ML20099M274

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License NPF-32 for Facility
ML20099M274
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 03/11/1985
From: Harold Denton
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20099L140 List:
References
NUDOCS 8503250139
Download: ML20099M274 (12)
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UNITED STATES

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- NUCLEAR REGULATORY COMMISSION 4:

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. KANSAS GAS AND ELECTRIC COMPANY

~ KANSAS CITY POWER A LIGHT COMPANY U

KANSAS ELECTRIC POWER COOPERATIVE, INC.

. DOCKET NO. STN 50-482 t

WOLF CREEK GENERATING STATION, UNIT NO. 1 FACILITY OPERATING LICENSE License No. NPF-3?

1.

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

A.

The application for license filed by Kansas Gas and Electric Company, Kansas City Power & Light' Company, and Kansas Electric Power Cooper-tive,

Inc. (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 notifica-tions to other agencies or bodies have been duly made; B.

Construction of the Wolf Creek Generating Station, Unit No.1 (the facility) has been substantially completed in conformity with Con-

-struction Permit No. CPPR-147 and the application, as amended ~, the provisions of the Act, and'the' regulations of the Commission; i

C.

The facility will operite in conformity with the application. as L

amended, the provisions of the Act, and the regulations of the Com-mission, (except as exempted from compliance in Section 2.D below);

D.

There is reasonable assurance:! (i)thattheactivitiesauthorized i

by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will ith the Comission's regulations set be conducted in compliance w(except as exempted from compliance in forth in 10 CFR Chapter I, Section2Dbelow);

l E.

Kansas Gas and Electric Company

  • is technically qualified to engage in the activities authorized by this license in accordance with the Commission's regulations set.forth in 10 CFR Chapter I; l

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  • Kansas Gas and Electric Company is author.ized to act as coent for the Ka'sas n

j City Power & Light Company and the kansas Electric Power Cooperative, Inc.,

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

8503250139 050311 DR ADOCK 0500

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2-F.

The licensees have satisfied the. applicable provisions of 10 CFR Part 140 " Financial Protection Requirements and Indemnity Agreements," of the Comission's regulations; G.

The issuance of this license will not be inimical to the comon defense and security or to the health and safety o# the public; H.

After weighing the environmental, economic, technical and other bene-fits of the facility against environmental and other costs and con-sidering available alternatives', the issuance of this Facility Oper-ating License No. NPF-32, 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 Connission's regulations and all applicable requirements have been satisfied; and I.- The receipt, possession, and use of source, byproduct and special nu-clear material as authorized by this license will be in accordance with the Connission's regulations in 10 CFR Parts 30, 40 and 70.

2.

Based.on the foregoing findings regarding this facility, Facility Operating License No. NPF-32 is hereby issued to Kansas Gas and' Electric Company, Kansas City Power & Light Company, and Kansas Electric Power Cooperative, Inc. (the licensees) to read as follows:

A. ' The license applies to the Wolf Creek Generating Station, Unit No.1, a pressurized water nuclear reactor and associated equipment (the fa-cility), owned by Kansas Gas and Electric Company, Kansas City Power

& Light Company, and Kansas Electric Power Cooperative, Inc. The facility is located in Coffey County, Kansas, approximately 28 miles east-southeast.of Emporia, Kansas, 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 Com-mission hereby licenses Kansas Gas and Electric Company (KG&E), Kansas City Power & Light Company (KCPL) and Kansas Electric Power Cooperative, Inc.(KEPCO).

(1)

Pursuant to Section 103 of the Act and 10 CFR Part 50 " Domestic Licensin~g of Production and Utilization Facilities," KG8E, to possess, use and operate the facility at the designated location in Coffey County, Kansas, in accordance with the procedures and limitations set forth in this license; (2)

KCPL and KEPCO to possess the facility at the designated location in Coffey County, Kansas, in,accordance with the procedures and limitations set forth in this license; L

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. y (3)..KG8E, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as readtor 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; i

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(4)

KG&E, 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 radia-tion monitoring equipment calibration, and as fission detectors in amounts as required; (5)

KG&E, pursuant.to the.Act and 10 CFR Parts 30,-40 and 70, to re-ceive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chem-ical.or physical fonn, for sample analysis or instrument cali-bration or associated'with radioactive apparatus or components; and (6).

KG8E, pursuant to the Act and 10 CFR Parts 30, 40 and 7d, t'o 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 Comission'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.Comission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level KG8E is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thennal (100% power) in accordance with the conditions specified herein and in Attach-ment 1 to this license. The preoperational tests, startup tests and other items identified ~in Attachment I to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license. Pending Commission approval, this-license is restricted to power levels not to exceed 5 percent of full power'(170 megawatts thermal);

(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.

KG&E shall operate the facility in accordance with the Technical Specifications 'and the Environmental Protection j

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_(3)' Antitrust' Conditions; l Kansas Gas & Electric Company and Kansas C1ty Power & Light Company shall comply with the antitrust conditions delineated Lin Appendix C to this license.

<(4)

Environmental Oualification (Section 3.11, SSER-#4, Section 3.11, 55ER #5).

All electrical ecuipment within the scope of 10 CFR 50.49'shall

'be~ qualified by_ November 30, 1985.

(5)

Seismic and Dynamic Oualification (Section 3.10, SSER #5)

Prior to exceeding five. percent of rated power, KG&E shall, for that equipment which is not completely qualified, complete such.

qualification or submit justification for safe operation at power levels greater than.five percent.

'(6)-

Fire Protection-(Section 9.5.1, SER, Section 9.5.1.8, SSER #5)

(a) KG&E shall maintain in effect all provisions of the approved fire protection program as described in the SNUPPS Final Safety Analysis Report for the facility through, Revision 17, the. Wolf Creek site addendum through Revision 15, and m

as approved in the SER through Supplement 5, subject to provisions b & c below.

(b) KG&E may make no change to the approved fire protection program which would decrease the level of fire protection in the plant without prior approval of the Commission. To make such a change the licensee must' submit an application for license amendment pursuant to 10 CFR 50.90.

(c) KG8E may make changes to features of the approved fire pro-tection program which do not decrease the level of fire pro-tection without prior Comission approval, provided:

(1)~ such changes do not otherwise involve a change in a license condition or technical specification or result in an unreviewed safety question (see 10 CFR 50.59).

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  • The parenthetical notation following the title of many license conditions

. denotes the section of the Safety Evaluation Report and/or its supplements

_wherein the license condition is discussed.

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5-(ii) such changes do not result in failure-to complete the fire protection program approved by the Commission prior to license issuance.

KG8E shall maintain, in an'auditable form, a current record

.. of all such changes including an analysis of. the effects of

--the change on the fire protection program and shall make such records available to NRC inspectors upon request. All changes to the approved program made without prior Commission approval shall be reported annually to the Director of the Office of Nuclear Reactor. Regulation, together with supporting analyses.

-(7) Qualification of Personnel (Section 13.1.2, SSER #5, Section 18, 55ER #1)

KG&E shall have'on each shift operators who meet the requirements described in Attachment 2.

(8) NUREG-0737 Supplement 1 Conditions (Section 22, SER)

KG8E shall complete the requirements described in Attachment 3 to the satisfaction of the NRC. These conditions reference the appropriate items in Section 22, "TMI Action Plan Requirements for Applicants for Operating Licenses," in the Safety Evaluation Report and. Supplements I, 2, 3,'4, and 5 NUREG-0881.

(9) Post-Fuel-Loading Initial Test Program (Section'14, SE'R Section 14, 55ER #5) 7.

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

(10)

Inservice Inspection Program (Sections 5.2.4 and 6.6, SER)

- Within nine months of the date of this license, KGAE shall submit for staff review and approval, the inservice inspection program

. which conforms to the ASME Code in effect 12 months prior to the date of issuance of this license.

(11) Emergency Planning (a) 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 Part 350, is an indication that a maior substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.

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. ~(b) Prior to exceeding five percent of rated power, letters of agreement shall be signed by _Coffey County with ambulance

' services and with funeral directors in surrounding counties providing for the transportation of non-ambulatory patients from the Coffey County Hospital and from the Golden Age Lodge Nursing Home i.n the event of an emergency evacuatinn occasioned by an accident at the Wolf Creek-Plant. These executed letters of agreement shall be ' submitted to the NRC staff and shall,be, included in the Coffey County Plan.

(12) Steam 4enerator Tube Rupture (Section 15.4.4 SSER 45)

Prior to restart following the first refueling outage, KGAE shall subnf t for NRC. review and approval an analysis which demonstrates

.that the steam-generator single-tube rupture (SGTR) analysis pre-

. sented in the FSAR is the most severe case with respect to the release of fission products and calculated doses. Consistent with the analytical assumptions, the licensee shall prbpose all necessary_ changes to Appendix A to this license.

(13) Low Temperature Overpressure Protection (Section 5, SSER #5)

By June 1, 1985, KG&E shall submit for NRC review and approval a description of equipment modifications to the residual heat removal system (RHRS) suction isolation valves and to closure circuitry which conform to the applicable staff requirements (SRP 5.2.2).

Within one year of receiving NRC approval of the modifications,. KG&E shall have the approved modifications in-stalled. ' Alternately, by June 1, 1985. KG&E shall provide ac-

. ceptable Justification for reliance on administrative means'

.alone to meet the staff's RHRS isolation requirements, or other-wise, propose changes to Appendix A to this license which remove L

reliance on the RHRS as-a means of low temperature-overpressure protection.

j (14) LOCA Reanalysis (Section 15.3.7, SSER #5)

Prior to restart following the first refueling ou'tage, KGAE shall submit for NRC review and approval a reanalysis for the worst large break LOCA using an approved ECCS evaluation model..At this time that model is the 1981 Westinghouse model. A modified version of the 1981 model which includes the BART computer code may be used.

(15) Generic Letter 83-?8 KG8E shall submit responses to and implement the requirements of Generic Letter 83-28 on a schedule which is consistent with that given in their November 15, 1983 February 29, 1984, and February 6,1985 letters.

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(16) Surveillance of Hafnium Centrol Rods (Section 4.2.3.:1(10),SER and 55E_R #2)

KG&E shall ' perform a visual inspection of a sample of. hafnium control rods during one of the first five refueling outages. A

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_ summary of the results of these inspections shall be submitted

.to the NRC.

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r D.. Exemptions from certain requirements of Appendix J to 10 CFR Part 50, sand from a portion of the requirements of, General Design Criterion 4 of Appendix A to 10 CFR Part 50, are described in the Safety Evaluation Report. These exemptions are authorized by law and will not endanger

= life or property or the comon defense and ' security and are otherwise in the-public interest. Therefore, these exemptions are hereby granted pursuant to 10 CFR 50.12. With the granting of these exemptions 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 Comission.

E. _KG8E shall fully implement and maintain in effect all provisions of the Commission approved Physical Security, Guari 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 Information as described in 10 CFR 73.?1 are collectively entitled " Wolf Creek Generating Station, Physical Security Plan Revi-sion 0, transmitted by letter dated February 8, 1980, Revision 1, trans-mitted by letter dated September 8, 1981, Revision 2, transmitted by letters dated March 31, 1982 and April 30, 1982, Revision 3, transmitted by letter ~ dated May 8,1984, Revision 4, transmitted by letter dated August 15, 1984, Revision 5, transmitted by letter dated September 28, 1984, Revision 6, transmitted by letter dated November 30, 1984, Revi-sion 7, transmitted by letter dated January 11, 1985, and Revision 8, transmitted by letter dated February 14, 1985; Safeguards Contingency Plan, Revision 0, transmitted by letter dated February 8,1980, Revi-sion 1, transmitted by letter dated September 8, 1981, Revision 2, transmitted by letters dated March 31, 1982 and April 30, 1982, (Revision 3wasnotsubmitted),RevisionC,transmittedbyletter dated August 22, 1984 (Revision 5 was not submitted), Revision 6, transmitted by letter dated November 30, 1984, Revision 7, transmitted by letter dated January 11, 1985 and Revision 8, transmitted by letter dated February 14, 1985; and the Security Training and Qualification Plan Revision 0, transmitted by letter dated July 30, 1981, Revision 1, transmitted by letters dated March 31, 1982, and April 30, 1982, (Revi-sions 2 through 5 were not submitted), Revision 6, transmitted by letter dated November 30, 1984, Revision 7, transmitted by letter dated January 11, 1985, and Revision 8, transmitted by letter dated February 14, 1985.

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F.

Except as otherwise provided in the Technical Specifications or En-

.vironmental Protection Plan, the licensee 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 describedLin 10 CFR 50.73(b), (c) and (e).

G. :The licensees shall have and maintain financial' protection of such type

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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.

H.-

This license is effective as of the date of issuance and shall expire at Midnight on -March 11, 2025.

FOR THE NUCLEAR REGULATORY COMMISSION lc

' Harold R. Den' ton, Director Office of Nuclear Reactor Regulation Attachments / Appendices:

1. - Tests and Other Items which must be Completed
2. : Attachment 2 - Operating Staff Experience Requirements

-- 3.. Attachment 3 - NUREG-0737, Supplement 1, Requirements 4.

Appendix A'- Technical Specifications (NUREG1109) l S.

Appendix B - Environmental

' Protection Plan 6.

Appendix C - Antitrust Conditions Date of Issuance: MAR 111985

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7 ATTACHMENT I 1.:

Prior.-to achieving initial criticality, the licensee shall complete, to the satisfaction of Region :IV, the following activities:

a.-

- All outstanding test deficiencies and associated retesting from Radwaste System Preoperational Tests SU3-HA01, SU4-PB01, Sild-HR02, SU4-HC01, SU4-HC02, and SU4-HC04 shall be resolved consistent with system operability requirements.

(482/8323-03, 04, 06, and 07)

b. -

The primary containment high radiation monitors shall be source checked'and calibrated.

(482/8406-04) 4.

Establish by additional. testing, the capability to close the pressurizer power operated relief valves following a pressure blowdown of approximately 200 psig starting at normal system operating pressure.

(482/8455-04) d.

Verify that operating vibration of the turbine driven auxiliary feedwater pump is acceptable.

(482/8509-01) e.

Resolve by test, the thermal expansion test discrepancies identified during the performance of Preoperational Test SU3-0004, " Power Conversion and ECCS Thermal Expansion Test." (482/8509-04) f.

- Establish by test, the operability of process radiation mon'itors SJ-RE-01 (CVCS Letdown Monitor), GE-RE-92 (Condenser Air Discharge Monitor), and GH-RE-23 (Waste Gas Decay Tank Vent Monitor).

g.

Preoperational testing and calibration of area, process and effluent radiation monitors.

(482/8323-08,09)-

2.

Prior to exceeding 5 percent of rated themal power,- the licensee shall complete, to the satisfaction of Region IV, the following activities:

a.

Complete implementation of a radiochemistry training program for all required personnel.

(482/8404-03) b.-

Implementation and operability demonstration of the postaccident sampling system.

(482/8404-07) c.

Demonstration of the ability to conduct timely shift auamentation.

(482/8425-5?)-

d.

Submit an evaluation demonstrating acceptable operation of ECCS, component cooling water, essential service water, and motor driven auxiliary feedwater pumps at the minimum electrical frequency allowed by Technical Specifications for the emergency diesel generators.

(482/8459-06) l 1

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Prior to startup following the first refueling outage, the licensee shall c-

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complete, to the satisfaction of Region IV, the following activities:

a..

Replace the emergency diesel generator lube oil keep warm pumps, with pumps satisfying ASME Section III Class 3 requirements.

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d' ATTACHMENT 2 Operating Staff Experience Requirements KG8E shall have a licensed senior operator (ni each shift who has had at least six months of hot operating experience on a same type plant, including at least six weeks at power levels greater than 20% of full power, and who has had start-up and shutdown experience.

For those shifts where such an individual is not available on the plant staff, an advisor shall be provided who has had at least four years of power plant experience, including two years of nuclear plant expe-rience, and who has had at least one year of experience on shift as a licensed senior operator at a similar type facility. Use of advisors who were licensed i

only at the R0 level will be evaluated on a case-by-case basis.. Advisors shall be trained on plant procedures, technical specifications and plant systems, and shall be examined on these topics at a level sufficient to assure familiarity

- with the plant. For each shift, the remainoer of the shift crew shall be trained in the' role of the advisors. The training of the advisors and remainder of the

. shift crew shall be completed prior to exceeding 5% power. Prior to exceeding 5% power, KG&E shall certify to the NRC the names of the advisors who have been examined and have been determined to be competent to provide advice to the operating shifts. These advisors, or fully trained and qualified replacements, shall be retained until the experience levels ident?fied in the first sentence above have been achieved. The names of any replacement advisors shall be certified by KG&E prior to these individuals being placed on shift. The NRC shall be notified at _least 30 days prior to the date KG8E proposes to release the advisors from further service.

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P ATTACPPENT 3

~ NUREG-0737. SUPPLEMENT 1, REQUIREMENTS

'(1) Control Room Design Review (I.D.1, SSER #5)

Prior to May 1, 1o85, KG&E shall submit for review and approval by the NRC staff, the results of the function and task analysis to identify control room operation tasks and information and control reouirements during emergency operations. The results of the task analysis shall be compared 4

- to a control room inventory. For those Human Engineering Discrepancies

-(HEDs) identified by this analysis that require correction, the submittel shall include the proposed correction and implementation schedule;-and for those HEDs for which no planned-correction is proposed, a basis for

.that determination shall be documented.

-(2) Functional and. Task Analysis (I.C.1, SSER #5)

Prior to startup following the first. refueling outage, KG&E shall submit for staff review and approval, a description of the process used to complete the functional and task analysis. including a description and justification for all information, and control deviations from the Westinghouse Owners Group Emergency Response Guidelines, Revision 1.

(3)- Em m ency Response Capabilities (Generic Letter 82-33, Supplement 1 1

To NUREG-0737)

Prior to restart following the first refueling outage, KG&E shall have a fully functional Technical Support Center and Emergency Operations 1

Facility and a fully operable Emergency Response Facilities Information System ERFIS).

(4) Reaulatory Guide 1.97 (Section 7.5.2.3, SSER #3)

L Prior to restart following the first refueling outage, KG&E shall have installed and operable the following instrumentation.

(a) Source range instrumentation qualified to post-accident conditions I

(b) Reactor vessel water level. instrumentation i

b (c).Subcooling monitors i.

(d) P.adiation monitors for releases from steam generator safety / relief l.

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(e) Auxiliary feedwater pump turbine exhaust monitor

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