ML17139C283

License NPF-22 for Facility

ML17139C283
Person / Time
Site:	Susquehanna
Issue date:	03/23/1984
From:	Harold Denton Office of Nuclear Reactor Regulation
To:
Shared Package
ML17139C284	List: ML17139C283 ML17139C285 NUREG-1042, Environ Protection Plan (Nonradiological).Tech Specs (NUREG-1042) Encl
References
NUDOCS 8404060380
Download: ML17139C283 (14)

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t UNITED STATES 1

NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 PENNSYLVANIA POWER 8

LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-388 SUSOUEHANNA STEAM ELECTRIC STATION UIIIT 2 FACILITY OPERATING LICENSE License No.

NPF-22 1.

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

A.

The application for a license filed by the Pennsylvania Power II Light Company and the Alleghany.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, and all required notifications to other agencies or bodies have been duly made; B.

Construction of the Susquehanna Steam Electric Station, Unit 2 (the facility), has been substantially completed in conformity with Con-struction Permit No.

CPPR-,102 and the application, as

amended, the provisions of the Act, and the regulations of the Commission; C.

The facility will operate in conformity with the application, as

amended, the provisions of the Act, and the regulations of the Commission; E.

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; The Pennsylvania Power 8 Light Company* is technically qualified to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter I;

• The Pennsylvania Power 5 Light Company is authorized to act as agent for the Alleghany Electric Cooperative, Inc.

and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

8404060380 840323 PDR ADOCK 05000388 P

PDR 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 common defense and security or to the health and safety of the public; H.

After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. NPF-22 subject to the condition for protection of the environment set forth herein, is in accordance with 10 CFR Part 51 of the Commission'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 Commission's regulations in 10 CFR Parts 30, 40 and 70.

2.

Based on the foregoing findings regarding this facility, Facility Operating License No. NPF-22 is hereby issued to the Pennsylvania Power

& Light Company and the Allegheny Electric Cooperative, Inc. to read as follows:

A.

This license applies to the Susquehanna Steam Electric Station, Unit 2, a boiling water nuclear reactor and associated equipment (the facility),

owned by the licensees.

The facility is located in Luzerne County, Pennsylvania, and is described in the licensees Final Safety Analysis

Report, as supplemented and

amended, and the licensees'nvironmental Report,'s supplemented and amended.

B.

Subject to the conditions and requirements incorporated

herein, the Commission he'reby licenses:

(I)

Pursuant to Section 103 of the Act and 10 CFR Part 50, "Oomestic Licensing of Production and Utilization Facilities", Pennsylvania Power

& Light Company (PP&L) and the Allegheny Electric Cooper-ative, Inc. to possess, and PP&L to use, and operate the facility at the designated location in Luzerne County, Pennsylvania,

.in accordance with the procedures and limitation set forth in this license; (2)

PP&L, 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;

V (3)

PP8L, pursuant to the Act and 10 CFR Pa~ts 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 neutron sources for reactor instrumentation and radiation monitoring equipment calibration,

.and as fission detectors in amounts as required; (4)

PPSL, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to

receive, possess, and use in amounts as required any byproduct, source or special nuclear mater,ial without restriction to chemical or physical form, for samp'le analysis or instrument calibration or associated with radioactive apparatus or components; and (5)

PP8L, pursuant to the Act and,10 CFR Parts 30, 40, and 70, to

possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation 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.) l'1aximum Power Level Pennsylvania Power 8 Light Company (PPINL) is authorized to operate the facility at reactor core power levels not in excess of 3293 mega-watts thermal (100% power) 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.

Pending Commission.approval, this license is re-stricted to power levels not to exceed five percent of full power (164.6 megawatts thermal ).

(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix 8, both of which are attached

hereto, are hereby incorporated in this license.

PPIIL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Fire Protection Proqram Section 9.5,

SER, SSER Pl, SSER 82, SSER b'3)

PPEL shall maintain in effect and fully implement all provisions of the approved fire protection program.

(4) 0 eration with Partial Feedwater Heatinq at End-of-Cycle (Section 15.1

SER, SER 1

PPSL shall not operate with partial feedwater heating for the purpose of extending the no~mal fuel cycle unless acceptable justification is provided to and approved by the HRC staff prior to such operation.

(5) Initial Test Proqram (Section 14,

SER, SSER F1 PP8L shall conduct the post-fuel-loading initial test program described in Section 14 of the Final Safety Analysis Report, as amended without making any major modifications unless such modifications have, prior HRC approval.

major modifications are defined as:

(a)

Elimination of any safety-related test*;

(b)

Modifications of objectives, test methods or acceptance criteria for any safety-related test; (c)

Performance of any safety-related test at a power 1'evel different from that stated in the licensees'inal Safety Analysis Report by more than 5 percent of rated power; (d)

Failure to satisfactorily complete the entire initial startup test program by the time core burnup equals 120 effective full power days; (e)

Deviation from initial test program adminstrative procedures or quality assurance controls described in the licensees'inal Safety Analysis Report; and (g)

Delays in the test program in excess of 30 days.(14 days if power levels exceeds 50 percent) concurrent with power operation.

If continued power operation is desired during a delay, the licensees shall provide justification that adequate testing has been per-formed and evaluated to demonstrate that the facility can be operated at the planned power level with reasonable assurance that the health and safety of the public will not be endangered.

• Safety-related tests are those test which verify the design, construction, and operation of safety-related

systems, structures, and equipment..

(6) Inservice Ins ection Pro ram (Section 5.2.4 and 6.6,

SER, SSEP, F1, SSER e3 By March 1, 1985, PP&L shall submit a revised inservice inspection program for NRC review and approval.

(7) Environmental Oualification (Section 3.11,

SER, SSER 81, SSER ~2, S

v3 S

R SS 0

S R

Prior to March 31,

1985, PP&L shall environmentally qualify all electrical equipment according to the provisions of 10 CFR 50.49.

(8) Seismic and Dynamic Qualification (Section 3.10,

SER, SSER 81 SR 3,

SRF" SR 5,S R

(a)

Prior to exceeding five percent of rated

power, PP&L shall complete qualification and documentation, as well as installation for:

(1)

RCIC backup power supply and inverter (2)

A/E-added devices to NSSS panels (b)

Prior to the first refueling outage, PP&L shall complete qualification and documentation, as well as installation for the in-vessel rack.

(9) Surveillance of Control Blade (Section 4.2.3, SER)

Within 30 days after plant startup following the first refueling

outage, PP&L shall comply with Items 1, 2, and 3 of IE Bulletin No. 79-26, Revision I, "Boron Loss from BWR Control Blades",

and submit a written response on Item 3.

(10) Additional Instrumentation and Control Concerns (Section 7.7.2,'SER, SS R P2; Section 3.11.3, SSER 6

Prior to exceeding five percent of rated

power, PP&L shall resolve the following concerns to the NRC's satisfaction:

(a) whether common electrical power sources or sensor malfunctions may cause multiple control systems failures, and (b) whether high energy line breaks will result in unacceptable co'nsequential control system failures.

(11) Emerqenc Diesel Engine Startina S stems (Section 9.6.3, SER)

Prior to September 1, 1985, PP&L shall install air dryers up-stream of the air receivers.

('12)

NUREG-0737 Conditions Section 22, SER)

PP&L shall complete the following conditions to the satisfaction of the NRC.

These conditions reference the appropriate items in Section 22.2, "TMI Action Plan Requirements for Applicants for Operating Licenses,"

in the Safety Evaluation Report and Supple-ments I, 2, 3, 4, 5, and 6, NUREG-0776.

(a)

Nuclear Steam Su 1

S stem Vendor Review of Procedures 1...

ER, R

1 Prior to achieving initial criticality, PP&L shall assure that the General Electric review of the power ascension test pro-cedures has been completed.

(b)

Detailed Control Room Desi n Review I.D.1, SSER P6)

All human engineering deficiencies requiring correction as a

result of PP&L's Detailed Control Room Design Review for Unit I shall be corrected in the Unit 2 control room.

By March I, 1985, PP&L should submit its schedule for implementing all human engineering deficiency corrective action for review and approval by NRC staff.

(c)

Post Accident Sam lin (II.B.3, SER SSER Pl, SSER 83)

(1)

Prior to exceeding five percent of rated power, PP&L shall have installed and have operational the Post-Accident Sampling System.

(2)

Prior to December I, 1984, PP&L shall revise the interim core damage estimating procedure by submitting for staff review a final procedure which incorporates hydrogen levels, reactor vessel coolant level and containment radiation levels in addition to radionuclide data.

(d)

Emer enc Res onse Ca abilities (Generic Lette~ 82-33, Su lement 1

to

<UREG-0 3 PP&L shall complete emergency response facilities and capabilities as required in Attachment 2 of'his license.

(e)

Instrumentation for Detection of Inade uate Core Coolina II F SER SSER zrl SSER z'3 SSER 6

PP&L shall implement the staff's requirements regarding upgrad-ing of liquid level instrumentation or inclusion of additional instrumentation for detection of inadequate core cooling necessary to c'omply with Commission regulations, based on the staff's review of the BWR Owner's Group Reports (SLI 8211

& SLI 8218) and PP&L's plant specific evaluation report addressing the recommendations of the BWROG reports.

Within 90 days after PP&L is informed of staff requirements, PP&L shall submit for review and approval by the staff, a schedule for implementing any required modifications regarding upgrading of liquid level instrumentation or inclusion of additional instrumentation for detection of inadequate core cooling.

(f)

Modification of Automatic De ressurization S stem Lo ic-Feasibilit for ncrease Dsversit for Some vent Se uences

.1 SSER kl, SSER

$2, SSER z3, SSER Fr6 (1)

Prior to achieving, initial criticality, PP&L shall:

(i)

Install modifications to the Automatic Depressurization System acceptable to the NRC, and (ii)

Propose Technical Specifications for the bypass timer setting and surveillance requirements for the bypass timer.

(2)

Prior to September 1, 1985, PP&L shall:

(i)

Incorporate into the Plant Emergency Procedures the usage of the manual inhibit switch, and (ii)

Propose Technical Specifications for the manual inhibit switch (3)

PP&L shall maintain the manual inhibit switch disabled until license condition Z.C.(12)(f)(2) above is satisfied.

(13)

Emerqency Service Water S stem (Section 9.2.1, SSER, b6)

Prior to September 1, 1985, PP&L shall complete modifications to. the emergency service water (ESW) system described in PP&L letter dated Hay 16, 1983.

(14) Control of Heav Loads (Section 9.1.4, SSER ¹6)

Prior to startup following the first refueling outage, PP8L shall submit commitments necessary to implement changes in modifications required 'to fully satisfy the guidelines of Sections 5.1.2 through 5.1.6 of NUREG-0612 (Phase II - nine month responses to the NRC generic lette~ dated December 22, 1980).

(15)

Radon (ASLB Initial Decision, Paraqra h 223)

This license will be subject to the ultimate outcome of the con-solidated radon proceeding currently underway in Docket Nos. 50-277, 50-278, 50-320, 50-354 and 50-355.

(16) Formal Federal Emerqenc Management A enc Findin In the event the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a maior sub-stantial problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54 (s)(2) will apply.

D.

PPSL shall fully implement and maintain in effect all provisions of the Com-mission approved physical security, guard training and qualification, and safeguards contingency plans, including amendments made pursuant to the authority of 10 CFR 50.54(p).

The approved

plans, which contain Safeguards'nformation as described in 10 CFR 73.21, are collectively entitled:

"Susquehanna Steam Electric Station Physical Security Plan",

Change A, dated July 31, 1978 (transmittal letter dated July 31, 1978);

Change B, dated February 15, 1979 (transmittal letter dated February 15, 1979);

Change C, dated August 15, 1979 (transmittal letter dated August 23, 1979);

Change D, dated September 28, 1979 (transmittal letter dated October 8, 1979);

Change E, dated Hay 22, 1980 (transmittal letter dated July ll, 1980);

Change F, dated March 27, 1981 (transmittal letter dated April 8, 1981);

Change G,

(Safeguards Contingency Plan Chapter

11) dated Hay 29, 1981 (trans-mittal letter dated June 5, 1981);

Change H, (Safeguards Contingencv Plan Chapter 11), dated June 26, 1981 (transmittal lette~ dated

June 29, 1981),

Change I, dated March 19, 1982 (transmittal letter dated March 26, 1981),

Change J, dated April 1, 1982 (transmittal letter dated April 23, 1982);

Change K, dated May 4, 1982 (trans-mittal letter dated May 5, 1982);

Change L, dated July 9, 1982 (transmittal letter dated July 13, 1982);

Change M, dated October 15, 1981 (transmittal letter dated October 25, 1982);

Change N, dated April 25, 1983 (transmittal letter dated May 6, 1983);

Change 0, dated June 15, 1983 (transmittal letter dated June 16, 1983);

Change P, dated June 27, 1983 (transmittal letter dated July 17, 1983);

and "Susquehanna Security Training and gualification Plan",

Change A, dated August 26, 1981 (transmittal letter dated September 1, 1981);

Change B, dated February 3, 1983 (transmittal letter dated February 11, 1983).

E.

Reporting to the Commission:

PPSL shall report any violations of the requirements contained in Section 2, Items C(1), C(3) through C(16) of this license within twenty-four (24) hours.

Initial notification shall be made.in accordance with the provisions of 10 CFR 50.72 with written followup in accordance with the procedures described in 10 CFR 50.73 (b), (c), and (e).

F.

PPSL shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as

amended, to cover public liability claims.

G.

This license is effective as of the date of issuance and shall expire at midnight on March 23, 2024.

FOR THE NUCLEAR REGULATORY COMMISSION I

DaaRGU, 8 Qasceg C c 8 Harold R. Denton, Director Office of Nuclear Reactor Regulation Attachments:

1.

Attachment 1

2.

Attachment 2

3.

Appendix A - Technical Specifications (NUREG-1042) 4.

Appendix B - Environmental Protection Plan Date of Issuance:

MAR ~ ~ l~~"

• See previous page for concurrences Retyped kab (3/21/84)

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• MWagner + DEisenhut >HDenton 03/19/84 03/g +84 03/P3/84

li

ATTACHMENT 1 1.

Outstandinq Items to be Accom lished Prior to Initial Criticalit a ~

b.

c ~

d.

e.

h; Complete permanent modification to correct the deficiency involving the isolation of the Nitrogen Makeup System.

(Construction Deficiency Report 83-00-15)

Complete system modifications to ensure elect~ical separation for safety-related circuits.

(Construction Deficiency Report 81-00-10)

Verify that waterhammer loads due to scram discharge volume vent and drain valve operation on scram'reset do not affect system integrity.

(Construction Deficiency Report 83-00-07)

Verify that system piping, for which improper design input was included in the piping specification, are qualified for the proper design stresses.

(Construction Deficiency Report 83-00-17)

Verify that signal isolation devices installed in Class 1E circuits pro-vide adequate electrical separation/isolation between Class-1E and Non lE circuits'.

(Construction Deficiency Report 84-00-01)

Upon issue of the Operating License Technical Specifications, verify that specified conditions, setpoints, and action points in facility procedures are consistent with those Technical Specifications.

Verify electrical separation criteria is met inside multiple division pull boxes and junction boxes.

(Construction Deficiency Report 83-00-14)

Complete modification to CRD insert/withdrawal line supports to ensure the system is qualified for design stresses.

(Construction Deficiency Report 83-00-20) 2.

Outstandinq Item to be Com leted Prior to Exceedin 5X Power a

~

b.

Submit technical specification change requests for both units to reflect bypass leakage limits on the feedwater lines and to require pneumatic local leak rate tests.

(Construction Deficiency Report 83-00-03)

Verify the installation of additional post-accident monitoring instru-mentation in accordance with NUREG-0737 items II.F.l. 1, II.F.1.2 and II.F.1.3 and FSAR Section

18. 1.30.

3.

Outstanding Items to be Corrected bv the First Refuelin Outa e

a.

Complete corrective action for deficiency involving cavitation caused by throttling valve in the RHR system.

(Construction Deficiency Report 81-00-33) b.

Complete corrective action for deficiency involving capstan springs in Pacific Scientific snubbers.

(Construction Deficiency Report 83-00-18) 4.

Oustandinq Items to be Corrected bv a S ecific Date a ~

Complete correction of the remaining HED deficiencies in the Unit 2 control room documented in Inspection Report 50-388/84-08 by June 1,

1984.

b.

c ~

d.

Complete corrective action for deficiency involving corrosion allowance for the ESM piping to and from the RHR pump motor oil coolers by 1988.

(Construction Deficiency Report 83-00-16)

Submit revisions to the FSAR to correct the discrepancies noted below by July 31, 1984.

'(i)

Delete reliance on the 30 day water seal on feedwater lines in Section 6.2.3 (Construction Deficiency Report 83-00-03).

(ii)

Correct statements concerning sizing of the ADS accumulators in Section 18.1.60,(TMI II.K.3.28).

.(iii) Correct information concerning containment isolation signals in Tables 18.1-10, 18.1-11, 18.1-12 and 6.2-12 (THI II.E.4.2)

(iv)

Correct information concerning performance of the SBGTS in Section 6.2, 6.5, 9.4 and 15.6 (Construction Deficiency 83-00-19).

(v)

Chapter 14 must be updated to correctly reflect the Unit 2 test program (UNR 83-04-01).

Verify that angle fittings used for class lE raceway supports and seismic category 1

HVAC duct supports are capable of supporting their associated design loads by June 1, 1984.

(Construction Deficiency Report 84-00-03) e.

By September 1, '1984, submit to NRC Region I an acceptable long-term solution for spray pond spray network freezing.

(Unresolved Item 83-32-02)

Complete corrective action for deficiency involving Emergency Service plater system water hammer by September 1,

1985.

(Construction Deficiency Report 82-00-06)

ATTACHMENT 2 PP&L shall implement the specific items below, in the manner described in PP&L letter (PLA-1621) dated April 15, 1983, as modified by PP&L letter (PLA-1750) dated July 22,

1983, PP&L letter (PLA-1772) dated August 3, 1983, PP&L letter (PLA-1966) dated November 23,

1983, PP&L letter (PLA-2059) dated February 1, 1984, and PP&L letter (PLA-2131) dated March 14, 1984 no later than the following specified dates:

(a) Safety Parameter Display System (SPDS)

,. SPDS fully operational and operators trained (b) Detailed Control Room Design Review (DCRDR)

Submit a supplemental summary report to the NRC including a proposed schedule f'r implementation.

(c) Regulatory Guide 1.97 - Application to Emergency

Response

Facilities (1) Submit a report to the NRC describing how the requirements of Supplement 1 to NUREG-0737 have been or will be met.

(2) Implement (installation or upgrade) requirements of R.

G. 1.97 or provide justification acceptable to the NRC staff for suppression pool water temperature, drywell atmosphere temperature, neutron flux, primary containment isolation valve position, radiation level in circ'ulating primary coolant, radiation exposure rate, and noble gas and vent rate.

(d) Upgrade Emergency'perating Procedures (1) Submit a Procedures Generation Package to the NRC (2) Implement the upgraded EOP's (e)

Emergency

Response

Facilities

( 1) Technical Support Center fully functional (2) Operational Support Center fully functional (3) Emergency Operations Facility fully functional

, July 1, 1984 March 1, 1985 May 1984 June 1987 June 1985 December

-1985 June 1987 June 1987 June 1987