ML20235L672
| ML20235L672 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/15/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235L675 | List: |
| References | |
| NUDOCS 8902270623 | |
| Download: ML20235L672 (15) | |
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UNITED STAT 55 :
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NUCt. EAR REGULATORY COMMISSION E
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VIRGINIA ELECTRIC AND POWER _ COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNI _T NO.J 1
AMENDMENT T0 FACILITY OPERATING LICENSE Amen'dment No. 11E.
License No. NPF-4
- 1. -
The~ Nuclear Regulatory Comission (the Cormnission) has four.d that:
A.
The epp11 cation for amendment by Virginia Electric and Power Company l
et al., (the licensee) dated January 13, 1989, complies with the o
standards and requirements of the Atomic Energy Act cf 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I;
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B.
The facility will operate in confor'aity with the application 3 1
the-provisions of the Act, and the rules and regulations of 1
the Commission; C.
Thera is reasonable assurance (i) that the activities authorized by this 'arnendment 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 comon 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 Comission's regulations and all applicable requirements have been satisfied.
1 8902270623 89T15 D
PDR ADOCK 05000338 P
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Accordingly, the license is amended by changes to the Technical' Speci-
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.fications as indicated in the attachment to this license amendinent, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby l
amended to read as follows:
(2) Technical. Specifications l
1 The Technical Specifications contained in Appendices A and B, as revised through Amendment No.115, are 'hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 7 days.
FOR THE NUCLEAR REGULATORY COMMISSinN T3 A c.
Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the lechnical Specifications Date of Issuance: February 15,.1989 l
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i ATTACHMENT TO LICENSE _f1ENDMENT NO. 115 A
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TO FAQ1LITY OPERATING LICENSE NO.'WPF-4 DOCKET NO. 50-338 Replace.the following pages of the Appendix "A" Technical Specifications -
. With the enclosed pages as indicated. The revised pages'are identified by emendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
'I'aie 3/4 9-10 3/4 9-10a (new)
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4 RJFUEQNG OPERATIONS,
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CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Purgt and Exhaust isolation system shall be-OPERABLE.
APPLICABILITY: MODE 6.
ACTION:-
With the Containment Purge and Exhaust isolation system inoperable, close each of the Purge and Exhaust penetrations providing direct access from the containment atmosphere to the outside atmosphere.
The provision of. Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.9 The Containment Purge and Exhaust isolation system shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS by verifying that con-tainment Purge and Exhaust isolation occurs on manual initiation and on a high radiation test signal from the containment gaseous and particulate radiation monitoring instrumentation channels.
NORTH ANNA - UNIT 1 3/4 9-9
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l-REFUELING OPERATIONS W. ATER LEVEL - REACTOR VESSEL L
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FUEL ASSEMBLIES LIMITING CONDITION FOR OPERATION l
3.9.10.1. At least 23 feet of water shall be maintained over the top of the j
reactor pressure vessel flange.
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i APPLICABILITY: MODE 6 during movement of fuel assemblies within the containment.
ACTION: With the requirements of the above specification not satisifed, suspend all operations involving movement of' fuel assemblies within the reactor l) pressure vessel. The provisions of Specification 3.0.3 are not applicable.
, SURVEILLANCE REQUIREMENTS 4.9.10.1 The dater level shall be determined to be at least its minimum required-l depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement of fuel assemblics.
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4 NORTH ANNA - UNIT 1 3/4 9-10 Amendment No. 32,792,115
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' REFUELING OPERATIONS WATER tEVEL - REACTOR: VESSEL-1 CONTROL. RODS LIM 7 TING CONDITION FOR OPERATION 3.9.10.2 At least 23 feet of water shall be maintained over th top of the irradiated fuel assemblies within the reactor pressure.vesss1.
APPLICABILITY: MODE 6 during movement of control rods within the reactor pressure vessel..
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ACTION: With the requirern.ents of the above specification not s.atisified,
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suspend all operations involving ; movement of control rods within the: reactor pres:,are vessel. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.10.2 The water level shall be determined to be at least its. minimum required-depth within 2. hours prior to the start of and'at least once' per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement of control-rods within the reactor pressure vessel.
l NORTH ANNA - UNIT 1 3/4 9-10a Amendment No.115
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i REFUELING OPERATIONS BASES 3/4.9.10 and 3/4.9.11 WATEP, LEVEL - REACTOR VESSEL AND IPENT FUEL PIT I
The restrictions on minimum water level ensure that sufficier.t water depth is available to remove 99% of the assumed 16% iodine gap activity released from the rupture of an irradiated fuel assembly. The l
minimum water depth is consistent with the assumptions of the accident analysis.
The minimum water level for movement of fuel assemblies (23 feet above the vessel flange) assures tht sufficient water depth is maintained above fuel elements being moved to or from the vessel. With the upper internals in place, fuel a:;semblies and control rods cannet be removed from the vessel. Operati6ns q
i involving the lifting of control rods with the vessel upper internals in pldce may proceed with less than 23 feet of water ab6ve the vessel flange provided that 23 feet 6f water is maintained above all irradiated fuel assemblies within the reactor vessel.
3/4.9.12 FUEL BUILDING VENTILATION SYSTEM The limitations on the fuel building ventilation system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the auxiliary buil...g HEPA and charcoal filter assemblies prior to discharge to the atmosphere. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
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l NORTH ANNA - UNIT 1 B 3/4 9 3 Amendment No.115
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'k UNITED STATES.
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WASHINGTON, D. C. 20655 ' '
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' VIRGINIA ELECTRIC AND' POWER COMPANY OLO DOMINION ELECTRIC COOPERATIVE, i
DOCKET tt0. 50-339
.J NOPTH_ ANNA POWER STATION,1NITJ0g.
q AMENDMENT TO FAC7.LITY CPERATING L'ICENSE-
- Amendment No. 98-l
' License No. NFFi7 1.
The Nuclear Regult. tory Comission (the Comission}: has found that:
A.
The application for amendment by Virginia ilhetric and Power Company, et al., (the licensee) dated January 13, 1989, complies with the standards and require m ts of the Atomic Energy Act of 1954, as amended (the Act), and t.he Comission's. rules and regulations set forth in 10 CFR Chapter I; i
B.,
The facility will operate in conformity with the application, 1
the provisi ms of the Act, and the rules and regulations of
'l the Comission; C.
There is reasonable assurance (i) that the activities authnrized by ~ this amendment can be conducted without endangering 'he health ind safety of the public, and (ii) that such activities will be i
c0nducted in compliance with the Cosmission's regulatforts; I
D.
The issuance of this amendment will not be inimica'. to the common defense and security or to the healG and safety Gf the public; and
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E.
The issuance of this amendment is in accordat:e with 10 CFR Part i
51 of the Comission's regulations and all applicable requirements j
have been satisfied.
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. 2.
Accordingly, the license is smenced by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, ard paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hueby art. ended to read er follows:
(2) Technical Specifications The Technical Spt.scifications contained in Appendices A and B, as revised through Amen 6 ment No. 98, are hereby incorporated in the license.
The licensee shall operate the facility in i
accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 7 days.
FOR T!:E NUCLEAR REGULATORY COMMISSION T$adC.%dd% hr<
Harbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifi cations Date of Issuance: February 15, 1989 l
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I' ATTACHMENT TO LICENSE AMEN 0 MENT NO. 98 TO FACILITY OPERATING LICENSE NO. NPF,
DOCKET N0. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the cnclos.ed pages at, indicatec. The revised pages are identified by n
amendment number and contain vertica.1 lines indicating the area of change.
]
The corresponding overleaf pages are also provided to maintain document completeness.
Page 3/4 9-11 3/4 9-11a (new) 3/4 9-12*
B3/4 9-3
- This page was not changed.
It is included to maintain document completeness.
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REftELING OPERATIONS I
WATIT< LEVEL - REACTOR VESSEL FUEL ASSEMBLIES-l.
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LIMITING CONDITION FOR OPERATION L'
3.9.10.1 At least 23 feet of water shall be maintained over the top of the.
l reactor pressure vessel flange.
APPLICABILITY: MODE 6 during movement of fuel assemblies within the containment. l
. ACTION:
I 3-With the requirements of the above specificctior, not satisfied, suspend al' operations involving movement of fuel assemblies within the reat: tor pressure l
vessel. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REijU!REMENTS 4.9.10.1 The water level thall be detennined to be at least its minimum l-required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> pr.ior to the start of and at least once per i
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement of fuel assemblies.
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NORTH ANNA - UNIT 2 3/4 9-11 Amendment No. 85. 98 i
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i REFUELING OPERATIONS I
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l WATERLQEL-REACTORVESSEL CONTROL RODS LIMITING CONDITION FOR'0?FRATION l
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3.9.10.2 At least 23 feet of water shall be maintained over the top of the irradiated fuol assemblies within the reactor pressure vessel, l
APPLICABILITY: MODE 6 during movement of control rods within the reactor
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pressure vessel.
1 ACTION:
With the requirements of the above specification not satisfied, suspend all operations involving movement of control rods within the reactor pressure vesrel.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.10.2 The water level shall be determined to be at least its minimum required' depth sithin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. prior to the start of and at lesst once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter d6 ring movewnt of control rods within the rcactor pressure vessel.
r NORTH ANNA - UNIT 2 3/4 9-ila Amendment No. 98
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-SPENT 70EL' PIT WATER LEVE,L
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LIMITING CONDITION FOR OPERATION 3.9.11' At least 23 feet of water shall be maintinined.over the top of irradinted fuel. asses 111es sected in the storage racks.
I APPLICA8ILITY: 'Whenever irradiated fue1' assemblies are in the spent i
fuel pit.
l ACTION:
With the requirements of the specification not satisfied, suspend all. movement of fusi assembifes and crane operations with loads in the spt:t fuel pit areas and place the load in a safe condition.
Restore water level to uithin its limit within 4 houps.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE (QE10EMENTS
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4.9.11 The water level in the spent fuel pit shall be determined to be st least at the miaisus required depth at least once per 7 days when irradiated fuel assemblies; are in the spent fuel pit.
l NORTH ANNA - UNIT 2 3/4 9-12
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' REFUELING OPERATIONS i
BASES i
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a 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL PIT The restricticris on minimum water level ensure that sufficient water depth ic available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth.is j
consistent with the assumptions of.the accident analysis.
i The minimum water level for movement of fuel assemblies (23 feet above the vessel flange) assures that sufficient water depth is maintained above fuel-elements being moved to or from the vessel. With the upper internals in place, fuel assemblies and control rods cianot be removed from the vessel. 10perations involviiig the lifting of control rc0s with the vessel upper internals in place l
may proceed With less than 23 feet of water above the vessel flange provided that 23 feet of water is mainta!!ned above all irradiated fuel assembes within the reactor vessel.
3/4.9.12 FUEL BUILDING VENTILATION SYSTEM The limitations on the fuel building ventilation system ensure that al?
radioactive material released from an irradiated fnel assembly will be filtered through the auxiliary building HEPA and charcoal filter assemblies prior to discharge to the 8tmosphere. The OPERABILITY of this sytem and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
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I 140RTH ANNA - UNIT 2 B 3/4 9-3 Amendment No. 98 i
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