ML19209B282
| ML19209B282 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/13/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19209B276 | List: |
| References | |
| NUDOCS 7910090436 | |
| Download: ML19209B282 (2) | |
Text
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ATTACHMENT TO LICENSE AMENDMENT NO. 58 FACILITY OPERATING LICENSE N0. DPR-44 DOCKET N0. 50-277 Rep'sce 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 171*
171*
172 172
- 0verleaf 7 910 0 9 0 <@- fs' 1114 194
~
s PSAPS ISURE _g _.ILL N,.C_E ?_C. OUI?2'.F.NT2 - -_ -
_LIMI~ ING COND_ITIONS__ FOR OPERA _T_I_O.N.--
t'3.7... Prima Q _Contair;..ent 3.7.A Primarv Containment i
4 mined to be not rore cperability is required, than 30 open as indica-cl1 other vacuum brea.ker ted by the position valves shall be exer-lights.
ci::cd immediately and every 15 days thereaf ter until the incperable valve has been returned to I
no mal service, c.
Two drywell-suppression c.
Once each operating chamber vacuum breakers c;cle, each vacuum breaker may be determined to be alvo shall be visually inoperable for opening.
inspected to insure proper maintenance and operation.
d.
If specifications 3.7.A
- d. A leak test of ti.e drywell to
.4.a,
.b, or.c cannot suppression chamber structure be met, the situation shell be conducted at each re-shall be corrected within fuelin;;' to assure no bypass
~
24 f.ours or the unit will lar;;cr than or equivalent to ens be placed in a cold shut-inch diameter hole exists betwear down condition in an t% dr~ ell anti auporession orderly manner.
chamb er.
5.
Oxygen concentration 5.- Oxygan Concentration a.
After completion of the startup The primary containment test program and demonstration oxvoen concentration shall of plant electrical output, the be'5aasured and recorded primary containment atmosphere at least twice weekly, shall be reduced to less than 4% oxygen with nitrogen gas during reactor power operation with reactor coolant pressure above 100 psig, except as specified in 3.7. A.S.b.
b.
Within the 24-hour period subsequent to plc.e og the reactor in the Run mode fo'llowing a shutdown, the containment atmosphere oxygen concentration shall be reduced to less than 4%
by volume and 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 shutdown.
lil4 195
-171-Octoberl973
s I.I".! TING CONDITIO::S 703 OPERTsTICN l SURVD LL7.':CI ?.IOUIFI"IMTS
- 3. 7. A Primary Containment
- 4. 7. A Primary Containment
- 6. Containmant Atmeschere
- 6. Containment Atmosehere Dilution
' Dilution
- a. Whenever either re. actor a.
The post-LOCA contain-is in pcwcr operation, rent atm sphere dilu-the Post-LOCA Containment tien system,shall be Atmesphere Dilution Sys-functionally tested tem must be cperable and cnce per operating capable of ' supplying cycle.
nitrogen to either Unit 2 or Unit 3 centainment for atmosphere dilution if required by post-LOCA conditions.
If this specification cannet be met, the system must be restored to an cpertble condition within 30 days or both reactors must be taken out of power opera-tien.
- b. Whenever either reactor b.
The level in the it in power operation, liquid N2 storage tank the post-LOCA Containment shall be recorded Atmosphere Cilution Sys-weekly.
tem shall centain a mini-mum of 2000 gallons of If this liquid N2 specification cannot be met the minimum volume will be restored within 30 days or both reactors must be taken out of powe.r operation.
- c. Whenever either of the c.
- The centainment reactors is in power exygen analyzing sys-operation, there shall be tem shall be func-at least one CAD system tionally tested twice H2 and 02 analy:er serv-per week in conjunc-ing the drywell and one tien with specifica-tion 4.7.A.5.
The CAD system H2 and 02 analyzer serving the sup-exygen analyzer shall pression cha ber en that be calibrated once per reactor.
If this speci-E months.
fication cannot be met, i114 196 k:endment No. 58
-172-
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UNITED STATES y ),3 vy g
NUCLEAR REGULATORY COMMISSION 3('
.E WASHINGTO N, D. C. 20$55 o
/
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPAfW OELMARVA POWER AflD LIGHT COMPAtlY ATLANTIC CITY ELECTRIC COMPAfiY DOCKET NO. 50-278 PEACH BOTT0ft ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILI!Y OPERATING LICENSE Amendment No. 58 License No. DPR-56 1.
The Nuclear Regulatery Commission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated September 11, 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 with9ut endaageriag the health and safety of the public, and (ii) that such activittes will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimfcal to the cocrnon 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.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications 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 in Appendices A and B, as revised through Amendment No. 58, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
1114 197
s 3.
This license amendment is affective as of the dat'e of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas n.
ppolito, hief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: September 13, 1979 O
1114 198
ATTACHMENT TO LICENSE AMENDMENT NO. 58 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 indicated by amendment number and contains vertical lines indicating the area of change.
Remove Insert 171*
171*
172 172
- 0verleaf 4
0 e
i 114 199
P00RORGNi PEAPS LI!*.ITING CONDITIONS FOP. OPERATION I S UF.W.ILL14~.'E,~?COIII 0T'5572 3.7.A Primarv Containment
.i.7.A Pri n? Contai.r.ent mined to be not : ore cperability is required, than 3 0 open as indica-
.all other vacuum breaker ted by the position valces shall be exer-
- lights, ciced i.:ediately and every 15 days thereaf ter -
until the incperable valve has been returned to l
nor.al service.
~
c.
Two drywell-suppression
- c. Once each operating cha.ber vacuum brcakers cycle, each vacuum breaker may be determined to be valvo shall be visually inoperable for opening.
inspected to insure prcper maintenance and operation.
d.
If specifications 3.7.A
- d. A Ic:h test of the drywell to
.4.a,
.b, or.c cannot sup;rassion chamber structure be met, the situation sh:11 be conducted at each re-shall be corrected within feelin;; :o assure no bypass
~
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the unit will lar;cr than er equivalent to oas be placed in a cold shut-iner disreter hole exists betweat down condition in an t9 dr ~ 1:. and mucoression orderly manner.
cha:Ser.
5.
Oxygen concentration
- 5. Cxvgan Concentration a.
After ccmpletion of the startup The primary containment test program and demonstration oxygen concentration shall of plant electrical output, the be measured and recorded primary containment atmosphere at least twice weekly.
shall be reduced to less than 4% oxygen with nitrogen gas during reactor power operation with reactor coolant pressure above 100 psig, except as specified in 3. 7. A.S.b.
b.
Within the 24-hour period subsequent to placing the reactor in the Run mode fo'llowing a shutdown, the containment atmosphere oxygen concentration shall be reduced to less than 4%
by volume and maintained in this condition.
De-inerting
=ay 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.
1114 200
-171-October 1973
LIMITING CONDITIO!!S FOR5?ERATION l SURVEILLA!:CE F.EOUIPIME.~fS 3.7.A Primary Containment 4.7. A Primarf Centainment
- 6. Containment Atmoschere
- 6. Containment Atmosohere Dilution Dilution
- a. Whenever either reactor
- a. The post-LOCA centain-is in pcwcr operation, tent atmosphere dilu-the Pos t-LOCA Containment tion system'shall be Atmosphere Dilution Sys-functionally tested tem must b9 cperable and, ence per operating capable of supplying cycle.
nitrogen to either Unit 2 or Unit 3 containment for atmosphere dilution if required by post-LOCA conditions.
If this specification cannot be met, the system must be restored to an operable condition within 30 days or both. reactors must be taken out of power opera-tion. -
- b. The level in the
- b. Whenever either reactor -
liquid.N2 storage tank is in power operation, the post-LOCA Containment shall be recorded Atmosphere Dilution Sys-weekly.
~ ~
tem shall contain a mini-mum of'2000 gallons of If this liquid N2 specification cannot be met,the minimum volume l
will be restored within 30 days or both reactors must be taken out of power operation.
- c. Whenever either of the c.
- The containment reactors is in power oxygen analyzing sys-operation, there shall be tem shall be func-at least one CAD system tionally tested twice H2 and 02 analyzer serv-per week in conjunc-ing tne drywell and one tion with specifica-CAD system H2 and 02 ti6n 4.7.A.S.
The analyzer serving the sup-oxygen analyzer shall pression chamber on that be calibrated once per reactor.
If this speci-5 months.
fication cannot be met, 114 20i Amendment No. 58
7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKETS NOS. 50-277 Al'D 50-278 PHILADELPHIA ELECTRIC COMPANY, ET AL.
NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U. S. Nuclear
- Regulatory Commission (the Commission) has issued Amendment Nos.58 and 58 to Facility Operating License Nos. DPR-44 and DPR-56, issued to Philadelphia Electric Company, Public Service Electric and Gas Company, Delmarva Power and Light Company, and Atlantic City Electric Co.apany, which revised Technical Specifications for operation of the Peach Bottom Atomic Power Station, Units Nos. 2 and 3 (the facility) located in York County, Pennsylvania. The amendments are effective as of the date of issuance.
The amendments revise the Limiting Conditions for Operation for the Containment Atmosphere Dilution System by permitting the system to be inoperable for a period of up to 30 days rather than for the 7 days currently permitted.
The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Comission has made appropriate find-ings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments.
Prior public nutice of these amendments was not required since the anndments do not involve a significant hazards consideration.
The Commission has determined that the issuance of these amendments will not result in any significant environmental impact and that pursuant to 10 CFR
!i51.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of these amendments.
1114 202
7590-01 For further details with respect to this action, see (1) the application for amendment dated September 11,1979,(2) Amendment Nos. 58 and 58 to License Nos. DPR-44 and DPR-56, and (3) the Comission's letter dated September 13, 1979. All of these items are available for public inspection at the Comission's Public Document Room,1717 H Street, N. W., Washington, 9. C. and at the Government Publications Section, State Library of Penruylvania, Education Building, Commonwealth and Walnut Streets, Harrisburg, Pennsylvania. A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C.
20555, Attention: Director, Division of Operating Rea'ctors.
Dated at Bethesda Maryland this 13th day of Sep,tember 1979.
FOR THE NUCLEAR REGULATORY COMMISSION 7 -
7
~
Thoma '
Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors 1114 203