ML20137Y813

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Amends 202 & 83 to Licenses DPR-66 & NPF-73,modifying Design Features Section 5.0 of TSs to Make Design Features Section Consistent W/Intent of 10CFR50.36 & W/Guidance Provided in NRC STS
ML20137Y813
Person / Time
Site: Beaver Valley
Issue date: 04/14/1997
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co
Shared Package
ML20137Y819 List:
References
DPR-66-A-202, NPF-73-A-083 NUDOCS 9704230244
Download: ML20137Y813 (25)
v • d • e


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o UNITED STATES 5

NUCLEAR REGULATORY COMMISSION k..... /

j WASHINGTON D.C. 20556-0001 DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION. UNIT NO. 1 i

AMENDMENT TO FACILITY OPERATING LICENSE

. Amendment No. 202 License No. DPR-66 4[

1.

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

l.

A.

The application for amendment by Duquesne Light Company, et al. (the licensee) dated September 9,1996, complies with the standards and i

requirements of the Atomic Energy Act of 1954, as amended (the Act),

j and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, j

.the provisions of the Act, and the rules and regulations of the Comission; i

C.

There is reasonat,le assurance (i) that the activities authorized i

by this amendment un be conducted without endangering the health l.

and safety of the public, and (ii) that such activities will be l

conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part i

51 of the Comission's regulations and all applicable requirements have been satisfied.

)

9704230244 970414 PDR ADOCK 05000334 p

PDR

j v

l -

i 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, i

-and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:

-(2) Technical Specifications j

The Technical Specifications contained in Appendix A, as revised through Amendment No.202, are hereby incorporated in the license.

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

i In addition, the license is amended to add paragraph 2.C.(10) to the Facility Operating License No. DPR-66 as follows:

{

(10) Additional Conditions i

The Additional Conditions contained in Appendix C, as revised i

through Amendment No. 202, are hereby incorporated into this license.

Duquesne Light Company shall operate the facility in 1

accordance with the Additional Conditions.

i 3.

This license amendment is effective as of its date of issuance and the change to the facility shall be implemented within 60 days from the date of issuance.

Implementation of this amendment shall include the l

relocation of certain technical specification requirements to the appropriate licensee-controlled documents as described in the Licensee's i

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

j FOR THE NUCLEAR REGULATORY COMMISSION b

John F. Stolz, Director i

Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:

1.

Page 6a to License

  • No. DPR-66 and page 1 to Appendix C of License

Changes to the Technical Specifications Date of Issuance: April 14, 1997

  • Page 6a of the license and page 1 of Appendix C are attached, for convenience, for the composite license to reflect this change.

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ATTACHMENT TO LICENSE AMENDMENT NO.202 l

FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 1.

Revise License as follows:

4 Remove Paae Insert Paae 6a 6a 4'

2.-

Insert page 1 of Appendix C of the License 3.

Replace the following pages of Appendix A Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

1 Remove Insert XIV XIV XV XV XVI XVI XVII i

XVIII XVII 1

XIX XVIII XX XIX i

XXI XX 5-1 5-1 5-la 5-lb 5-Id 5-le 5-2 5-3 5-4 5-5 5-6 5-2 e

- 6a -

(10) Additional Conditions The Additional Conditions contained in Appendix C, as revised i

through Amendment No. 202, are hereby incorporated into this license. Duquesne Light Company shall operate the facility in accordance with the Additional Conditions.

1 2.D.

Etty1. cal Protection 1

The licensee shall fully implement and maintain in effect all provisions of the following Commission approved documents, including amendmerts and changes made pursuant to the authority of 10 CFR 50.54(p). These approved documents consist of information withheld from public disclosure pursuar.t 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.

l 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, 2015.

FOR THE 14UCLEAR REGULATORY COMMISSION ORIGINAL SIGNED BY R. S. BOYD Roger S. Boyd, Director Division of Froject Management Office of Nuclear Reactor Regulation Date of Issuance: July 2, 1976 Amendment No. M, 38, M6,202

A APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO. DPR-66 l

Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company shall comply with the following conditions on the schedules noted below:

Amendment Additional Condition Implementation i

Number Date i

202 The licensee is authorized to relocate certain The amendment 3

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, 1997 to the appropriate documents, as described in the licensee's application dated September 9, i

1996, and evaluated in the staff's safety 3

evaluation attached to this amendment.

)

1 Amendment No.202

p i

DPR-66 INDEX BASES SECTION PAGE 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.5 Gas Storage Tanks.......................

B 3/4 11-1 3/4.11.2.6 Explosive Gas Mixture...................

B 3/4 11-1 DESIGN FEATURES SECTION PAGE 5.1 SITE LOCATION....................................

5-1 5.2 REACTOR CORE.....................................

5-1 5.3 FUEL STORAGE.....................................

5-1 ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY...................................

6-1 6.2 ORGANIZATION 6.2.1 Onsite and Offsite Organizations........

6-1 j

6.2.2 Unit Staff..............................

6-2 I

6.3 FACILITY STAFF OUALIFICATIONS....................

6-5 6.4 TRAINING 6-5 6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY COMMITTEE (OSC) 6.5.1.1 Function................................

6-5 6.5.1.2 Composition.............................

6-5 6.5.1.3 Alternates..............................

6-6 BEAVER VALLEY - UNIT 1 XIV Amendment No. 202

{

DPR-66 INDEX ADMINISTRATIVE CONTROLS SECTION g

.a 6.5.1.4 Meeting Frequency.......................

6-6 4

6.5.1.5 Quorum..................................

6-6 6.5.1.6 Responsibilities........................

6-6 6.5.1.7 Authority...............................

6-7 l

6.5.1.8 Records.................................

6-7 j

6.5.2 OFFSITE REVIEW COMMITTEE (ORC) i

-6.5.2.1 Function................................

6-7 1

6.5.2.2 Composition.............................

6-8 l

6.5.2.3 Alternates..............................

6-8 i

1 6.5.2.4 Consultants.............................

6-8 6.5.2.5 Meeting Frequency.......................

6-9 i

a 1

6.5.2.6 Quorum..................................

6-9 i

6.5.2.7 Review..................................

6-9 6.5.2.8 Audits..................................

6-10 i

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6.5.2.9 Authority...............................

6-11 l

6.5.2.10 Records.................................

6-11 j

1 1

1 1

6.6 REPORTABLE EVENT ACTION..........................

6-11 1

i 6.7 SAFETY LIMIT VIOLATION...........................

6-11 b

4 6.8 PROCEDURES.......................................

6-12 i

6.9 REPORTING REOUIREMENTS...........................

6-16 1

. 6.9.1 Routine Reports.........................

6-16 5

6.9.1.1,2,3 Startup Reports.........................

6-16 i

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BEAVER VALLEY - UNIT 1 XV Amendment No. 202

i DPR-66 l

INDEX l

ADMINISTRATIVE CONTROLS I

SECTION EAGE i

i i'

6.9.1.4,5 Annual Reports..........................

6-17 i

4 6.9.1.6 Monthly Operating Report................

6-18 1

6.9.1.10 Annual Radiological Environmental Operating Report........................

6-18 i

6.9.1.11 Annual Radioactive Effluent Release j

Report..................................

6-19 6.9.1.12 Core Operating Limits Report............

6-19 l

6.9.2 SPECIAL REPORTS.........................

6-20 1

{

6.10 RECORD RETENTION................................

6-21 6.11 RADIATION PROTECTION PROGRAM....................

6-22 6.12 HIGH RADIATION AREA.............................

6-23 6.13 PROCESS CONTROL PROGRAM (PCP) 6-24 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6-24 6.16 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS...............................

6-25 6.17 CONTAINMENT T.FAKAGE RATE TESTING PROGRAM........

6-25 BEAVER VALLEY - UNIT 1 XVI Amendment No. 202

l DPR-66

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TABLE INDEX TABLE TITLE PAGE 2.2-1 Reactor Trip System Instrumentation Trip 2-6

{

Satpoints i

3.1-1 Accident Analyses Requiring Reevaluation 3/4 1-19a j

in the event of an Inoperable Full or Part Length Rod 3.2-1 DNB Parameters 3/4 2-13 3.3-1 Reactor Trip System Instrumentation 3/4 3-2 i

3.3-2 Reactor Trip System Instrumentation 3/4 3-9 Response Times I

4.3-1 Reactor Trip System Instrumentation 3/4 3-11 Surveillance Requirements 3.3-3 Engineered Safety Features Actuation System 3/4 3-15 Instrumentation 1

l 3.3-4 Engineered Safety Features Actuation System 3/4 3-22 Instrumentation Trip Setpoints i

3.3-5 Engineered Safety Feature Response Times 3/4 3-25 i

4.3-2 Engineered Safety Feature Actuation System 3/4 3-29 j

Instrumentation Surveillance Requirements a

3.3-6 Radiation Monitoring Instrumentation 3/4 3-34 l

j 4.3-3 Radiation Monitoring Instrumentation 3/4 3-36 j

Surveillance Requirements 3.3-7 Seismic Monitoring Instrumentation 3/4 3-39 1

i 4.3-4 Seismic Monitoring Instrumentation 3/4 3-40 i

Surveillance Requirements 3.3-8 Meteorological Monitoring Instrumentation 3/4 3-42 4.3 Meteorological Monitoring Instrumentation 3/4 3-43 l

Surveillance Requirements 3.3-9 Remote Shutdown Panel Monitoring 2/4 3-4S Instrumentation 4.3-6 Remote Shutdown Monitoring Instrumentation 3/4 3-46 Surveillance Requirements i

BEAVER VALLEY - UNIT 1 XVII Amendment No. 202 4

t

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DPR-66 l

Table Index (cont.)

TABLE TITLE PAGE AccidentMonitoringInstrubentation 3/4 3-51 3.3-11 l

4.3-7 Accident Monitoring Instrumentation 3/4 3-52 4

i Surveillance Requirements 3.3-13 Explosive Gas Monitoring Instrumentation 3/4 3-55 4.3-13 Explosive Gas Monitoring Instrumentation 3/4 3-57

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Surveillance Requirements 4.4-1 Minimum Number of Steam Generators to be 3/4 4-10e Inspected During Inservice Inspection

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4.4-2 Steam Generator Tube Inspection 3/4 4-10f 4.4-3 Reactor Coolant System Pressure Isolation 3/4 4-14b i

Valves

)

3.4-1 Reactor Coolant System Chemistry Limits 3/4 4-16 4.4-10 Reactor Coolant System Chemistry Limits 3/4 4-17 Surveillance Requirements 4.4-12 Primary Coolant Specific Activity Sample 3/4 4-20 and Analysis Program 3.7-1 Maximum Allowable Power Range Neutron Flux 3/4 7-2 High Setpoint With Inoperable steamline Safety Valves During 3 Loop Operation 3.7-2 Maximum Allowable Power Range Neutron Flux 3/4 7-3 High Setpoint with Inoperable Steam Line Safety Valves During 2 Loop Operation 3.7-3 Steam Line Safety Valves Per Loop 3/4 7-4 4.7-1 Snubber Visual Inspection Interval 3/4 7-31 4.7-2 Secondary Coolant System Specific Activity 3/4 7-9 Sample and Analysis Program 3.8-1 Battery Surveillance Requirements 3/4 8-9a 3.9-1 Beaver Valley Fuel Assembly Minimum Burnup 3/4 9-15 vs. Initial U235 Enrichment For Storage in Region 2 Spent Fuel Racks BEAVER VALLEY - UNIT 1 XVIII Amendment No. 202

l DPR-66 Table Ind&x (cont.)

TABLE TITLE PAGE B 3/4.4-1 Reactor Vessel Toughness Data (unirradiated)

B 3/4 4-7 6.2-1 Minimum Shift Crew Composition 6-4 i

T i

f i

1 i

1 l

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BEAVER VALLEY - UNIT 1 XIX Amendment No. 202

= _ - -.

DPR-66 Flaura Indgx i

FIGURE TITLE PAGE 2.1-1 Reactor Core Safety Limit - Three Loop 2-2 Operation i

3.4-1 Dose Equivalent I-131 Primary Coolant 3/4 4-21 Specific Activity Limit Versus Percent of Rated Thermal Power with the Primary Coolant Specific Activity > 1.0 pCi/ gram Dose Equivalent I-131 3.4-2 Beaver Valley Unit 1 Reactor Coolant 3/4 4-24 System Heatup Limitations Applicable for the First 16.0 EFPY 3.4-3 Beaver Valley Unit 1 Reactor Coolant 3/4 4-25 System Cooldown Limitations Applicable for the First 16.0 EFPY 3.6-1 Maximum Allowable Primary Containment Air 3/4 6-7 Pressure Versus River Water Temperature B 3/4.2-1 Typical Indicated Axial Flux Difference B 3/4 2-3 Versus Thermal Power at BOL B 3/4.4-1 Fast Neutron Fluence (E>l Mev) as a B 3/4 4-6a Function of Full Power Service Life B 3/4.4-2 Effect of Fluence, Copper Content, and B 3/4 4-6b Phosphorus Content on ARTNDT for Reactor Vessel Steels per Reg. Guide 1.99 B 3/4.4-3 Isolated Loop Pressure-Temperature Limit B 3/4 4-10a Curve BEAVER VALLEY - UNIT 1 XX Amendment No. 202

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d DPR-66 5.0 DESIGN FEATURES 5.1 SITE LOCATION 1

i The Beaver Valley Power Station Unit No. 1 is located in Shippingport Borough, Beaver County, Pennsylvania, on the south bank of the Ohio i

River.

The site is approximately 1 mile southeast of Midland, Pennsylvania, 5 miles east of East Liverpool, Ohio, and approximately 25 miles northwest of Pittsburgh, Pennsylvania.

The exclusion area 1

5 boundary has a minimum radius of 2000 feet from the center of containment.

I I

i 5.2 REACTOR CORE i

5.2.1 FUEL ASSEMBLIES 2

The reactor shall contain 157 fuel assemblies.

Each assembly shall l

consist of a matrix of zircaloy clad fuul rods with an initial j

composition of natural or slightly enriched uranium dioxide (UO ) as 2

i fuel material.

Limited substitutions of zirconium alloy or stainless I

steel filler rods for fuel

rods, in accordance with approved i

applications of fuel rod configurations, may be used.

Fuel i

assemblies shall be limited to those fuel designs that have been i

analyzed with applicable NRC staff approved codes and methods and i

shown by tests or analyses to comply with all fuel safety design i

bases.

A limited number of lead test assemblies that have not l

completed representative testing may be placed in nonlimiting core j

regions.

i 5.2.2 CONTROL ROD ASSEMBLIES i

The reactor c o rra shall contain 48 full length and no part length control rod assemblies.

The full length control rod essemblies shall i

contain a noninal 142 inches of absorber material.

The nominal

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values of absorbor material shall be 80 percent silver, 15 percent indium and 5 peracnt cadmium.

All control rods shall be clad with d

stainless steel tubing.

5.3 FUEL STORAGE j

i 5.3.1 CRITICALITY l

5.3.1.1 The spent fuel storage racks are designed and shall be j

maintained with:

a.

Fuel assembli-having a maximum U-235 enrichment as set j

forth in Speniivation 3.9.14; i

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b.

K,gg $ O '. 9 5 if fully flooded with unborated water, which 2

includes an allowance for uncertainties as described in UFSAR Section 9.12;

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BEAVER VALLEY - UNIT 1 5-1 Amendment No. 202 l

i

DPR-66 DESIGN FEATURES J

l c.

A nominal center to center distance between fuel assemblits 4

placed in the fuel storage racks of 10.82 inch for Region 1, with 9.02 inch for Regions 2 and 3; d.

Fuel assembly storage shall comply with the requirements of Specification 3.9.14.

4 5.3.1.2 The new fuel storage racks are designed and shall be i

maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment of 4.5 i

weight percent; b.

K.gr 5 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in j

UFSAR Section 9.12; I

c.

K gg $ 0.95 if moderated by aqueous foam, which includes an allowance for uncertainties.as described in UFSAR Section i

9.12; i

i d.

A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

5.3.2 DRAINAGE 4

i The spent fuel storage pool is designed and shall be maintained to i

prevent inadvertent draining of the pool below elevation 750' - 10".

1 5.3.3 CAPACITY i

The fuel storage pool is designed and shall be maintained with a

]

storage capacity limited to no more than 1627 fuel assemblies.

4 2

BEAVER VALLEY - UNIT 1 5-2 Amendment No. 202

l W "*%,

UNITED STATES 5

NUCLEAR REGULATORY COMMISSION i

%,.....,,[

WASHINGTON, D.C. 20555 @ 01 DUOVESNE LIGHT COMPANY j

OHIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.83 License No. NPF-73 1.

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

A.

The application for amendment by Duquesne Light Company, et al. (the licensee) dated September 9, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

i

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-73 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 83, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLC0 shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

In addition, the license is amended to add paragraph 2.C.(11) to the Facility Operating License No. NPF-73 as follows:

(11) Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 83, are hereby incorporated into this license.

Duquesne Light Company shall operate the facility in accordance with the Additional Conditions.

3.

This license amendment is effective as of its date of issuance and the change to the facility shall be implemented within 60 days from the date of issuance.

Implementation of this amendment shall include the relocation of certain technical specification requirements to the appropriate licensee-controlled documents as described in the Licensee's application dated September 9, 1996, and evaluated in the staff's safety evaluation attached to this amendment.

FOR THE NUCLEAR REGULATORY COMMISSION y

John F. Stolz, Director Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:

1.

Page 5 to License

  • No. NPF-73 and page I to Appendix D of License

Changes to the Technical Specifications Date of Issuance: April 14, 1997

  • Page 5 of the license and page 1 of Appendix D are attached, for convenience, for the composite license to reflect this change.

1 l

i

AT TACHMENT TO LICENSE AMENDMENT NO.83 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 1.

Revise License as follows:

Remove Paae Insert Paae 5

5 2.

Insert page 1 of Appendix 0 of the License 3.

Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated.

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert XIII XIII XIV XIV XV XV XVI XVI 5-1 5-1 5-2 5-3 5-4 5-5 5-6 5-7 5-2

J

. i 1

(8) Detailed Control Room Desian Review (DCRDR)

Deleted j

(9) Safety Parameter Disolav System (SPDS)

Deleted (10)

Fire Protection Modifications (Section 9.5.1 of SER Suoolement 6) l Deleted l

(11) Additional Conditions The Additional Conditions contained in Appendix 0, as revised through Amendment No.83, are hereby incorporated into this licensee. Duquesne Light Company shall operate the facility in accordance with the Additional Co d itions.

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D.

Exemotions l

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 i

herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

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(1) The facility requires an exemption from the requirements of General Design Crite.rion (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 i

environmental assessment was published on March 27, 1987 (52 FR i

9979). Therefore, pursuant to 10 CFR 50.12(a)(1), 10 CFR l

50.12(a)(2)(ii) and (iv), Beaver Valley Power Station, Unit 2 is exempt from the requirements of GDC 4, Appendix A to 10 CFP. 50 i

with respect to the dynamic loading effects associated witn the i

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-4

. associated dynamic transients.

Specifically, this eliminates the need to install jet impingement barriers and pipe whip restraints associated with postulated pipe breaks in the pressurizer surge line, reactor coolant bypass system, BEAVER VALLEY - UNIT 2 Amendment No. 74,83 1

s

l APPENDIX D ADDITIONAL CONDITIONS OPERATING LICENSE NO. NPF-73 Duquesne Light Company, 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 The amendment Technical Specification requirements to shall be licensee-controlled documents.

Implementation implemented of this amendment she.l' include the relocation sithis. 60 days of these technical specification requirements from April 14, 1997 to the appropriate documents, as described in i

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

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l 1

Amendment No.83

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l-NPF-73 i

INDEX BASES SECTION PAGE 3/4.9.12 AND 3/4.9.13 FUEL BUILDING VENTILATION SYSTEM B 3/4 9-3

}

3/4.9.14 FUEL STORAGE - SPENT FUEL STORAGE POOL..

B 3/4 9-4 3/4.10 SPECIAL TEST EXCEPTIONS i

{

3/4.10.1 SNCTDOWN MARGIN.........................

B 3/4 10-1

}

3/4.10.2 GROUP HEIGHT, INSERTION AND POWER

{

DISTRIBUTION LIMITS.....................

B 3/4 10-1 3/4.10.3 PHYSICS TESTS...........................

B 3/4 10-1 l

3/4.10.4 REACTOR COOLANT LOOPS...................

B 3/4 10-1 1

l 3/4.10.5 POSITION INDICATION SYSTEM-SHUTDOWN.....

B 3/4 10-1 4

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS......

B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS.......................

B 3/4 11-1 3

-f 1

l DESIGN FEATURES

]

SECTION PAGE 4

4 5.1 SITE LOCATION...............,....................

5-1 5.2 RER Q' 3R CORE.....................................

5-1 5.3 FUEL STORAGE.....................................

5-1 ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY...................................

6-1 6.2 ORGANIZAT'lyR 6.2.1 ONSITF AND OFFSITE ORGANIZATIONS........

6-1 BEAVER VALLEY - UNIT 2 XIII Amendment No. 83

4 NPF-73 INDEX c

ADMINISTRATIVE CONTROLS SECTION PAGE 6.2.2 UNIT STAFF..............................

6-1 1

6.2.3 INDEPENDENT SAFETY EVALUATION GROUP (ISEG) 6-2 6.3 FACILITY STAFF OUALIFICATIONS....................

6-6 6.4 TRAINING 6-6 l

4 6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY COMMITTEE (OSC) -

j Function................................

6-d 6.5.1.1 6.5.1.2 Composition.............................

6-6 1

4 1

6.5.1.3 Alternates..............................

6-7 6.5.1.4 Meeting Frequency.......................

6-7 3

6.5.1.5 Quorum..................................

6-7 1

6.5.1.6 Responsibilities........................

6-7 1

6.5.1.7 Authority...............................

6-8 6.5.1.8 Records.................................

6-8 6.5.2 OFFSITE REVIEW COMMITTEE (ORC) 6.5.2.1 Function..,.............................

6-8 4

6.5.2.2 Composition.............................

6-9 6.5.2.3 Alternates..............................

6-9 6.5.2.4 Consultants.............................

6-9 6.5.2.5 Meeting Frequency.......................

6-9 6.5.2.6 Quorum..................................

6-9 6.5.2.7 Review..................................

6-9 BEL V VALLEY - UNIT 2 XIV Amendment No. 83

i NPF INDEX o

Q ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.2.8 Audits..................................

6-10 6.5.2.9 Authority...............................

6-11 6.5.2.10 Records.................................

6-11 6.6 REPORTABLE EVENT ACTION..........................

6-11

)

l 6.7 SAFETY LIMIT VIOLATION............................

6-12 6.8 PROCEDURES.......................................

6-12 6.9 REPORTING REOUIREMENTS 6.9.1 ROUTINE REPORTS.........................

6-16 6.9.1.1 Startup Reports.........................

6-16 6.9.1.4 Annual Reports..........................

6-17 6.9.1.6 Monthly Operating Report................

6-18 6.9.1.10 Annual Radiological Environmental Operating Report........................

6-19 6.9.1.11 Annual Radioactive Effluent Release i

Report..................................

6-19 6.9.1.12 Core Operating Limits Report............

6-19 6.9.2 SPECIAL REPORTS.........................

6-20 6.10 RECORD RETENTION................................

6-21 6.11 RADIATION PROTECTION PROGRAM....................

6-23 6.12 HIGH RADIATION AREA.............................

6-23 6.13 PROCESS CONTROL PROGRAM (PCEl...................

6-24 BEAVER VALLEY - UNIT 2 XV Amendment No. 83

NPF-73 n

INDEX ADMINISTRATIVE CONTROLS SECTION FAGtg C.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6-25 I

6.16 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT i

SYSTEMS (Licuid. Gaseous and Solid) 6-25 6.17 CONTAINMENT LEAKAGE RATE TESTING PROGRAM........

6-25 i

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l BEAVER VALLEY - UNIT 2 XVI An.wdment No. 83

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NPF-73 i

5.0 DESIGN FEATURES 11 SITE LOCATION j

j The Beaver Valley Power Station Unit No. 2 is located in Shippingport Borough, Beaver County, Pennsylvania, on the south bank of the Ohio River.

The site is approximately 1 mile southeast of Midland, Pennsylvania, 5 miles east of East Liverpool, Ohio, and approximately 25 miles northwest of Pittsburgh, Pennsylvania.

The exclusion area boundary has a minimum radius. of 2000 feet around the Unit No. 1 i

containment building.

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5.2 REACTOR CORE l

i 5.2.1 FUEL ASSEMBLIES The reactor shall contain 157 fuel assemblies.

Each assembly shall i

consist of a matrix of Zircaloy or ZIRLO fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO ) as 2

fuel material.

Limited substitutiors of zirconium alloy or stainless steel filler rods for fuel ree,

in accordance with approved j

applications of fuel rod cea.igurations, may be used.

Fuel 1

assemblies shall be limited to those fuel designs that have been j

analyzed with -applicable NRC staff approved codes and methods and i

shown by tests or analyses to comply -with all fuel safety design i

bases.

A liinited number of lead test assemblies that have not i

completed representative testing may be placed in nonlimiting core regions.

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5.2.2 CONTROL ROD ASSEMBLIES b

i The reactor core shall contain 48 full length and no part length j

control rod assemblies.

The full length control rod assemblies shall j

contain a nominal 142 inches of absorber material.

The nominal i

values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium.

All control rods shall be clad with i

stainless steel tubing.

5.3 FUEL STORAGE 5.3.1 CRITICALITY 5.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment as set forth in Specification 3.9.14; b.

K.gf 5 0.95 if fully flooded with unborated water, which includes an allowance for uncertaintjes as described in UFSAR Section 9.1; BEAVER VALLEY - UNIT 2 5-1 Amendment No. 83 4

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NPF-73 j

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5.0 DESIGN FEATURES

\\

i c.

A minimum center to center distance between fuel assemblies I

placed in the fuel storage racks of 10.4375 inches; d.

Fuel assembly storage shall comply with the requirements of Specification 3.9.14.

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5.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment of 4.85 weight percent; b.

K.gr 5 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in UFSAR Section 9.1; l

c.

K,gg $ 0.95 if moderated by aqueous foam, which includes an i

allowance for uncertainties as described in UFSAR Section l

9.1; t

5 d.

A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

j 5.3.2 DRAINAGE I

j The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 751'-3".

5.3.3 CAPACITY The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1088 fuel assemblies.

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BEAVER VALLEY - UNI'r 2 5-2 Amendment No. 83 N

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