspection (ISI) program for Unit 2 has not been submitted by the applicant.

To complete its review of the PSI program for Unit 2, the staff will require, before licensing Unit 2, that the applicant provide the following information:

(1) a comparison of the similarities and differences in the PSI programs for Units. 1 and 2

(2) a description of all plant-specific ASME Code requirements that have been determined to be impractical and a supporting technical justification The staff will report its conclusions regarding the above PSI information in a future supplement to the SER.

The staff will complete a postlicensing evaluation of the ISI program after the applicable ASME Code Edition and Addenda can be determined based on Sec-tion 50.55a(b) of 10 CFR 50, The Unit 2 license will be conditioned to require an approved ISI program before the first refueling outage when inservice in-spections will be performed.

5.3 Reactor Vessel 5'. 1 Reactor Vessel Materials In its input to the Susquehanna SER, the staff identified areas for which the applicant had not submitted sufficient information to determine compliance with Appendices G and H to 10 CFR 50.

As a result of information supplied by the applicant for Susquehanna Unit 1, the staff was able to complete its review of that unit.

The staff will complete its evaluation of the Unit 2 compliance with Appendices G and H to 10 CFR 50 when the applicant submits the informa-tion requested by the staff in the SER.

This matter must be resolved before licensing Unit 2.

5.3.2 Pressure-Temperature Limits The applicant is expected to submit the required information that was identi-fied in SER Section 5.3. 1 by May 1, 1983.

The staff will require that the adequacy of the proposed pressure-temperature limits for Susquehanna Unit 2 be resolved before licensing Unit 2 ~

Susquehanna SSER 5

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5.3.3 Reactor Vessel Integrity The applicant is expected to submit the required information that was identified in SER Section 5.3. 1 by Hay 1, 1983.

The staff will require that the adequacy of the Susquehanna Unit 2 reactor vessel integrity be resolved before licensing Unit 2.

The staff will report its conclusions, once the above information is received and evaluated, in a future supplement to the SER.

Susquehanna SSER 5

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6 ENGINEERED SAFElY FEATURES 6.6 Inservice Ins ection of Class 2 and 3

Com onents The staff completed the review of the preservice inspection (PSI). program and requests for relief from certain impractical ASME Code examination requirements for Susquehanna Unit 1 in Section 6.6 of Appendix H of Supplement 3 to the SER.

A PSI program and the initial ISI program for Unit 2 has not been submitted by the applicant.

To complete its review of the PSI program for Unit 2, the staff will require, before licensing Unit 2, that the applicant provide the following information:

(1) a comparison of the similarities and differences in the PSI program for Units 1 and 2

(2) a description of all plant-specific ASME Code requirements that have been determined to be impractical and a supporting technical justification The staff will report the conclusions regarding the above PSI information in a future supplement to the SER.

The staff will complete a postlicensing evaluation of the ISI program after the applicable ASME Code Edition and Addenda can be determined based on Sec-tion 50.55a(b) of 10 CFR 50.

The Unit 2 license will be conditioned to require an approved ISI program before the first refueling outage when inservice in-spections will be performed.

Susquehanna SSER 5

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13 CONDUCT OF OPERATIONS 13.6 Industrial Securit The applicant has submitted security plans applicable to Units 1 and 2 entitled "Susquehanna Steam Electric Station Physical Security Plan" and "Susquehanna Steam Electric Station Security Training and gualification Plan" for protection against radiological sabotage.

The contingency plan is incorporated as Chap-ter ll in the Susquehanna Steam Electric Station Security Plan.

The plans were reviewed in accordance with the guidance of Section 13.6 "Physical Security" of the July 1981 Edition of the "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants" (NUREG-0800).

As a result of the staff's evaluation, certain portions of the plans were identified as requiring additional information and upgrading to satisfy the requirements of Section 73.55 and Appendices B and C of 10 CFR 73.

The applicant filed revisions to these plans to satisfy these requirements.

The staff concludes that these plans, as revised now comply with the Commis-sion's regulations contained in 10 CFR 50 and 73 for both Units 1 and 2.

The identification of vital areas and measures used to control access to these

areas, as described in the plan, may be subject to amendments in the future.

The applicant's security plans are being protected from unauthorized disclosure in accordance with 10 CFR 73.21.

Susquehanna SSER 5

22 TMI-2 RE(UIREMENTS 22.2 TMI Action Plan Re uirements for A licants for 0 eratin Licenses II Sitin and Desi n

II.F. 1 Additional Accident-Monitorin Instrumentation NUREG-0737, Items II.F. 1-1 and II.F.1-2 The staff has conducted a generic design review of effluent monitoring instru-mentation and sample collection systems being provided by various manufacturers to meet the requirements set forth in Items II.F.l-l and II.F.1-2 of NUREG-0737.

The staff's generic review included a review of the primary calibration pro-cedures used by the manufacturers and of the secondary calibration procedures recommended by the manufacturers for subsequent in situ use by licensees and applicants.

On the basis of this review, the staff identified certain specific systems that have been determined to meet the design criteria of NUREG-0737 and that when installed, calibrated, and operated in accordance with the manufac-turers'nstructions, are considered by the staff to meet the intent and pur-pose of NUREG-0737.

In a supplement to the FSAR, the applicant has identified his monitoring system as a fixed airborne activity monitor (FAAM).

The system is designated by the manufacturer (Eberline Instrument Corporation, Santa Fe, New Mexico) as a Model

.SPING-3 air monitor, modified by addition of an optional Model SA-9 high-range noble gas detector.

The design of the Eberline SPING-3, together with the SA-9 high-range option, has been reviewed by the staff on a generic basis and has been determined to be acceptable for the purpose of meeting the design criteria set forth in Items II.F.1-1 and II.F.1-2 of NUREG-0737.

Confirmation of the installation, in-place calibration, and operation of the effluent monitoring system described above will be made for Unit 2 by the staff.

Susquehanna SSER 5

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APPENDIX A CHRONOLOGY OF NRC STAFF RADIOLOGICAL REVIEM OF SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 and 2

Appendix A in the Safety Evaluation Report and Supplements 1, 2, 3, and 4 provided a chronology of the NRC staff's radiological safety review of the application for the period from April 10, 1978 to November 8, 1982; the purpose of this appendix is to update that chronology through November 9, 1982 Letter from applicant concerning nomination of historic places.

November 9, 1982 Letter from applicant concerning structural dynamic models.

November 10, 1982 November ll, 1982 November 12, 1982 November 12, 1982 December 1, 1982 Letter from applicant concerning nonconformance with NUREG-0737, Item II.E.4.2.

Letter from applicant concerning proposed Amendment 14,to License NPF-14.

Letter to applicant transmitting 20 copies of Supplement No.

4 to the Susquehanna Steam Electric Station Safety Evaluation Report (NUREG-0776, Supplement No. 4).

Letter to applicant transmitting Amendment No.

5 to Facility Operating License NPF-14.

Amendment No.

5 authorizes operation at 100K power (3,293 megawatts thermal).

Letter from applicant concerning emergency service water system modification.

December 7, 1982 Letter from applicant concerning Phase III anchors.

December 7, 1982 December 9, 1982 December 10, 1982 December 13, 1982 Letter from applicant concerning schedule for correcting nonconformance with NUREG-0737, Item II.E.4. 2.

Letter to applicant concerning the physical security plan.

Letter from applicant concerning the proposed Amendment 15 to License NPF-14.

Letter from applicant concerning environmental qualification " SPOTMOS RTDs.

Susquehanna SSER 5

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December 16, 1982 December 16, 1982 Letter to applicant concerning proposed amendment to License NPF-14 on physical security and security training and qualification plan.

Letter to applicant transmitting Amendment No.

6 to Facility Operating License NPF-14 changes to various surveillance requirements and corrections to typographical errors.

December 17, 1982 December 21, 1982 Letter from appl icant concerni ng Unit 2 Sei smi c gualification Review Team (SgRT) and Environmental gualification Audit.

Letter from applicant concerning License Condition 2.C.(13).

December 22, 1982 December 23, 1982 December 28, 1982 December 28, 1982 Letter from applicant concerning hydrodynamic loads on CRD piping.

Letter from applicant concerning License Condition 16, wetwell to drywell vacuum breakers.

Letter from applicant concerning seismic qualification of NSIV actuator License Condition 2.C.(23)(c).

Letter (Generic Letter No. 82-30) to applicant concerning filing relating to 10 CFR 50 production and utilization facilities.

December 29, 1982 December 29, 1982 December 29, 1982 January 7,

1983 January ll, 1983 January ll, 1983 January ll, 1983 January 24, 1983 Letter to applicant concerning License Condition 2.C.(13),

nearby faci 1 ities.

Letter from applicant concerning License Condition 2.C.(19),

hanger reconciliation.

Letter from applicant concerning emergency support facilities - interim emergency relocation centers.

Letter from applicant concerning diesel generator start time.

Letter from applicant concerning additional information in support of proposed Amendment ll to License NPF"14.

L'etter from applicant concerning safeguards information

program, Letter from applicant concerning photographs - historic places.

Letter from applicant conerning response to comments on physical security plan changes.

Susquehanna SSER 5

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January 25 - 27, 1983 January 26, 1983 Representatives from NRC 8

PP8L meet at the Training Center, Luzerne County, Pennsylvania to discuss inservice inspec-tions (pumps.and valves).

Letter from applicant concerning proposed Amendment 17 to License NPF-14.

January 31, 1983 January 31, 1983 Letter from applicant conerning proposed Amendment 18 to License NPF"14.

Letter to applicant transmitting Amendment 7 to Facility Operating License NPF-14 to revise Technical Specifications to be consistent with the intent of NUREG-0313.

February 7, 1983 February 7, 1983 Letter to applicant transmitting Amendment 8 to Facility Operating License NPF-14 making correctios to Technical Specifications

4. 6. l. 2. h; 3. 8. 3.1; and 4. 11. 2.7.1.

Letter to applicant transmitting Amendment 9 to License NPF-14 allowing a total of 25 operational'ycles on the recirculation discharge valve assemblies without the motor brake.

February 7, 1983 Letter to applicant concerning storage of safeguards information.

February 10, 1983 Letter to applicant transmitting Amendment 10 to License NPF-14 to add Fire Zone 1-2B and delete Fire Zone 1-6A from Technical Specification 3.7.6.2 listing areas where spray and sprinkler systems shall be operable.

February ll, 1983 Letter from applicant concerning sercurity training and qualification plan.

Susquehanna SSER 5

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APPENDIX B BIBLIOGRAPHY Code of Federal Re ulations, Title 10, "Energy," U.S.

Government Printing 0

sce, Washington, D.C.

U.S. Nuclear Regulatory Commission, NUREG-073?, "Clarification of TMI Action Plan Requirements,"

Nov.

1980.

---, NUREG-0776, "Safety Evaluation Report Related to the Operation of Susque-hanna Steam Electric Station, Units, 1 and 2," Apr. 1981; Supplement No. 3, July 1982; and Supplement No. 4, Nov. 1982.

---, NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," July 1981.

RG 1.97, Instrumentation tor Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs During and Following an Accident," Rev. 2, Dec.

1980.

RG 1, 101, "Emergency Planning and Preparedness for Nuclear Power Reactors,"

Rev.

2, Oct.

1981.

U.S. Nuclear Regulatory Commission, Office of Inspection and Enforcement (IE)

Bulletin 79-27, "Loss of Non-Class IE Instrumentation and Control Power System Bus During Operation," Oct.

25, 1979.

Industry Codes and Standards American Society of Mechanical Engineers, "Boiler and Pressure Vessel Code" (ASME Code),Section III, NB-3113(b).

Susquehanna SSER 5

B-l

APPENDIX F CONTROL ROOM DESIGN REVIEM, SUSQUEHANNA UNITS 1 AND 2 DISCUSSION The applicant's preliminary design assessment (PDA) and the staff's control room design review/audit of the Susquehanna Steam Electric Station Unit 1 con-trol room identified 42 human engineering discrepancies (HEDs) which required correction before licensing.

On July 17, 1982, Unit 1 received a license for low-power operation on the basis of the applicant's correction of a large majority of those HEDs.

Correction of'he remaining HEDs was completed, per license condition, by September 1,

1982 (see Inspection Report 82-33).

Supplement 3 to the SER noted that the Susquehanna Unit 2 control room must be subjected to either a

PDA or a detailed control room design review before licensing of that Unit.

To satisfy this requirement, the applicant has verb-ally committed to incorporate all HED corrections applied to the Unit 1 control room into the design for the Unit 2 control room.

The applicant should provide a written commitment to this effect.

In addition, if the applicant expects licensing of Unit 2 to be based on the PDA for Unit 1, any differences between the two control rooms must be determined and addressed in a supplement to the Unit 1 PDA.

Corrections of HEDs in the Unit 2 control room should be completed before licensing.

In addition, the applicant should submit a report addressing all HEDs at least 6 months before licensing to ensure timely closeout of the pre-licensing control room design review.

The report should list proposed correc-tive actions for the HEDs, implementatio'n schedules, and any deviations from previous commitments.

Justifications for deviations from previous commitments also should be provided.

Conclusion A formal commitment as to the manner for completing the prelicensing control room design review for Unit 2 should be submitted.

Given that commitment, the applicant should plan to have corrections to HEDs implemented before licensing.

A report listing HEDs, proposed corrective actions, and implementation schedules must be provided at least 6 months before licensing along with descriptions of any deviations from previous commitments and justifications for those deviations.

Susquehanna SSER 5

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NRC FORM 335 17 771 U.S. NUCLEAR REGULATORY COMMISSION BIBLIOGRAPHICDATA SHEET

4. TITLE ANO SUBTITLE JAdd Volume Na,ifepproprieseJ Safety Evaluation Report related to the operation of Susquehanna Steam Electric Station, Units I and 2

1. REPORT NUMBER JAssiflned by DDCJ NUREG-0776 Supplement No.

5

2. JLeeee blenk J

3. RECIPIENT'6 ACCESSION NO.

7. AUTHOR ISl

5. DATE REPORI'OMFIT LEI)

9. PERFORMING ORGANIZATION NAME ANO MAILINGADDRESS llnclude Zip Codei Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 MONTH a ch DATE REPORT ISSUED MONTH March

6. JLeeee bfsnkJ B. JLseee blenkJ YEAR 1983 YEAR 1983 12; SPONSORING ORGANIZATIONNAME ANO MAII.INGADDRESS Jlnclude Zip CodeJ Same as 9 above

10. PROJECTITASKIWORK UNITNo.

11. CONTRACT No.

13. TYPE OF REPORT Safety Evaluation Report - Technical.

15. SUPPLEMENTARY NOTES D cket Nos.

50-387 and 50-388 PERIOD COVE RED llnclusree desesJ November 1982 - March 1983

14. ILeeee blank J

16. ABSTRACT J200 words or lessJ In April 1981; the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0776) regarding the application of the Pennsylvania Power and

.L'ight Company (the applicant and/or licensee) and the Allegheny'lectric Cooperative, Inc.

(co-applicant) for licenses to operate the Susquehanna Steam Electric Station, Units 1

and 2, located on.a site in Luzerne County, Pennsylvania.

Supplement 1 to NUREG-0776 was issued in June 1981 and addressed several outstanding issues.

Supplement 2 was issued in September 1981 and addressed additional outstanding issues.

Supplement 2 also contains NRS staff responses to the comments made by the Advisory Committee on Reactor 'Safeguards in its report dated August 11, 1981.

Supplement 3 was issued in July 1982 and addressed five items that remained open and closed them out.

On July 17, 1982, Operating L'icense NPF-14 was issued to allow Unit 1 operation at power levels not to exceed 5K of rated

power, Supplement 4 was issued November 1982 and discusses the resolution of several license conditions.

On November 12, 1982, Operating License NPF-14 was amended to remove the 5$ power restriction, therety permitting full-power operation of Unit l.

~

This supplement, No. 5, addresses several issues that require resolution before licensing operation of Unit 2.

\\7, KEY WORDS AND DOCUMENT ANALYSIS 17k. OESCRIPTORS 17b. IDENTIFIERSIOPEN ENDED TERMS

16. AVAILABILITYSTATEMENT

19. SECURITY CLASS Jfhis reporrl 21 NO. OF PAGiES VAC FQAM".l'Ir S7 771 Unl imited

20. SECURITY CLASS IThis peeeJ Unclassified

22. PRICE S