L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached

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Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached
ML20210J113
Person / Time
Site: Beaver Valley
Issue date: 07/30/1999
From: Jain S
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-99-124, NUDOCS 9908040201
Download: ML20210J113 (21)


Text

Beaver Valley Power Station Shippingport, PA 15077-0004 s

en of VI Pr s! dent Fax 7 )64 8 9 Nc ow Division July 30, 1999 L-99-124

/ U. S. Nuclear Regulatory Commission

/ Attention: Document Control Desk Washington, DC 20555-0001 i

l

Subject:

Beaver Valley Power Station, Unit No. I and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Withdraw Part of License Amendment Request Nos. 269 and 144 This letter requests withdrawal of the editorial changes that do not pertain to the transfer of the operating authority or plant ownership that are proposed in License Amendment Request Nos. 269 and 144, submitted by Letter L-99-068 dated May 5,1999. Based on discussions between members of the NRC and the Duquesne Light Company (DLC) staff, the determination was made that the editorial changes that do not pertain to the transfer of the operating authority or plant ownership can be excluded from License Amendment Request Nos. 269 and 144. Therefore, Attachments A-1 (for BV-1) and A-2 (for BV-2) contain the revised marked-up License pages that reflect those changes that pertain to the transfer of plant operating authority or plant ownership.

Sincerely, Sushil C. Jain

'/ !,

c:

Mr. D. S. Collins, Project Manager

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Mr. D. M. Kern, Sr. Resident Inspector

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Mr.' H. J. Miller, NRC Region I Administrator Mr. W. P. Dornsife, Director BRP/DEP ho },

o Mr. M. P. Murphy (BRP/DEP) 9900040201 990730 PDR ADOCK 05000334 DEllVERING

[9.g9994 PDR g y g ( l 7,y ENERGY

AFFIDAVIT FOR APPLICATION OF AMENDMENT COMMONWEALTH OF PENNSYLVANIA)

) SS:

COUNTY OF BEAVER

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Subject:

Beaver Valley Power Station, Unit No. I and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Withdraw Part of License Amendment Request Nos. 269 and 144 Before me, the undersigned notary public, in and for the County and Commonwealth aforesaid, this day personally appeared Sushil C. Jain, to me known, who being duly sworn according to law, deposes and says that he is Senior Vice President, Nuclear Services of the Nuclear Power Division, Duquesne Light Company, he is duly authorized to execute and file the foregoing submittal on behalf of said 1

Company,i.ed the statements set forth in the submittal are true and correct to the best of i

his knowledge, information and belief, i

Q Ext.d -

' Sushil C. Jain "

Subscribed and sworn to before me on this ay of

, /77f Tra,~u d g

7,

  1. ' lotarial Seal Tracey A. Baczek, Notary Public My omm n xpir A.

1 Mernber, Pennsylvania Association of Notanes

REVISED ATTACHMENT A-1 t

Beaver Valley Power Station, Unit No. 1 License Amendment Request No. 269 The following is a list of the affected pages:

Affected Pages:

Operating License page 1 Operating License page 2 Operating License page 3 Operating License page 4 operating License page 6 Operating License page 6a Appendix C of Operating License i

UNITED STATES t,

1 NUCLEAR REGULATORY COMMISSION y

j r:AsHINGToN. D. C. 20655

/

MIRSTENEd6Y Nutt.tMt ofEM ATim GoMFAN j

  • 5 OHIO EDISON COMPANY

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PENN5YLVANIA POnER COMPANY l

DOCKET NO. 50-334 BEAVER VALLEY POWER STATION UNIT NO. I FACILITY OPERATING LICENSE Amendment No. 4 License No. DPR-66 c ki g c wn ik S otA m M4 ad ag'epY fo I.

The Nuclear Reculatory Commission (the Commission) having found that:

l G*ies%ss#v Nuded Oper=Y$a:n 6_ :; CFENoc.T'y ;r,. Ohio The appilcaTron for license rwea Dy r_ ::::: _:;;r

_r A.

Edison Company, and Pennsylvania Power Company (the licensees) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and 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 Beaver Valley Power Station, Unit No.1 (f acility), has been substantially completed in conformity with Construction Permit No. CPPR-75 and the application, as amended, the provisions of the Act and the rules and regulations of the Commission; C.

The f acility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; D.

There is reasonable assurance: (i) that the activities authorized by this amended operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compilance with the rules and regulations of the Commission;

.(FENoQ

' @^ 5;E, is technically quellflod and the licensees J

E.

? gn:

are financially quallfled to engage in the activities authorized by this amended operating license in accordance with the rules and regulations of the Commission; F.

The licensees have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agree-monts," of the Commission's regulations; MD 1

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G.

The issuance of this amended operating license will not be inimical to the common defense and security or to the health and safety of the public; j

H.

After' weighing the environmental, economic, technical, and other benefits of the facility against environmental and o+ner costs and considering available alternatives, the issuance of Amendment No. 4

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to Facility Operating License No. DPR-66 is in accordance with 10 CFR Part 51 (formerly Appendix 0 of 10 CFR Part 50) 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 amended license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70, including 10 CFR Sections 30.33, 40.32, 70.23, and 70.31.

2.

Facility Operating License Pt. OPR-66 issued to Mrr: L!

Cr;rj, 7

Ohio Edison Company, and Pennsylvania Power Company is hereby amended in its entirety to read as follows:

A.

This amended license applies to the Beaver Valley Power Station, Unit I

L!;"/

No. I, a pressurized water nuclear reactor and associated equipment (the f acility), owned by 7.; l';;;;;; and operated by 0;; :=:

Gempany.

The f acility is located in Beaver County, Pennsylvania, on the so'uthern shore of the Ohio River, and is described in the " Final Safety Analysis Report" as supplemented and amended (Amendments I through 21) and the Environmental Report as amended (Sunnleman+= 1 +hrough 6).

G hio t eston C m pow emd f% ntNWeMoi / owe.r Come 8.

Subject to tne conditions' and requirements incorporated herein, e

Comission hereoy licenses:

00, 0:;::=: L' p? Or;; y, pursuant to Section 104b of the Act and 10 CFR Part 50, " Licensing of Production and Utilization Facilities," to possess, use, and operate the facility and DELEW Ohio Edison Company, and Pennsylvania ver Company to possess the f acility at the designated location in Seaver County, Pennsylvania in accordance with 4

the procedures and limitations set forth in this amended q

license; ENOC-(2 Or-er: Lf 7^ fr;r y, 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 ith the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; hyo5e hMONM

. (3

,__ _......... - _,_,, pursuant to the Act and 10 CFR Parts 30, 40 g

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; (FE E M(4)D ::::

.' f;50 C:-;;r;, 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 material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or compoaents; (5)7" ;;:::: '.i;ht 0:-;;;; pursuant to the Act and 10 CFR Parts 30 and

@ N O C y. 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

This amended license shall be deemed to contain and is subject to the conditions specified in the following Comeission regulations in 10 CFR Chapter 1: Part 20, Cection 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 Level oc S : rn 'ight C1;=; is authorized to operate the facility at a steady state reactor core power level of 2652 megawatts thermal.

(2) Technical Specifications khbe.alded h NRG)

The Technical Specificati n Icontained in Appendix A, as revised through Amendment No, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Auxiliary River Water System (Deleted by Amendment No. 8)

Amendment No. % %, 4 #

UtopsSeci %orbMh (next page is 6)

(3)

Less Than Three looo Ooeration FENt(,

Du;==: U;ht C: p=; shall not operate the reactor at power levels above P-7 (as defined in Table 3.3-1 of Specification 3.3.1.1 of the Technical Specifications, Appendix A) with less than three (3) reactor coolant loops in operation until safety analyses for less than three loop operation have been submitted by the licensees and approval for less than three loop operation at power levels above P-7 has been granted by the Commission by amendment of this license.

(4)

Steam Generator Water Rise Rate Deleted per License Amendment No. 24.

(5)

Fire Protection Proor&m 3,,,Th: l i::=: shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final (FEt40c}

Safety Analysis Report (UFSAR) for the facility, subject to the following provision:,th; li:= =: 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.

I Amendment No. 8, M, M, 48, M, M, 39, 4M, C rr=t:d by 1:tter d;ted feril % N (ProgescskIMOMiy

\\

DPR-66 *

(6)

Systems Intearity FENoc.

DT'^rre Light C: ; ny shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

This program shall include the following:

1.

Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2.

Integrated leak test requirements for each system at a

frequency not to exceed refueling cycle intervals.

(7)

Iodine Monitorina (FENo9

=nue:rere ti;5t cer;1ry shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

1.

Training of personnel, 2.

Procedures for monitoring, and 3.

Provisions for maintenance of sampling and analysis equipment.

(8)

Backun Method for Determinina Subcoolina Marcin CFENobt" T2 rn Li;ht " 4 27 8 hell implement a program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin.

This program shall include the following:

1.

Training of personnel, and 2.

Procedures for monitoring.

(9) 3,ta== Generator Surveillance Interval Extension The performance interval for the steam generator surveillance requirement identified in the licensee's requert for surveillance interval extension dated November 11, 1998, shall be extended to coincide with the cycle 13 refueling outage or the end of 500 effective full power days, whichever is sooner.

This surveillance will not extend beyond June 15, 2000.

Amendment No. 944.

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(10)

Additional Conditions k

b I

The Additional Condition contained in Appendix C, as revised throuah Amendment No.

, are hereby incorporated into this (FENotf. license.% rent l'.;ht Cn;=; shall operate the facility in accordance with the Additional Conditions.

2.D.. Physical Protection hNOL Th; li;n:n shall fully implement and maintain in effect all provisions of the following Commission approved documents, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p).

These approved documents consist of information withheld from public disclosure pursuant to 10 CFR 2.790(d):

(1) " Beaver Valley Power Station, Unit No. 1, Physical Security Plan",

Revision 1, dated October 31, 1977, as supplemented by Revision 2 dated May 15, 1978, Revision 3 dated February 21, 1979.

(2) The NRC approved Safeguards Contingency Plan as transmitted by letter of March 22, 1980.

(3) " Beaver Valley Power Station Guard Training and Qualification Plan",

submitted by letter, dated August 16, 1979, as revised by letter dated September 26, 1980. This Plan shall be fully implemented in accordance with 10 CFR 73.55(b)(4), within 60 days of this approval by the Commission. All security personnel shall be qualified within two years of this approval.

E.

All work and activities in connection with this project shall be performed pursuant to the provisions of the Commonwealth of Pennsylvania Clean Streams Acts of June 24, 1913, as amended, and of June 22, 1937, as amended, and.in accordance with all permits issued by the Department of Environmental Resources of the Commonwealth of Pennsylvania.

2.F.

This amended license is effective as of the date of issuance and shall expire at midnight on January 29, 2016.

FOR THE NUCLEAR REGULATORY COMMISSION i

ORIGINAL SIGNED BY R. S. 50VD Roger S. Boyd, Director Division of Project Management Office of Nuclear Reactor Regulation Date of Issuance: July 2, 1976 Amendment No. 34, 34, M6,4GB (f y sseh Gorbs

t APPENDIX C

^

ADDITIONAL CONDITIONS OPERATING LICENSE NO. DPR-66 sWeg Nwdtpgwpg Mr;ur: 'i;ht C ;x;,. Ohio Edison Company, and Pennsylvania Power Company i

' shall comply with the following conditions on the schedules noted below-Amendment Additional Condition Implementation

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Number Date i

202 The-licensee is authorized to relocate certain The amendment Technical Specification requirements to shall be licensee-controlled documents.

Implementation implemented of this amendment shall include the relocation within 60 days of these technical specification requirements from April 14, to the appropriate documents, as described in 1997 the licensee's application dated September 9, 1996, and evaluated in the staff's safety evaluation attached to this amendment.

208 The licensee commits to perform the post weld The amendment heat treatment of sleeve welds and the shall be NRC-recommended inspections for repaired tubes implemented as described in the licensee's application within 60 days dated March 10, 1997, as supplemented July 28 from and September 17, 1997, and evaluated in the November 25, staff's safety evaluation attached to this 1997 amendment.

209 The licensee is authorized to relocate certain The amendment Technical Specification requirements to shall be licensee-controlled documents.

Implementation implemented of this amendment shall include the relocation within 60 days of these technical specification requirements from to the appropriate documents, as described in December 10, the licensee's application dated March 14, 1997 1997, as supplemented July 29 and August 13, 1997, and evaluated in the staff's safety evaluation attached to this amendment.

210 The licensee is authorized to relocate certain The amendment Technical Specification requirements to shall be licensee-controlled documents.

Implementation implemented of this amendment shall include the relocation within 30 days 1

of these technical specification requirements from to the appropriate documents, as described in January 20, 1998 the licensee's application dated September 11, 1997, and evaluated in the staff's safety evaluation attached to this amendment.

1 Amendment No. MB, 308, M9,4M-(fropo5 d W ord

REVISED ATTACHMENT A-2 Beaver Valley Power Station, Unit No. 2 License Amendment Request No. 144 4

The following is a list of the affected pages:

Affected Pages:

Operating License page 1 Operating License page 2 Operating License page 3 Operating License page 3a operating License page 5 Operating License page 6 Operating License page 7 Cover page for Appendix B to the Operating License Appendix B of Operating License Page 1 J

Appendix D of Operating License j

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UNITED sTATss

,{

g NUCLEAR REGULATORY COMMISSION

-ADD mASMlaecToN, D. C. 20555 0

','...../

rutSTENEd&Y t4utteAttn#vtATING CnM9ANY ML CNA" hEtan(LMNW foWEk OHIO EDIS0N COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDIS0N COMPANY DOCKET N0. 50-412 SEAVER VALLEY POWER STATION, UNIT 2 FACILITY 0PERATING LICENSE 9thwsylVamm 8= wet Comte License No. NPF-73 1.

The' Nuclear Regulatory Comission (the Cessnission or the NRC) has found that:

M h g N d w cytta kag Co (FENOC. M A.

The application for license filed by N h ; x = M p.; 5.xp 1

5 actino "r : W and as agent for40hio Edison Caspany. The Cleveland on dS E' ectric Illuminting Company, and The Toledo Edison company (the I

be.b44 licensees), couplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regula -

tions set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made;

, B.

Construction of the Beaver Valley Power Station, Unit 2 (the facility) has been substantially completed in conformity with Construction Permit No. CPpt 105 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 (ezcept as exempted from compliance in Section 2.0.

below);

D.

There is reasonable assurance:

(1) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public and (ii) that such activ' ties will be conducted in compliance with the Coussission's regulations set Section 2.0. below)pter I (except as exempted from compliance in forth in 10 CFR Cha

^I7 ' "* * * *'#

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(FENOC.)

%:== 1"70 I _ x; "".Cd is authorized to act as agent for" Ohio Edison Company. The Cleveland Illuminating Electric Caspany, and The Toledo Edison Company and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.

(fropstec\\Woch y)

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FENog.

E.

Mrm Lf;5t Car; i, technically qualified to en' gage in.the activities authorized by this license in accordance with-the Commission's regulations set forth in 10 CFR Chapter I; F.

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

The issuance of this license will not be inimical to the coninon 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 r,nvironmental and other costs and considering available alternatives, the issuance of this Facility Operating License No. NPF-73 is subject to the conditions

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for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 cf the Consnission's regulations, and all applicabk

, requirements have been satisfied; I;

The receipt, possession and use of source, byproduct and special nuclear material as authorized by this l':ense will be in accordance-with the Consuission's regulations in 10 CFR Parts 30, 40, and 70.

2.

Based on the foregoing findinfis, review by the Nuclear Regulatory Consiission at a meeting on Ju y 8,1987, and approval by the Consnission on August 13, 1987, the License for Fuel Loading and Low Power Testing Operating License NPF-73, hereby issued to 0; N;nn Li@t L-;=,[,E License No. NPF-64, issued on May 28, 1987, is superseded by Facility 40hio Edison Company, The Cleveland Electric Illuminating Company, and

~ The Toledo Edison Cemnany (the licensees) to read as follows:

Servsvwo.w P.we.r cowoav,1 A.

This license applies to the Beaver Valley Power Station, Unit 2, a pressurized water reactor and associated equipment (the facility) owned by40hio Edison Company The Cleveland Electric 111uminatina g g Company, and The Toledo Edison Company 2 f :. r and operated by FENoc 0; Z:x:: 'i;50 L r;. The facility is located on the licensees' site on the southern shore of the Ohio River in Beaver County, Pennsylvania, approximately 22 miles northwest of Pittsburgh and 5 miles east of East Liverpool, Ohio, and is described in

.p

and amended, and in its Environmental Report, as supplemented and Z
n ; U;t * ;r.,': Final Safety Analysis Report, as supplemented FgJ amended; S.

Subject to the conditions and requirements incorporated herein, the Consnission hereby licenses:

gggog (1) Pursuant to Section 103 of the Act and 10 CFR Part 50, Segu%sme Lf;5t C ; r;/ to possess, use, and operate the facility at the designated location in Beaver County, Pennsylvania, in accordance with the procedures and limitations set forth in l

this license; Wtsfosub Wob

I

=

. Asp oo iA k m f (c y l

(2)

Pursuant to the Act and 10 CFR Part 50,'f0hio Edison Company.

The Cleveland Electric Illuminating Company, cnd The Toledo Edison Company to possess the facility at the designated location in Beaver County, Pennsylvania, in accordance with the procedures and limitations set forth in the licensei NOC-(3). Pursuant to the Act and 10 CFR part 70, i;m '_det C pq 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 A alysis Report, as supplanented and amended; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, Duquesee L*f t P---

y to receive, possess, and use at any time any byproduct, source, and special nuclear material such 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; g

(5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, Dugveene L' 7 0 C n : ;/ to receive, possess, and use in amounts as required any byproduct, source, or smetal nuclear material without restriction to chemical or piysical fom, for sample analysis or instrument calibration or othu activity associated with radioactive apparatus or components; (FENCC-(6) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, lift C J2; to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of thL facility authorized herein.

(a) gewoma r.warcwpow)

(7)

. J;x i n Li d t t ; ;, Ohio Edison Company, The Cleveland ElectricIlluminatingCompanyandTheToledoEdisonCompany are authorized to transfer any portion of their respective 1

13.745, 41.881, 24.475 and 19.91% ownership interests in 8VPS Unit 7 and a proportionate share of their ownership interests in the BVPS consnon facilities to certain potential investors identified in their submittals of July 14,16, 22 and '31, and September 14,17 and 18,1987, and at the same time to lease back from such purchasers such interest transferred in the BVP5 Unit 2 facility. The term of the lease is for approximately 29-1/2 years subject to a right of renewal. Such sale and leaseback transactions are subject to the representations and conditions set forth in the aforementioned submittals. Specifically, a lessor and anyone else who may acquire an interest under these transactions are prohibited from exercising directly or indirectly any control over the Itcense of BVPS Unit 2.

For purposes of this condition the limitations in 10 CFR 50.81, as now in effect and as may be subsequently amended, are fully applicable to the lessor and any successor in interest to that lessor as long as the license for BVP5 Unit 2 remains in effect; these financial

([roposed Wob

r-9 1.

- 3a -

transactions shall have no effect on the license for the BVPS Unit 2 facility throughout the term of the license.

(b)

Further, the licensees are also required to notify the NRC in writing prior to any change in:

(1) the tem or conditions of any lease agreements executed as part of these transactions; (111 insur,the BVPS Operating Agreement, (iii) the existing property ance coverage for BVPS Unit 2 and (iv) any action by a lessor or nthers that may have an a,dverse effect on the sa'e operation of the facility.

C.

This license shall be deemed to contain and is subject to the conditions specified in the Connission's regulations set forth in 10 CFP 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 TENo pt okse is authorized to operate the factlity at reactor core power V

levels not in excess of 2652 megawatts themal (100 percent power) in accordance with the conditions specified herein.

(2) Technical Snecifications

  • h4
  • b'i The Technical Specification Icontained in Appendix A, as revised through Amendment No.

nd the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the licens #e in accordance with the Technical Tpecifications and theshall operate the facility Environmental Protection Plan.

0Q e

L

(8) Detailed Control Room Desian Review (DCRDR)

Deleted (9) Sifety Parameter Disclav System (SPDS)

Deleted (10) Fire Protection Modifications (Section 9.5.1 of SER Sunclement 61 l

Deleted q

(11) Additional Conditions b*boMd j

The Additional Condition contained in Appendix D, as revised through Amendment No.

' are hereby incorporated into this license. ex:n '.'dt 5;=, shall operate the facility in withtheAIiditionalConditions.

accordance D.

Exemotions The following exemptions are authorized by law and will not endanger life or property or the common defense and security, and certain special circumstances are present. 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 Commission.

(1) The facility requires an exemption from the requirements of' General Design Criterion (GDC) 4, Appendix A to 10 CFR 50.

The staff has described in detail in Supplement 4 and Supplement 5 to the Safety Evaluation Report the technical basis and "special circumstances" associated with this exemption. The staff's environmental assessment was published on March 27, 1987 (52 FR 9979). Therefore, pursuant to 10 CFR 50.12(a (1), 10 CFR 50.12(a)(1)(11) and Civ), Beaver Valley Power) Station, Unit 2 is exempt from the requtrements of GDC 4, Appendix A to 10 CFR 50 with respect to the dynamic loading effectr associated with the postulated pipe breaks described in detail in Section 3.6.3 of Supplement 4 to the Safety Evaluation Report. These dynamic loading effects include pipe whip, jet impingement, and break-associated dynamic transients. Specifically, this eliminates the need to install jet impingement Iarriers and pipe whip restraints associated with postulated pipe breaks in the pressurizer surge line, reactor coolant lpypass system, BEAVER VALLEY - UNIT 2 Amendment No. M,46 -$t-F i Or-

r.

safety injection system, and residual heat removal system. This exemption will expire when the current GOC 4 rulemaking changes have been completed.

(2)

Jhe facility requires an exemption from the requirements of 10 CFR liD, Appendix J,Section III.D.2 b)(ii). The justification of this exemption is contained in Section 6.2.6 of Supplement 5 to the Safety Evaluation Report and modiflod by a letter dated Juif 26, 1995.

The staff's environmental assessment was published on May 12, 1987

($2 FR 17651) and on June 9, 1995 pursuant to 10 CFR 50.12(a)(1) and(60 FR 30611). Therefore, 10 CFR 50.12(a)(2)(11) and (iii), Beaver Valley Power Station, Unit 2 is exempt from the quoted requirement and instead, is required to perform the overO..

air lock leak test at pressure P before establishing containment integrity if air lock maintenance has been perfomed that could affect the air lock sealing capability. Local leak rate testing at a pressure of not less than P air lock test where the desig, may be substituted for an overall n permits.

(3) The facility was previously granted an exemption from the criticality alare requirements of 10 CFR 70.24 (see License No.

SNM-1954) dated April 9, 1986, which granted this exemption).

Beaver Valley Power station, Unit 2 is hereby exempted from the criticality alars system provisions of 10 CFR 70.24 so far as this sectica applies to the storage of fuel assemblies held under this license.

E.

Physical Security shall fully implement and maintain in effect all provisions of the ptiNoc.

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 50.90 and 10 CFR 50.54(p). The plans, which contain safeguards information protected under 10 CFR 73.21, are entitled:

" Beaver Valley Porer station security Plan," with revisions submitted through April 15, 387; '8eaver Valley Power Station Security Training and Qualification Plan,' with revisions submitted 1

through April 15 1987; and Beaver Valley Power Station security Cantingency Plan,,' with revisions submitted through February 19, 1987.

F.

Fire Protection Procram (Section 9.5.1 of SER Supplement 3) eggoc3>,n9L4o shall implement and maintain in effect all provisions of the L

approved fire protection program as described in the Final Safety Analysis Report through Amendment No.17 and submittals dated May 18, May 20, May 21, June 24 and July 6, 1987, and as described in the Safety Evaluation Report dated October 1985, and Supplements 1 through 6, subject to the following provision:

Amendment No. fE-O (feoposed Wod'b[

NPT-73

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@ENo.Q d u ee-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.

Renortine to the commission DELETED H.

Financial Protection The licensees 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.

I.

Erniration This license is effective on the date of issuance and shall expire at midnight on May 27, 2027.

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FOA The sucLEAA REGULATORY COMMISSION

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ORIGINAL SIGNED BY:

Thomas E. Murley, Director office of Nuclear Reactor Regulation

Enclosures:

1.

Appendix A - Technical Specifications (NUREG-1279) 2.

Appendix B - Environmental Protection Plan Date of Issuance:

August 14, 1987 l

Aga*af A..ne nt No. 4

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APPENDIX B

.To FACILITY OPERATING LICENSE NO. NPF-73 BEAVER VALLEY P0ER STATION UNIT 2 e DIN lH6ME-M4HTiiGMPANY, ET AL DOCKET N0. 50-412 ENVIR0lmENTAL PROTECTION PLAN (NONRADI0 LOGICAL)

August 1987 FIRSTENERGY NutLEM 09EAA11NG COMPANY e

(G.gi.a w -a l g

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1.0 Objectives of the Environmental Protection Plan The Environmental Protection Plan (EPP) is to provide for protection of -

nonradiological environmental values during operation of the Beaver _ValTey Power Station. Unit 2 (facility). The principal objectives of the EPP are as follows:

(1) Verify that the facility is operated in an environmentally acceptable manner, as established by the Final Environmental Statement - Opera' ting License Stage (FES-OL) and other NRC environmental impact assessments.

(2) Coordinnte NRC requirements and maintain consistency with other Federal.

State, and local requirements for environmental protection.

(3) Keep NRC infomed of the environmental effects of facility construction and operation and of actions taken to control those effects.

Enviremental concerns identified in the FES-OL (September 1985, NUREG-1094) which relate to water quality matters are regulated by way of the licensee's*

NPDES pemit.

2.0

  • Environmental Protection Issues IntheFES-OL(NUREG-1094. September 1985),thestaffconsideredthe environmental impacts associated with the operation of the Beaver Valley Power Station. Unit 2.

No aquatic / water quality, terrestrial, or noise issues were identified.

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3.0 Consistency Reouirements 3.1 Plant Design and Goeration The licensee may make changes in station design or operation or perfom tests or eiperiments affecting the environment provided such activities do not involve an unreviewed environmental question and do not involve a change in the EPP*. Changes in station design or operation or perfomance of tests or experiments which do not affect the environment are not subject to the requirements of this EPP. Activities governed by Section 3.3 are not subject to the requirements of this Section.

Before engaging in additional construction or operational activities which may significantly affect the environment. the licensee shall prepare and record an environmental evaluation of such activity. Activities are excluded from this requirement if all measurable nonradiological environmental effects are confined to the on-site areas previously disturbed during site preparation and plant construction. When the evaluation indicates that such activity involves an unreviewed environmental question, the licensee shall provide a written evalu-ation of such activity.and obtain prior NRC approval. Such activity and change to the EPP may be implemented only in accordance with an appropriate license amendment as set forth in Section 5.3 of this EPP.

esWnergf NsadearCWs*3 64an'td C

" Licensee" refers to 4 ;.7. ".'Ja i

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M omrator of the facility, and acting as. agent fornphio tdison Company. T3e C1 d

Electric Illuminating Company, andlThe Toledo Edison Company, owners j

of fac m ty.

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APPENDIX D ADDITIONAL CONDITIQNJ OPERATING LICENSE NO. NPF-73

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W;::.: L';.: C:I; n,, Ohio Edison Company, The Cleveland Electric illuminating Company, and The Toledo Edison Company shall comply with the following conditions on the schedules noted below-Amendment Additional Condition Implementation Number-Date 83 The licensee is authorized to relocate certain This amendment Technical Specification requirements to shall be

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licensee-controlled documents. Implementation implemented of this amendment shallinclude the relocaten within 60 days of these technical specificebon requirements from April 14, to the appropriate documents, as described in 1997 3

the licensee's application dated September 9, 1996, and evaluated in the staff's safety evaluation attached to this amendment.

87 The licensee is authorized to relocate certain The amendment Technical speafication requirements to shall be licensee-controlled documents. Implementation implemented within of this amendment shallinclude the relocabon 60 days from of these technical speaficaf. son requirements December 10, to the appropriate documents, as described in 1997 the licensee's applicaten dated March 14, 1997, as supplemented July 29 and August 13, 1997, and evaluated in the staffs safety evaluation attached to this amendment.

88 The licensee is authorized to relocate certain The amendment Technical Specificahon requrements to shall be licenseN:ontrolled documents. Implementation implemented of this amendment shallinclude the relocation within 30 days of these technical spooficedon requirements to from the appropriate documents, as described in the January 20,1998 licensee's apphcahon dated September 11, 1997, and evaluated in the staffs safety evaluation attached to this amendment.

98 The licenses commits to perform visual The amendrnent acceptance examinations of sleeve welds; post shall be weld heat treatment of sleeve welds; and the implemented within NRC-recommended inspections of repared 60 days from tubes as described in the licensee's applicaton Ptreh 26,1999 dated March 10,1997, as supplemented July 28,1997, September 17,1997, April 30,1998,

'4 and January 29,1999, and evaluated in the staffs safety evaluation attached to this amendment, esNnap Nadeeroper thy

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