ML19225B400
| ML19225B400 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/15/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19225B401 | List: |
| References | |
| NUDOCS 7907250110 | |
| Download: ML19225B400 (18) | |
Text
f' umino stavas NUCLEAR REGULATORY CCMMISSION y
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT H0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. DPR-44 The Nuclea-Regulatory Commission (the Commission) has found that:
1.
The application for amendment by Philadelphia Electric Company A.
et al., (the licensee) dated January 12, 1979, 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; B.
The facility will operate in conformity with the application, the 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 heal th and safety of the public, and (ii) that such activities will be conducted in compiiance 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 witn 10 CFR Par?
51 of the Commission's regulations and all applicable requirments have been sati sfied.
417 141 vternre11$
Accordingly, the license is amended by enanges to the Technical Specifications as indicated in the attachment to this license 2.
amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through knendment No. 55, are The licensee hereby incorporated in the license.
shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of its issuance, 3.
FOR THE NUCLEAR REGULATORY COMMISSION
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omas A.
polito, Chief Operating Reactors Branch f3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: June 15,1979 417 142
ATTACHMENT TO LICENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE NO. OPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix "A" Technical Specifications with the The revised pages are identified by Amendment number and contain enclosed pages.
vertical lines indicating the area of change.
Insert Remove 127 127 234k 234k 2341 2341 234m 234m 234n 234n 251 251
YBAPS UnLL MM_!T!N_G _ Cps _otrionS, FOR OPERATI,0N SURVE1L1.ANCE REQUIREM).NTS 3.5.A Core Spray and LPCI, 4.5. A core._ Spray and LPCI Subsystem (cont'd)
Sutpystem (cont'd)
- 6. All recirculation pump discharge
- 6. All recirculation purep discharge valves shall be operable prior to valves shall be tested f or reactor startup (or closed if operabilty during any period permitted elsewhere in these of reactor cold shutdown exceeding specifications).
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if operability tests have not been performed during the preceding 31 days.
- 7. If the requir u nts of 3.5.A cannot be me t, an ordarly shutdown of the reactor shall be initiated and the reactor shall be in the Cold Shutdown Condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
B. Containment C_ool,ing B._ Containment Cooling Subsysten (HPSW)
S,ubsysten,(HPSW)_.
- 1. Except as specified in 3.5.B.2,
- 1. Containment Cooling Subsystem 3.5.B.3, 3.5.B.4, and 3.5.F.3 Testing shall be as follows:
below, all containment cooling subsystem loops shali be operable Iten Frequency whenover irradiated f uel is in the J
reactor vessel and reactor coolant (a)
Pump Once/ month temperature is greater than 212*F, Operability and prior to reactor startup f rom a Cold Shutdown Condition.
(b)
Motor operated Once/ month valve operability (c)
Pump Capacity After pump Test. Each HPSW ma inte nance pump shall and every deliver 4500 3 months.
gpa at 233 psig.
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(d)
Air test on once/5 years I
f drywell and torus headers and noszles.
- 2. From and af ter the date that any two
- 2. When it is determined that any two HPSW pumps are made or f ound to be HPSW pumps are inoperable, the inoperable f or any reason, continued remaining components of the reactor operation is permissible only containment cooling subsys: ems shall during the succeeding thirty days, be demonstrated to be operable unless such pump is soor.er made imamdiately and weekly thereaf ter.
operable, provided that during such thirty days all active components of the containment cooling subsystem are p
- I,i operable.
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_ _. _ _ _ _. No. 23_, 3_2, 47, 55 4._.
u Amendment
PSAPS Unit 2 TABLE 3.!!.D.1 (Cont'd)
S_a_fe_ty Related Shock Suppressor,s_,(Soubbe_r_s)
SNUBBERS SNUBBERS SNUHKEMS SNUBBER IN HIGH(1)
ESPECIA:.LY INACCESSitiL6 4CCESSi tile SNUBBER RADIATION AREA DIFFICULT DURING NORMAL DURING NORMAL NlgiBER_,,
, LOf *]T_M
_ FI FVATJnN.
FWIRING SHUTDOWN TO REMOVE OPERATION OPERATIGN 10-CR-S-12 RHR 98 See 4.11.D.4.b
10-C8-S-43-1 RHR 130 X
TORUS RM.
4 LD 10-GB-S-43-2 RilR 130 X
TORUS RH.
10-CB-S-44 RHR 128 X
TURUS RM.
~
124
10-CB-S-48 RilR 10-CB-S-49 RHR 124 s.
7 10-CB-S-50 RHR 98
)
10-CB-S-51 RHR 98
(r 10-CH-S-52 RHR 124 lO-GB-S-53 RHR 124 ge 9
1-10-CB-S-54 RHR 130 X
TORUS RH.
10-CB-S-55 RHR 130 X
10-CB-S-58 RHR 98
4-,
g 10-DCN-S-73 RHR 180 X
Drywell g::%LTM 10-DCN-S-74 RHR IMU X
Drywell rnz 2D r
Ame ndment No. 33, 55
PBAPS Unit 2 TABLE 3.II.D.1 (Cont'd)
Saf_e_ty_ Relate:1 Shock Suppreesors (Snubbers)
SNUBBERS SNUBBERS SNUBBERS SHUBBER IN ti1GH(!)
ESPECIALLY INACCESSIBLE
< P.ESSIBLE SNUBBER RADIATION AREA DIFFIQJLT DURINC NORMAL DUL.VC NORMAL OP_ LT.T1_0N N_L_rH_B E R, _
_,,L_,OC_A_T I_0 N ELEVATION _ _ _DURING SHUTDOWN _, TO REMOVE _. ____ OPERATION 7
10-CB-S-77 RHR 102 See 4.11.D.4.b
N 10-CB-S-76 EllR 102
~
10-CB-S-75 RHR 93 10-CB-S-80 RHR 102
'D'RHR KH.
~
~
10-C B-S-7 9 Ri(R 102
~
10-CB-S-78 RHR 93 I
12-DCh-S- 2 RWCU 17 3.5 X
RWCU ISOLATION
~
VALVE RM. 165 P
12-DCN-S-5 R.JCU 165 X
Drywell 12-DCN-S-7 RWCU 165 X
Drywell
~
12-DCF-S-8A RWCU 162 Drywell l
~
14-DCN-S-23 CORE SPRAY 168 X
Drywell
~
14-DCN-S-24 CORE SERAY 168 X
Drywell
~
N" 14-DCN-S-26 CORE SPRAY 168 X
Drywell 14-DCN-S-27 CORE SPRAY 168 X
Drywell 2ap g
Amendraent No. 33, 55
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PBAPS 6.5.2.7 Continued d.
Proposed changes in Technical Specifications or Licenses.
Violations of applicable statutues, codes, e.
regulations, orders, Technical specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnormalities or deviations frca normal and expected performance of plant equipment that affect nuclear safety.
All events which are required by regulations or g.
Technical Specifications to be reported to the NRC in writing within 24 bours.
h.
Any indication of an unanticipated deficiency in some aspect of design or operation of safety related structures, systema, or components.
1.
Reports and neeting r.dAutos of the Plant Operation Review Coctaittee.
Audits 6.5.2.8 Audits of facility activitie s shall be performed under the cognizance of the OSR Committee.' These audits shall encompass:
The conformance of facility operation to provisions l
a.
contained within the Technical Specifications and applicable license conditions at least once per year.
b.
The performance, training and qualifications of the entire facility staff at least once per year.
The rer.alts of ' actions taken to correct I
c.
deficiencies occuring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.
d.
The performance of activities required by the l
( uality Assurance Program to meet the criteria of
-0 CFR 50, Appendix B, at least once per two years.
g hp Amendment No. J7, 55
-251-an'o ra 417 149
UNITE D 5TATES
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HUcLEAR HEGULATOi4Y CCMM;tSION
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o PHILADELPHI A ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS C0fPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PE{CH BOTTCM ATOMIC POWER STATION, UNIT NO. 3 E
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License NL DPR-Sti 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al., (the licensee) dated January 12, 1979, 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; B.
The facility will operate in confomity with the application, the 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.
Qf 3
AU 150 wa 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-56 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained ir. Appendices A and B, as revised through Amendment No. 55, are hereby incorporated in the If cense.
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 h
J.)
omas A.
ppolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specificatiens Date of Issuance: June 15,1979 417 151
ATTACHMENT TO LICENSE AMENDMENT N0. 55 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET N0. 50-278 Replace the folloring pages of the Appendix "A" Technical Specifications with the enclosed pages. 1he revised pages are identified by Amendment number and contain vertical lines inc icating the area of change.
Insert Remove _
127 127 251 251 i
417 152
PBAPS Unit 1 LIMITING CONDITIONS FOR OPERATION SUtVEILLANCE REQUIREMENTS 3.5.A Core,Sgral,and _LPCI_
4.5. A C_oreAray, a_nd, LP,C,I Subsystem (cont'd)
Subsystep,(cont'd)
- 6. All recirculation pump discharge
- 6. All recirculation pump discharge valves and bypass valve (s)[*] shall valves and bypass valve (s)[*] shall be operable prior to reactor startup be tested f or operability during any (or closed if permitted elsewhere period of reactor cold shutdown in these specifications).
exceeding 48 hou rs, if operability tests have not been perf ormed during the preceding 31 days.
- 7. If the requirements of 3.5.A cannot be met, an orderly shutdown of the reactor shall be initiated and the reactor shall be in the Cold Shutdown Condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
B. Containment Coolin3 B. Containment _ Cooling Subsystes (HPSW)
Su,bsystem (HPSW)
- 1. Except as specified in 3.5.8.2,
- 1. Containment Cooling Subsystem 3.5.B.3, 3.5.B.4, and 3.5.F.3 Testing shall be as follows:
below, all containment cooling subsystem loops shall be operable Item F_regue_ncy whenever irradiated fuel is in the I
reactos vess'el and reactor coolant (a)
Punp Once/montti temperature is greater than 212 F, Opera bility and prior to reactor s tartup f rom a Cold Shutdown Ccndition.
Motor operated once/ month valve operability (c)
Punp Capacity After pump Test. Each HPSW maintenance pump shall and every deliver 4500 3 months.
8Pm at 233 paig.
4}f
] (d) Air test on Once/5 years drywell and torus headers and nozzles.
- 2. From and af ter the date that any two
- 2. When 1; is determined that any two itPSW pumps are sade or f ound to be HPSW pumps are inoperable, the inoperable f or any reason, continued remaintag components of the reactor operation is permissible only containment cooling subsystems shall during the succeeding thirty days, be demonstrated to be operable unless such pump is sooner made immediately and weekly thereaf ter.
operable, provided that during such thirty days all. active ccaponents of
- Upon.he removal of both recirculation the containment cooling subsystem are pump discharge valve bypass valve s,
operable. operability and surveillance of unly the c'ecirculation pump discharge valves is requir2d. Amendme nt No. 27, 31, 47, 55 -127-
PBAPS 6.5.2.7 Conti7ued d. Proposed changes in Technical Specifications or Licences. Violatio2s of applicable statutues, codes, e. regulations, orders, Technical Specifications, license requirements, or of internal procedures or lnatructions having nuclear safety significance, Significant operating abnormalities or deviations f. fraca normal and expected performance of plant equips:ent tint affect nuclear safety. All evonts wnics are required by regulations or g. Technical Specifications to be reported to the NRC in writing within 24 hours. Any indication of an unanticipated deficiency in h. some aspect of denign or operation of safety related structures, systems, or corponents. Reports and meeting minutes of the Plant Operation 1. Review Cos:mittee. Audits 6.5.2.8 Audit s of facility activities shall be performed under the c ognizance of the OSR Coctaittee." These audits shall encos: pass: The conformar.ce of f acility operation to provisions l a. contained within the Technical Specifications and applicable license conditions at least once per year. b. The performance, training and qualifications of the entire facility staff at least once per year. I The results of actions taken to correct c. deficiencies occuring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months. l d. The performance of activities required by the Quality Assurance Program to meet the criteria of 10 CFR 50, Appendix B, at least once per two years. Amendment No. J7, 55 -251-g - *h 417 154
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