ML20062F357
| ML20062F357 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/30/1978 |
| From: | Grimes B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20062F360 | List: |
| References | |
| NUDOCS 7812180105 | |
| Download: ML20062F357 (12) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION s
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS C0b9ANY OELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY l
DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT HO. 2 kMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. OPR-44 1.
The Nuclear Regulatory Commission (the Comraission) has found that:
A.
The applications for amendment by Philadelphia Electric Company, et al. (the licensee) dated January 18, April 12. May 19, i
June 12, and September 19, 1978, comply with the standards and requirements of the Atomic Energy /,;L of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, tha provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations and all applicable requirements have been satisfied.
7812180105
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i 2.
Accordingly, the license is amended by char.ges to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 49, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION s
I Brian K. Grimes, Assistant Director
, for Engineering and Projects Division of Operating Reactors
Attachment:
Changes to the. Technical Specifications Date of Issuance: November 30, 1978 r
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i ATTACHMENT TO LICENSE AMENDMENT NO. 49 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET N0. 50-277 Replace the following pages of the Appendix "A" Technical Specifications 4
with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 11 11 228 228 241 241 l
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o PBAPS - 2 l
TABLE OF CONTENTS (Cont'd.)
Pace No.
i I
SURVEILLANCE
- J LIMITING CC"DITIONS FOR OPERATION REQUIREMENTS 3.6 PRIMARY SYSTEM BCUNDARY 4.6 143 A.
Thermal and Pressurization Limitations A
143
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B.
Ccolant Chemistry B
115 C.
Ccolant Leakage C
146 D.
Safety and ' Relief Valves D
147 E
148.
E.
Jet Pumps F.
Jet Pump Ficw Mismatch F
148 G.
Structural Integrity G
149 37 CONTAINMENT SYSTEMS 4.7 165 A.
Primarf Containment A
165 B.
Standby Gas Treatment System B
175 C.. Secondarf Containment C
176 D.
Primary Containment Isolation valves D
177 3.8 RADICACTIVE MATEaIALS 4.8 203 A.
General A
203 B.
Liquid Ef fluents B
204 C.
Airborne Ef fluents C
206 D
Mechanical Vacuum Pump D
209 3.9 AUXILIARY ELECTRICAL SYSTEMS 4.9 217 A.
Auxiliary Electrical Equipment A
217 B.
Operation with Incperable Equipment B
219 C.
Erwargency Service Water Sys tem C
221 3.10 CORE 4.10 225 A.
Refueling Interlocks A
225 3.
Core Monitoring B
227 C.
Spent Fuci Pool Water Level C
228 D.
Heavy Loads Over Spent Fuel D
228 E
Spent feel Decay Time E
228 3.11 ADDITICNAL SAFETY RELATED PLANT CAPABILITIES 4.11 233' A.
Main Control Recm Ventilation A
233 B.
Alternate E::at Sink Facility B
214 C.
Imcrgency Shutdown Centrol Panel C
234 3.12 RIVER LEVEL 4.12 237 A.
High alver U.dwr Level A
237 B.
Lcu River Wctor Level B
237 C.
Lovel Instrumentation C
238 3.13 MISCELLANEOUS RADICACTIV2 MATERIALS SOURCES 4.13 240a Amendment No.[ 49.
PBAPS r
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.10.B (Cont ' d. )
4.10.B (Cont'd.)
1.
The SRM shall be inserted to the normal operating level.
(Use of special moveable, dunking type detectors during initial fuel loading and major core altera-tions in place of normal detec-tors is permissible as long as the detector is connected to the normal SRM circuit.)
2.
The SRM shall have a minimum of 3 cps with all rods fully in-sorted in the core.
C. Spent Fuel Pool Water Level C. Spent Fuel Pool Water Level Whenever irradiated fuel is stored Whenever irradiated fuel is in the spent fuel pool, the pool stored in the spent fuel pool, water level shall be maintained at the water level shall be or above 81/2' above the top of the recorded daily.
fue1.
D.
Heavy Loads Over Spent Fuel Loads in excess of 1000 lbs (excluding the rigging and transport vehicle) shall be prohibited from travel over fuel assemblies in the spent fuel storage pool.
E.
Spent Fuel Decay Time E.
Spent Fuel Decay Time The reactor shall be suberitical for The reactor shall be determined to at least 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> prior to movement have been subcritical for at least of fuel elements from the reactor 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> by verification of the vessel to the spent fuel pool, date and time of subcriticality prior to movement of irradiated fuel from the reactor vessel to the spent fuel pool.
2
' Amendment No. 49
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PBAPS Unit 2 5.0 PATOR DESIGN FEATUFIS
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5.1 SITE FEATURES j
'rhe site is located partly in Peach Bottom Township, York County, partly in Drumore Township, Lancaster County, and partly in Fulton Township, Lancaster County, in southeastern Pennsylvania on the westerly shore of Conowingo Pond at the mouth of Rock Run Creek.
It is about 38 miles north-northeast of Baltimore, Faryland, and 63 miles west-southwest of Philadelphia, Pennsylvania.
Figures 2.2.1 through 2.2.4 of the FSAR show the site location with respect to surrounding communities.
5.2 REACTOR A.
The core shall consist of not more than 764 fuel assemblies.
' 7 x 7 fuel asserblies shall contain 49 fuel rods and 8 x 8 fuel asserblies shall contain 62 or 63 fuel rods.
B.
The reactor core shall contain 185 cruciforn-shaped control rods.
The control material shall be boron carbide powder (B C) compacted to approximately 701t of the theoretical 4
density.
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5.3 REACTOR VESSEL The reactor vessel shall be as described in Table 4.2.2 of the FSAR.
The applicable design codes shall be as described in Table 4.2.1 of the FSAR.
5.4 CONTAI!U'ENT A.
The principal design parameters for the primary containment shall be as given in Table 5.2.1 of the FSAR.
The applicable design codes shall be as described in Appendix M of the FSAR.
B.
The secondary containrent shall be as described in Section 5.3 of the FSAR.
C.
Penetrations to the primary containment and piping passinct through such penetrations shall be desianed in accordance with standards set forth in Section 5.2.3.4 of the FSAR.
5.5 FUEL STORAGE I
A.
The new fuel storace facility shall be such that the K,ff dry is less than 0.90 and flooded is less than 0.95.
B.
The Keff of the spent fuel storage pool shall be less than or equal to 0.95.
C.
Spent fuel shall only be stored in the. spent fuel pool in a vertical orientation in approved storage racks.
D.
The average fuel assembly loading shall not exceed 17.3 grams U-235 per axial centimeter of total active fuel height of the assembly.
Amendment No.g 49
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UMTED STATES NUCLEAR REGULATORY COMMISSION g
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PHILADELPMIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50 278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. OPR.56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Philadelphia Electric Company, et al. (the licensee) dated January 18, April 12 May 19 June 12, and September 19, 1978, comply 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; 8.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; i
C.
There is reasonable assurance (f) 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 Commission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this ifcense amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 48, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION s
Brian K. Grimes, Assistant Director for Engineering and Projects Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: November 30, 1978 e
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I ATTACHMENT TO LICENSE AMENDMENT NO. 48 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
i 1
Remove Insert 11 11 l
228 228 242 242 t
9 T
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PBAPS - 3 TABLE OF CONTENTS (Cont'd.)
Pace No.
SURVIILLANCE LIMITING CONDITIONS FOR OPERATION REQUIRE CNTS 3.6 PRIMARY SYSTEM BCUNDARY 4.6 143 A.
Thermal and Pressurizaticn Limitations A
143 B.
Ccolant chemistry B
115 i
C.
Ccolant Leakage C
146 D.
Safety and Relief Valves D
147 i
E.
Jet Pumps E
148
[
F.
Jet Pump Flcw Mismatch F
148 G.
Structural Integrity G
'149 3.7 CONTAINMENT SYSTEMS 4.7 165 i
A.
165 B.
Standby Gas Treatment System B
175 C.
Secondarr Containment C
176 D.
Primary Containment Isolation Valves D
177 3.8 RADICACTIVE MATE 3IALS 4.8 203
[
A.
General A
203 B.
Liquid Ef fluents B
204 C.
Airborne Ef fluents C
206 D
Mcchanical Vacuum Pump D
209
[
3.9 AUXILIARY ELECTRICAL SYSTEMS 4.9 217 t
A 217 A.
Auxiliar( Electrical Equipment B.
Operaticn with Incperi.ble Equipment 3
219 t
C.
Em>2rgency Service Water Syste C
221 3.10 CORE 4.10 225 1
A.
Refueling Intei, locks A
225 i
B.
Core Monitoring B
227 C.
Spent Fuci Pool Water Level C
228 D.
Heavy Loads Over Spent Fuel D
228 E.
Soent Fuel Decay Time E
228 3.11 KDDITICNAL SAFETY rLATED PLANT CAPABILITIES 4.11 231-
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A.
Main Control Recm Ventilation A
233 l
B.
. Alternate H::a Sink Facility 9
214 j
C.
Emergency Shutdown Centrol Panel 0
234 3
3.12 RIVER LEVEL 4.12 237 I
237 A.
High River Unter Level A
B.
Lcu River Wats: Level 3
237 C.
Icvc1 Instrumentation C
238 3.13 MISCELLGEOUS RADICACTIVE MATERIALS SOURCES 4.13 240a Amendment No.
48 ;
1 l
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS j
3.10.B (Cont' d.)
4.10.B (Cont'd.)
1.
The SRM shall be inserted to the normal operating level.
(Use of special moveable, dunking type detectors during initial fuel loading and major core altera-tions in place of normal detec-tors is permissible as long as
.the detector is connected to the normal SRM circuit.)
2.
The SRM shall have a minimum of 3 cps with all rods fully in-serted in the core.
C. Spent Fuel Pool Water Level C. Spent Fuel Pool Water Level I
Whenever irradiated fuel is stored Whenever irradiated fuel is in the spent fuel pool, the pool stored in the spent fuel pool, water level shall be maintained at the water leve'l shall be or above 81/2' above the top of the recorded daily, f ue 1.
D.
Heavy Loads Over Spent Fuel Loads in excess of 1000 lbs (excluding the rigging and transport vehicle) shall be prohibited from travel over fuel assemblies in the spent fuel storage pool.
^
E.
Spent Fuel Decay Time E. Spent Fuel Decay Time t
The reactor shall' be subcritical for The reactor shall be determined to at least 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> p'rior to movement have been subcritical for at least of fuel elements from the reactor 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> by verification of the vessel to the spent fuel nool, date and time of subcriticality prior to movement of irradiated j
fuel from the reactor vessel to the spent fuel pool.
Amendment No. 48
-228-e
e PBAPS Unit 3 a
5.5 FUEL STORAGE 4
A.
The new fuel storage facility shall be such that the K,gg dry is less than 0.90 and flooded.is less than 0.95.
B.
The Keff of the spent fuel storage pool shall be less than or equal to 0.95.
C.
Spent fuel shall enly be stored in the spent fuel pool in a vertical orientation in approved storage ra:ks.
D.
The average fuel assembly loading shall not exceed 17.3 grams U-235 per axial centimeter of' total active fuel height of the assembly.
5.6 SEISMIC DESIGN The station Class I structures and systems have been designed for ground accelerations of 0.05g (design earthquake) and 0.12g (maximum credible earthquake).
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Amendment No.
48
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