ML20147C134
| ML20147C134 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/18/1988 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20147C140 | List: |
| References | |
| NUDOCS 8803030014 | |
| Download: ML20147C134 (16) | |
Text
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'o, UNITED STATES NUCLEAR REGULATORY COMMISSION 3
e y
W ASHING TON, D. C. 20555
%.... /
PHILADELPHIA ELECTRIC COMPANY PURLIC SFRVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-?77 PEACH ROTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSF Amendment No.127 License No. DPR d4 1.
The Nuclear Regulatory Comission (the Connission) has found that:
A.
The apolication for amendment by Philadelphia Electric Company, et al. (the licensee) dated August 6,1981 as sucolemented on April 2, 1984, December 2, 1985, October 29, 1986 and July 7, 1987, complies l
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.
R.
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 l
this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in como11ance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of the public; an.'
E.
The issuance of this amendment is in accordance with 10 CFR Part il of the Commission's regulations and all applicable requirements 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 oaragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
8803030014 880218 PDR ADOCK 05000277 P
PDR i
1 t
i_
-?-
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 127, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 60 days of its date of issuance to accommodate the writing and approval of implementing procedures.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: February 18, 1988 h fB3 OGC J N
PDI-?/0 e p P
M p I tin:mr J i-l Le w J / WButler l/p88 pl /27/88 1/ //88 J /[$/88 J gy
. (2)
Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.127, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 60 days of its date of issuance to accomodate the writing and approval of implementing procedures.
FOR THE NUCLEAR REGllLATORY COMMISSION Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: February 18, 1988 i
ATTACHMENT TO LICENSE AMENDMENT NO.127
' 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 areas are indicated by marginal lines.
Remove Insert 128 128 4
170 170 171 171 Replace the following page of the Appendix B Technical Specifications with the enclosed page. The revised area is indicated by marginal lines.
51 51
l l
PSAPS Unit 2 O
I S"RVI!!I.ANCI RIOU:RD2NT i.:.'C7:NO CON 0!TICNS,JO,1 CPI"G7:CN i
3.5.3
. ntainmen: cecline 4.5.3 Containment cooline d csvstem (con ' [77 Su:svstem (cont'd.)
3.
T::m'and after :1e date that 3.
When it is determined that any 3 HPSW pumpn are made c any 3 HPSW pumps are in-found to be ino;:erable for operable, the remaining any reascn, continued reactor components of both contain-cperation is per:issible only ment cooling subsystems during the succeeding fifteen shall be demonstrated to be days unicss suen pumps are operable immediately and scenar made operamle provided weekly caereafter.
all re=aining cc:ponents of the containment cooling sys-tem are operacle.
4.
T: m and after the date that 4.
When 3 centaLnment eccling 3 con a nment cooling subsys-subsystem loops beccme in-tem iceps are made c found ope r able, the operacle su -
to be ineperable for any rea-system loop and its asscei-son, continued reactor opera-ated diesel-genera:c shall tien is permissible only dur-be demenstrated o be cper-
- ng :ne succeeding seven days able im=ediately and the unless such subsystit.1 loop is operable containmen: ceci-se:ne r made operatic, provi-ing subsys tem 1e *,a daily ded :na all active compo-tnereafter.
nen s of :..e c:ner contain-ment ecc 11..; subsystita icop, including its associa:ed die-se' gene:c ::s, are cperacle.
5.
If :ne requirements ct 3.5.3
~
cannot be met, an c darly s..utdewn shall be initiated and the rea: :: shall be in a Cold Shu-dcwn Cond :ica w1*h-an 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C.
HPC: Scbsvs em C.
If7C: Subsys:2m 1.
The HPC: Subsystem shall be 1.
H2C: Subsystem tes-i..;
cperacle v..enever there is sha*1 be perferned as fel-artsd:stod fuci in the reac-lows:
to vessel, reac:c press re
[
is greata= than 105 psig, and Item Frecue-ey_
pric: to rea: c; startup from a cold Condition, except as (a)
Simulated once/ opera-specified in 3.5.C.2 and Automatic ting cycle 3.5.C.3 below.
Actuation Test M N kwndment No. 127
-128-
PBAPS Unit 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l3.7.A Primary Containment (Cont'd.)
4.7.A Primary Centainment (Cont'd.)
l 3.
Pressure Suppression Chamber -
3.
Pressure Suppression Chamber -
Reactor Bu11dino Vacuum Breakers Reactor Bu11dino Vacuum Breaners
)a. Except as specified in 3.7.A.3.b
- a. The pressure suppression chamber-below, two pressure suppression reactor building vacuum breakers chamber-reactor building vacuum and associated instrumentation breakers shall be operable at*
including setpoint shall be all times when primary contain-checked for proper operation ment integrity is required.
every refueling outage.
The setpoin?, of the differential pressure instrumentation which actuates the pressure suppression chamber-reactor building vacuum breakers shall be 0.5 0.25 psid.
- b. Frem and after the date that one of the pressure suppression chamber-reacter building vacuum breakers is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding seven days unless such vacuum breaker is sooner made oper-able provided that the repair proce-dure dces not violate primary containment integrity.
4.
Orvwell-Pressure Suppression 4.
Drywell-Pressure Suceressien Cnameer Vacuum Breakers Chamoer Vacuum Breakers
- a. When primary containment is
- a. Each drywell' suppression chamber required, all drywell-suppression vacuum breaker shall be chamber vacuum breakers shall exercised through an opening-be operable and positioned closing cycle once a month.
in the fully closed position (except during testing) except
- b. When it is determined that as specified in 3.7.A.4.b and a vacuum breaker is inoperable e below.
for opening at a time when operability is required, all etper opera'le vacuum breake:
'b. Drywell-suppression chamber c
vacuum breaker (s) may be shall be exercised immediately "not f;11y seated" as and every 15 days tr.ereafter shown by position indication until the inoperable if testine ecnfirms that the vacuum breaker has been bypass area is less than or returned to ncemal service.
equivalent to a one-inch diameter hele.
Testing shall be initiated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- c. Once per operating cycle of initial detection of a each vacuum breaker shall "nct fully seated" position be visually inspected teendment No. H.127
-170-
PBAPS Unit 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary Containment (Cont'd) 4.7.A Primary Containment (cont'd.)
indication and shall be per-to insure proper maintenance formed periodically there-and operation.
after as follows:
(1) Once every 15 days (only d.
A leak test of the drywell to if "not fully seated" suppression chamber structure shall be conducted at eacn valve (s) are indicated).
refueling outage to assure
]
(2) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following no bypass larger than or vacuum breaker exercising equivalent to a one-inch required by 4.7.A.4.a and diameter hole exists between 4.7.A.4.B.
(only if the drywell and suppression "not fully seated" valve (s) chamber.
are indicated).
c.
Two drywell-suppression chamber i
vacuum breakers may be inoperable for opening.
d.
If specifications 3.7.A.4.a, b, or e cannot be met, the situa-tion shall be corrected within l
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the unit shall be placed in a cold shutdown condition in an orderly canner.
5.
Oxycen Concentration 5.
Oxycen Cencentratien a.
The primary containment atmos-The primary containment oxygen phere shall be reduced to less coree-tration shall be ressured tnan 4% oxygen with nitrogen gas and recorded at least twice during reactor power operation
- weekly, with reactor coolant pressure above 100 psig, except as specified in 3.7.A.S.b.
l l
b.
Within the 24-hour period, subsequent to placing the reactor in the RUN mode following a shutdown, the containment atmosphere oxygen concentration shall be reduc 6d to less than 4% by volume and maintained in tnis c:nditi n.
De-inerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a shutdown.
l
% a 1 9 9-Amendment No.127
-171-i l
PRAPS Unit 2 7.4 Flant Reporting Requirements 7.4.1 Routine Reports In addition to the environmental monitoring information required by Section 6.9.3.h of Appendix 4 to the Operating License, the following information shall be submitted in an annual' report:
A.
Records of special study programs data and analysis thereof.
B.
Records of changes to the plant which affect the environmental impact of the facility.
C.
Records of changes to environmental per=1ts and certificates.
7.4.2 Non-Routine Reoorts A.
Enviren= ental Deviatien Reoorts In the event of an environmental deviation as defined in the environmental technical specifications, notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone or telegraph to the Director of the NRC Regional Inspection and Enforcement Office. A shall follow within 10 working days to the Director of f vritten report Nuclear Reactor Regulation (copy to the Director of Regional Inspection and Enforcesant Of fice).
The written report on an environmental deviation, and to the extent possible, the preliminary telephone and telegraph notifica-tion, should: (a) describe, analyze, and evaluate implications, (b) deter =ine the cause of the occurrence and (c) indicate the corrective action (including any significant changes mado in procedures) taken to preclude repetition of the occurrence and I
to prevent similar occurrences involving similar components or systa=s.
B.
Reporting of Changes to the Plant or Per=its A written report, including an evaluation of the environmental impact resulting from a change, shall be forwarded to the Direc-tor, Office of Nuclear Reactor Regulation (copy to the Director of the Regional Inspection and Enforcement Office) in the event of:
1.
Changes to the plant that affect the environmental impact evaluation contained in the Environmental Report or the l
A endment No, if,127
/
'o UNITED STATES
~g NUCLEAR REGULATORY COMMISSION n
W ASHING TON, D. C. 20555
%,...../
PHILADELPHIA 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. 130 License No. DPR-56 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendmant by Philadelphia Electric Company, et al. (the licensee) dated August 6, 1981 as supplemented on April 2, 1984, December 2, 1985, October 2n, 1986 and July 7, 1987, complies with the standards and reauirements 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 Comission's regulations;
[
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health or 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.
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:
l I
. (2)
Technical Specifications The Technical Soecifications contained in Appendices A and B, as revised through Amendment.No.130, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 60 days of its date of issuance to accommodate the writing and approval of implementing procedures.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 18, 1988 OGC a k PDI-?/D Pl-/rtin:mr P
a 5 4[eWI:
WButler Jg/88 O/ /JuB8 1/ / /88 gl@8
2 (2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.130, are hereby incorporated in the license. PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license anendment is effective within 60 days of its date of issuance to accommodate the writing and approval of implementing procedures.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-2 Division of Reactor Pro.iects I/II Attachnent:
Changas to the Technical Specifications Date of Issuance: February 18, 1988 I
I
ATTACHMENT TO LICENSE AMENDMENT Nn.130 QCILITYOPERATINGLICENSENO.DPR-56 DOCKET NO. 50-278 Reolace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert 128 128 170 170 171 171 Reolace the following page of the Appendix B Technical Specifications with the enclosed page. The revised area is indicated by marginal lines.
51 51 J
ATTACHMENT TO LICENSE AMENDMENT NO.130 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Reolace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert 128 128 170 170 171 171 Reolace the following page of the Appendix B Technical Specifications with the enclosed page. The revised area is indicated by marginal lines, i
51 51 4
l t
j
PSA?S Unit 3 i M:7:NC CON 0!?!CNS FOR CPERATION SURVI!* LANCE RICU:RE.%ENT 3.5.3 Centain.t.en
"- 14ne' 4.5.3 contain. ment cooline Su:svstem (:en
'd.)
Sussvstem (cont'c.)
3.
T::m and after the date that 3.
When it is determined that any 3 HPSW pumps are made or any 3 HPSW pumps are in-found to be inoperable fer operable, the remaining any reason, continued reac c c mponents of both contain-Operation is permissible only ment coeling subsystems during the succeeding fif teen shall be demonstrated ts be days unicss such pumps are operable immediately and scener made operable provided weekly thereaf ter.
all remain:ng components of
- ..e conta:nmen: cooling sys-tem are operacle.
4.
T :m and after the date that 4.
When 3 contair. ment c'coling 3 c:..: air. ment cooling subsys-subsystem leops beceme in-tem 1 cps are made or found operable, the operacle sum-
- de incperable fe any rea-system loop and its associ-son, continued reactor opera-ated diesel-genera::: shall tien is permissible only dur-be demonstrated to be oper-ing -ne succeeding seven days able immediately and ne unless such subsystem loop is operable centatr. men: cec.-
scener made operable, provi-ing subsystem 1e
,a daily ded :na: al' active compo-
- nereafter.
nents of the c:her contain-me..
c:o*i..g subsystem Icep, including its associa:ed die-se'. genera ::s, are operacle.
5.
If ne requirements of 3.5.3
~
cannet be met, an orderly snutdewn shall be initiated a..d the react:r shall be in a Cold Shutdown Conditicn wi*h-i.. 24 hcu s.
C.
HPO: Sebsvstem C.
1G0: Subsvs:sm 1.
The MPC: Subsystem shall be 1.
EPC: Subsys em testing operam*.e vaenever there is shall be performed as fo'-
- adiated fuel in the reac-lows:
to vessel, reactor pressure l
is greater than 105 psig, and Item Frecuenev pric to reactor startup f:cm a Cold Condisson, except as (a)
Simulated once/ opera-specified in 3.5.C.2 and Automatic ting cycle 3.5.C.3 below.
Actuation Test
.ura Amendment Nc' 130
- 128-
PBAPS Unit 3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l3.7.A Primarv Containment (Cont'd.)
4.7.A Primary Containment (Cent'd.)
(
3.
Pressure Suppression Chamber -
3.
Pressure Suppression Chamber Reactor Buildinc Vacuum Breakers Reactor Bu11cina Vacuum Breaxers l a. Except as specified in 3.7 A.3.b
- a. The pressure suppression chamber-below, two pressure suppression reactor building vacuum breakers chamber-reactor building vacuum and associated instrumentation breaxers shall be operable at including setpoint shall be all times when primary contain-checked for proper operation every refueling outage.
ment integrity is required.
The setpoint of the differential pressure instrumentation which actuates the pressure suppression chamber-reactor building vacuum breakers shall be 0.5 +
0.25 psid.
- b. From and after the date that one of the pressure suppression chamber-reactor building vacuum breakers is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding seven days unless such vacuum breaker is sooner made oper-able provided that the repair proce-dure does not violate primary containment integrity.
4.
Drvwell-Pressure Suppression 4.
Devwell-Pressure Suppression Cnameer Vacuum Breakers Chamber Vacuum Breakers l
Each drywell-suppression chamber l
- a. Wnen primary containment is a.
required, all drywell-suppression vacuum breaker shall be i
chamber vacuum breakers shall exercised through an opening-be operable and positioned closing cycle once a month.
in the fully closed position l
(except during testing) except
- b. When it is determined that I
as specified in 3.7.A.4.b and a vacuum breaker is incperable c below, for opening at a time when operability is required, I
- b. Drywell-suppression chamber all ot er operable vacuum breake:
vacuum breaker (s) may be shall e exercised immediately I
"not fully seated" as and every 15 days thereafter shown by position indication until the inoperable I
I if testing confirms that the vacuum breaker has been returned to normal service.
bypass area is less than or equivalent to a one-inch diameter hole.
Testing shall be initiated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- c. Once per operating cycle l
of initial detection of a each vacuum breaker shall "not fully seated" position be visually inspected l
A endment No. 23,130 170-l l
1
PBAPS Unit 3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary Centainment (Cent'd) 4.7.A Primary Containment (Cent'd.)
indicatien and shall be per-to insure proper maintenance formed periodically there-and operation.
after as follows:
(1) Once every 15 days (enly d.
A leak test of the drywell to if "not fully seated" suppression chamber structure valve (s) are indicated).
shall be conducted at eacn refueling outage to assure 1
(2) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following no bypass larger than er vacuum breaker exercising equivalent to a one-inch require 5 by 4.7.A.4.a and diameter hole exists between 4.7.A.4.B.
(only if the drywell and suppression "net fully seated" valve (s) chamber.
are indicated).
c.
Two drywell-suppres'sion chamber l
vacuum breakers may be inoperable for opening.
d.
If specifications 3.7.A.4.a, b, or c cannot be cet, the situa-tion shall be corrected within l
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the unit shall be placed in a cold shutdown condition in an orderly manner.
5.
Oxycen Concentration 5.
O_xycen Concentration a.
The primary containment atmes-The primary containment exygen phere shall be reduced to less conee-tration shall be terrured than 41 cxygen with nitrogen gas and recorded at least twice during reacter power operation weekly.
with reactor coolant pressure above 100 psig, except as specified in 3.7.A.5.b.
b.
Within the 24-hour period, subsequent to placing the reactor in the RUN mode following a shutdown, the containment e
atmosphere oxygen concentration shall be reduced to less than 4% by volume a.d maintained in this condition.
De-inerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a shutdewn.
% ::;^ 10';
kwndnent No.130
-171-
FRAPS Unit 3 7.4 Plant Reporting lequirements 7.4.1 Routine Reports In addition to tie environmental =onitoring information required by Section 6.9.3.h of Appendix.A to the Operating License, the following information shall be submitted in an annual report:
A.
Recorti of special study programs data and analysis thereof.
B.
Records of changes to the plant which affect the environ = ental impact of the ??:ility.
C.
Records of changes to environmental persies and certificates.
7.4.2 Non-Routine Reoerts A.
Environmental Deviation Reoorts In the evett of an environmental deviation as defined in the environmental technical specifications, notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone or telegraph to the Director of the FRG Regional Inspection and Enforcement Office. A written report shall follow within 10 working days to the Director of l Nuclear Reactor Regulation (copy to the Director of Regional Inspection and Enf orcement Of fice).
The vTitten report on an environmental deviation, and to the extent possible, the preliminary telephone and telegraph notifica-tion, should:
(a) describe, analyse. and evaluate. implications, (b) determine the cause of the occurrence and (c) indicate the correceive action (including any significant changes made in procedures) taken to preclude repetition of the occurrence and l
to prevent similar occurrences involving similar components or systems.
3.
Reporting of Changes to the Plant or Permits A vTitten report, including an evaluation of the environmental impact resulting from a change, shall be forwarded to the Direc-tor, Office of Nuclear Reactor Regulation (copy to the Director of the Regional Inspection and Enforcesant office) in the event of:
l 1.
Changes to the plant that affect the environmental i= pact evaluation contained in the Environmental Report or the Amenument No. 25,130 ;
i
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