ML19209B315
| ML19209B315 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/20/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19209B316 | List: |
| References | |
| NUDOCS 7910090498 | |
| Download: ML19209B315 (12) | |
Text
.
f UNITED STATES y '-
4 NUCLEAR REGULATORY COMMISSION j%[D ( j WASHINGTON, D. C. 20555 N,.
s, s 7 e/
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC CCMPANY DOCKET NO. 50-2 77 PEACH SOTTOM ATCMIC POWER STATION. UNIT NO. 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 61 License No. DPR 44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Philadelphia Electric Company et al. (the licensee) dated May 8 and August 21, 1979, 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; 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) tnat the activities authorized by thi5 amendment can De 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 oublic; and E.
The issuance of this amencment is in accordance with 10 CFR ? art 51 of tne Commission's regulations ano all acolicable requirements have been sati sfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, ana paragraph 2.C(2) of Facility Operating License No. OPR-44 is hereby amended to read as follows:
(2) Technical Soecifications lll2 llb The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 61, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the 7 910 0 9 0 4_ccp Technical Specifications.
W'
. 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
f Thomas A. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: September 20, 1979 1ii2 117
ATTACHMENT TO LICENSE AMENDMENT NO. 61 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 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.
Remove Insert 180 180 245 245 246 246 1112 118
TAHLE 3'.7.1 (Cont'd.)
PRIMARY CONTAINMENT ISOLATION VALVES Hundie r o t Power Maximum Action on Operated Valves Operating Normal Initiating Group Valve Identification Inboard Outboard Time (sec. )
Position Signal NA Feedwater check valves 2*
2*
NA 0
Process NA Control rod hydraulic return
[1*]#
[1*]#
NA C
Process check valves NA Control rod hydraulic return
[l*]##
NA C
Loe.ed valve closed f
14 NA 0
GC Oxygen Analyzer System 3
I NA Standby liquid control system 1*
1*
NA C
Process 7--
check valves rV 2B RIIRS shutdown cooling suction 1
1 32 C
SC isolation valves 2B Rl!RS shutdown cooling injec-1 24 C
SC tion isolation valves 20 Rl!RS Reactor Vessel llead Spray 1
1 30 C
SC y
isolation valves 2C Feo' water Flush Valves 2
50 C
SC 4
l' iS steam line isolation 1
1 20 0
GC valves S
5 RCICS steam line isolation 1
1 15 0
GC E
valves a
2A Reactor water cleanup system 1
1 30 '
0 GC isolation valves z
2A Reactor water cleanup system 1
20 0
GC return isolation valve cn
- Valves not power operated.
- Deleted after CRD RL is. cut and capped l
lI Superintendent SIO* #
l (I
Anat. Superintendent SID*
l N
I l
1 Operationn Fngineer (SID)
Clerical Engineer Technical (SID)
Engineer Maintenance M
-Security Ibree
- Engineer Reactor
-fiaintenance l
- Engineer I & C (and/or Resulto) l m
- Engineer Health Physion
~ Custodial
- Engineer Chemistry
- Stores l
1/S fih!fL Supt. (SID) a *
- Engineero
- pyjn,
- Technicians LEE 8 1/S Shift Supr. (SIO) *
- N 1
At lenot one of these shall be licensed.
1/S Control Op. Nuclear (IO)
Only one of these need to be licensad 2/S Annt. Cont. Op. Nuclear (ID) g during a training and qualification 1/S Plant Op.
period provided a second SID is available on site.
1/3 Aos L. Plan t Op.
l X/S - Number of men per ehlf t.
All shift 1/S Aux. Op.
Positiono are marked.
ID
' NRC Licensed Operator SID - NRC Licensed Senior Operator
- Renponalble for onsite fire protection activities r
ORGANIZATION JVR CONDUCT OF PLAff? OPERATIONS-N CD Figure 6.2-2
.e PBAPS Of)ft Q
' l[
3 U!1 UIk i
iBifb-6.3 Facility Sta ff Qualifications 6.3.1 Each member of the facility staf f shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Engineer-Health Physics who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
6.4 Training 5.4.1 A retraining and replacement training program for tne facility staff, shall be maintained under the direction of the Station Superintendent and shall meet the requirements of Section 5.5 of ANSI N18.1-1971 and 10 C.?R 55, Appendix A.
6.4.2 A training program for the Fire Brigade shall be conducted such that Fire Brigade members complete an Instruction program within a two year period.
Regularly planned meetings will be held every 3 months.
6.5 Review and Audit 6.5.1 Plant oeeration Review committee (Poac)
Function 6.5.1.1 The Plant Operation Review Comalttee shall f unction to advise the Station Superintendent on all matters related to nuclear saf ety.
comonsition
- 6. 5.1. 2 The Plant operation Review Committee shall ce composed of the:
Station Superintendent-Chairman Station Assistant Superintendent Engineer - Technical Engineer - Maintenance Engineer - Operations Engineer - Results Engineer - Reactor Engineer - Instrument & Control Engineer - Health Physics 1
Engineer - Chemistry l
Shift Superintendent Alternates
.. $.1. 3 niternate me=cers shall be appointed in writing ty the PC2C Chairman to serve on a camporary rasis; however, no more than two alternaces shall participate in PCEC activities at any one time.
.;mnam=r.c :u. 22, ;456 1112 121
-:"6-
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UNITED STATES
[
,:. N p.
NUCLEAR REGULATORY COMMISSION j
(
WASHINGTON, D. C. 20555 e....j PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS C0f4PANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, Uf1IT NO. 3 AMENDf9ENT TO FACILITY OPERATING LICENSE Amendment No. 61 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 May 8 and August 21, 1979, comply 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 reasonaDie assucance (i) tnat the activities authorizec by this amendment can be conduc :ed without endangering the health and safety o ~ the cualic, and (ii) that such activities sill De conducted in compliai:ce with the Commission's regulations; D.
The issuance of this _aendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of triis amendment is in accorcance with 10 CFR Part 51 of tne Commission's regulations and all apolicacle recuirements have been sati sfied.
2.
Accordingly, the license is amended by ch.nges to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. OPR-56 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 61, are hereby incorporated in the license.
The licensee j4I I /-
- 22-4 q shall operate the facility in accordance with the i
Technical Specifications.
. 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/?
Thomas
/Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 20, 1979 1112 123
ATTACHMENT TO LICENSE AMENDMENT NO. 61 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.
Remove Insert 18J 180 245 245 246 246 1112 124
TisHLE 3.7.1 (Coni'd.)
PRIMARY CONTAINMENT ISOLATION VALVES IIniiGief of Power flaximum Action on Operated Valves Operating Normal Initiating Group Valve Identification Inboard Outboard Time (sec.)
Position Signal NA Feedwater check valves 2*
2*
NA 0
Process NA Control rod hydraulic return
[l*]#
[l*]#
NA C
Process check valves NA Control rod hydrauli return
[l*]##
NA C
Locked valve Closed l
Oxygen Analyzer System 14 NA 0
GC
", 3 Is1 NA Standby liquid control system 1*
1*
UA C
Process check valves rs)
'J' 2 B RIIRS shutdown cooling suction 1
1 32 C
SC isolation valves 2B RilRS shutdown cooling injec-1 24 C
SC tion isolation valves s
2D Rl!RS Reactor Vessel llead Spray 1
1 30 C
SC y
isolation valves 2C Feedwater Flush Valves 2
50 C
SC 4
IIPCIS steam 11.ie isolation 1
1 20 0
GC valves k
5 RCICS steam line isolation 1
1 15 0
GC valves u
E 2A Reactor water cleanup system 1
1 30 0
GC isolation valves z
2A Reactor water cleanup system 1
20 0
}$
return isolation valve
- Valves not power operated.
- Deleted after CRD RL is cut and capped
{
lI Superintendent SID* #
l
{
Aset. Superintendent SIO*
- -?
I-l l
l Operationn Digineer (SID)
Cle Engineer Technical (SID)
Pngineer Maintenance L
rical Security Farce
- Engineer Reactor
-tisintenance
- Engineer.I & C (and/or Resulte) cn
- Fngineer Health Physion
~ Custodial
- Engineer Chemietry
- Storee 1/S Shift Supt. (SIO)**
- Engineere pygg
- Technicians 1/S Shi f t Supr. (SIO)**
I'EE '
N I
d' At least one of these shall be licensed.
1/S Control Op. Fluclear (IO) l
- - Only one of theee need to be licensed 2/S Annt. Cont. Op. !?uclear (ID) g during a training and qualification 1/S Plant Op.
peri d provided a second SIO la available on cite.
l/S Aprt. Plant Op.
'l X/S - Number of men per shift. All shift 1/S Atix. Op.
Positions are marked.
ID
' NRC Licenced Operator SID - NRC Licensed Senior Operator Responalble for onsite fire protection activities m
N ORGANIZATION JVR CONDUCT OF PLAFTP OPERATIOllS.
N Figure 6.2-2 i
PBAPS 6.3 Facility Sta ff Oualifications 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for tne Engineer-Health Physics who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
6.4 Training 6.4.1 A retraining and replacement training program for tne facility staff shall be maintained under the direction of the Station Superintendent and shall meet the requirements of Section 5.5 of ANSI N18.1-1971 and 10 CFR 55, Appendix A.
6.4.2 A training program for the Fire Brigade shall be conducted such that Fire Brigade members completc an instruction program within a two year period.
Regularly planned meetings will be held every 3 months.
- 6. 5 Review and Audit 6.5.1 Plant oceration Review committee (PORC)
Function 6.5.1.1 The Plant Operation Review Committee shall f unction to advise the Station Superintendent on all matters related to nuclear saf ety.
Comoosition 6.5.1.2 The Plant Operation Review Committee shall ce composed of the:
Station Superintendent-Chairman Station Assistant Superintendent Engineer - Technical Engineer - Maintenance Engineer - Operations Engineer - Results Engineer - Reactor Engineer - Instrument & Control Engineer - Health Physics Engineer - Chemistry i
Sh12t Superintendent Alternates
- u. 5.1. 3 Alternate memoers shall be appointed in writing ty the PC2C Chuirman to serve on a comporary rasis; nowever, no more than two alternaces shall participate in PORC activities at any one time.
1112 127 22,je',e,
. aenam :.t 20.
-;eo-
.