ML19209B172
| ML19209B172 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/19/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19209B173 | List: |
| References | |
| NUDOCS 7910090273 | |
| Download: ML19209B172 (10) | |
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(o, UNITED STATES y 3,,-
i NUCLEAR REGULATORY COMMISSION WA$mNGTON, D. C. 20555 gv j-PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND U GHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al., (the licensee) dated April 14, 1978 with supplemental information dated November 18,1977, June 22 and August 27, 1979, 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 Chapte,r I; B.
The facility will operate in confamity with the applicatien, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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 com:non defense and security or to the nealth and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Pas t 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the liu.'.ise is amended by changes to the Technical Spec-ifications as indicated in the attachment to this licente amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
(2) The Technical Specificctions contained in Appencices A and B, as revised through Amendment No.60, are hereby incorporated in the license. The licensee shall operatt:
the facility in accordance witn tne Technical Specifications.
1113 N 0 7 010 0 90Z7}d
. 3.
This license amend:..ent is effect'v2 as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Tho:$"as K.dppolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technica'.
Specifications Date of Issuance:
September 19, 1979 1113 Del
ATTACHMENT TO LICENSE AMENDMENT NO. 60 FACILITY OPERATING LI ENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix "A" Technical Specifications with the e.. closed pages. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
Remove Insert 179*
179*
180 180
- 0verleaf
_ 'm
TATILE 3.7.1 PRIMARY COllTAINMEllT ISOTATION VAINES t1 umber of Power-Maxiinum Astion on
~
Operated Valves Operating flo rrr..i l Isiitiating Grou t Valve Identification Inboard Outboard Tine (sec.)
Position Sirinal 1
Main steam line isolation valves 4
.4 3<T< 5 0
GC 1
Main steam line drain isolation 1
1 15 C
SC valves 1
Iteactor water sample line iso-1 l'
5 C
SC lation valves 1
Main steam sample line 1
1 5
C SC 3
I)r y6m11 purge inlet isolation 2
5 C
SC v.il vt Ie-
't Suppression chanber purge inlet 2
5 C
SC g~
anolation valvec e
3 Nitrogen purge isolation valve 1
5 C
SC 3
Nitrogen makeup isolation valve 1
10 C
SC
'3 Drywell main e.aust isolation 2
'i C
SC salves 3
Drywell exhaur.'
- alve bypass 2
5 C
SC isolation vals.:s 3
suppression chamber main 2
5 C
SC exhaust isolation valves
?
2 5
C SC Us 3
Suppression chamber exhaust m'
valve bypass isolation valves t :]
u-P00R ORGiiEL
~
TA!!Ll' 3.7.1 (Cont'd.)
PRIt1ARY COtJTAIllMEllT ISOLATIOri V%I.VI:S IFuTr uie r O L Power Maximum 8 AcLion on Operated Valves Operating 11ormal Initiatin(I Group Valve Identification Inboard Outi:oa rd Time (sec.)
Position Signal ila Peedwate r check val ~ves 2*
2*
IIA 0
Process 11A Control rod hydraulic return
[l*]#
11*1#
11A C
Process check valves I
lia Control rod la y d r a u l i c return ll*l##
liA C
Locked valve Closed 2a Oxygen Analyzer System 14 NA 0
GC i
tiA Standhy 1iquid control system 1*
l' ilA C
Process check valves 2n RilitS shutdown cooli ng suction 1
1 32 C
SC isolation valves 2 11 RilRS shutdown cooling in jec-1 24 C
SC r
tion isolation valves i
U 2 11 RIlRS Reactor vessel llead Spray 1
1 30 C
SC o
isolation valves 2C Peedwater Plush Valves 2
50 C
SC 4
IIPCIS steam Ir.se isolation 1
1 20 0
GC valves 3
S 5
ItCICS steam line isolation 1
1 15 0
GC E
valves n
2A Reactor water cleanup system 1
1 30 0
GC isolation valves LY u
'3
?
2A Iterictor wat er cicanup system 1
20 0
GC return isolation valve A
- Valves not power operated.
- Deleted after CRD RL is c u t a rid capped wak (8
U~I =
- 1:ffective after CRD RL is rerouted to HWCU System
' ww
~
s ffpa a n c,o, o
UNITED STATES y 7,,
J' h NUCLEAR REGULATORY COMMISSION
,, J %.-,8 E
W ASW NG TON, D. C. 20555 k
PHILADELPHIA ELECTRIC COMPANY PUBLIC SEavlCE ELECTRIC AND GAS C0FPANY DELMARVA POWER AND Lib COMPANY ATLANTIC CITY ELECTR. f.0MP AN Y DOCKET NO. 50-278 PEXCH BOTTCM ATOMIC POWER STATICN, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amencment No. 60 License No. DPR-56 1.
The Nuclear Regulatory Comnission (the Commission) has found that:
A.
The application for amendment by PHladelphia Electric Company, et al., (the licensee) dated April 14, 1978, with supplemental information dated November 18, 1977, June 22 and August 27, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amend 3d (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; 3.
The facility will oper ate in confor nity 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 puDlic; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations ano all applicaole recairements have been satisfied.
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 Faciliey Operating License No. DPR-56 is heremy amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in A;;pendices A and 3, as revised through Amencment No. 60, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
P00ROHNM
. 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ge-rd Thomas'.
lito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 19, 1979
ATTACHMENT TO LICENSE AMENDMENT NO. 60 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 page is identified by Amendment number and contains vertical lines indicating the area of change.
Remove Insert 179*
179*
180 180 1113 CA7
TABLP 3.7.1 PRIMARY CONTAINMENT ISOI.ATION VAINES Humber of Power.
Maximum Action on Operated Valves Operating Normal Initiating Group Valve Identification Inboard Outboard Tine (sec.)
Position Si_onal
]
Hain steam line isolation valves 4
4 3<T<5 0
GC 1
Main steam line drain isolation 1
1 15 C
SC valves 1
Heactor water sample line iso-1 1
5 C
SC 1ation valves 1
Main steam sample line 1
1 5
C SC 3
Drywell purge inlet isolation 2
5 C
SC valves
,e;l 3
Suppression chamber purge inlet 2
5 C
SC s'
isolation valves 3
Nitrogen purge isolation valve 1
5 C
SC 3
Nitrogen makeup isolation valve 1
10 C
SC 3
Drywell main exhaust isolation 2
5 C
SC valves 3
Drywell exhaust valve bypass 2
5 C
SC isolation valves 2
3 Suppression chamber main 2
5 C
SC exhaust icolation valves tea T-3 Suppression chamber exhaust 2
5 C
SC c3 g;
valve bypass isolation valves
_s O
CD
TA!ll.E 3. 7.1 (cont'd.)
PRIt1AltY COllTAlli?1EllT ISOLATIOtt VALVI-:S
~~
Ifuhdier OL Power Maximum Action on Operated Valves Operating flormal Initiating Group Valve Identification Inboard Outboard,
Time (sec.)
Position Signal 11A l'cedwater check valves 2*
2*
IIA 0
Process liA Control rod hydraulic return i1*]#
11']#
liA C
Process check valves HA Control rod la yd r a u l i c return ll*]##
NA C
Lo c it e d valve Closed
! Oxygen Analyzer System 14 tiA 0
GC 2D NA Standby liquid control system 1*
1*
IIA C
Process check valves 2n RilRS shutdown cooling suction 1
1 32 C
SC isolation valves 2B RllRS shutdown cooling injec-1 24 C
SC tion isolation valves e
e
'o$
2in Hl:RS Heactor Vessel llcad Spray 1
1 30 C
SC o
isolation valves 2C Feedwater F?ush Valves 2
50 C
SC 4
itPCIS steam Irae isolation 1
1 20 0
GC valves 5
ItCICS steam line isolation 1
1 15 0
GC E
valves n
2A Reactor water cleanup system 1
1 30 0
GC 04 isolation valves v
'O 7A nonctor water cleanup system 1
20 0
CC return isolation valve G
- Valves not power' operated.
- Deleted after CRD RL is cut and capped
~
- Effective after CRD RI. is rerouted to RWCil System I UUER U u u EWI lb.