ML20011E258
| ML20011E258 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 02/05/1990 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20011E259 | List: |
| References | |
| NUDOCS 9002130006 | |
| Download: ML20011E258 (5) | |
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'o,j UNITED STATES
- P NUCLEAR REGULATORY COMMISSION o
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ll WASHINGTON, D. C. 20666
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i VERM0NT' YANKEE NUCLEAR-POWER CORPORATION ~
DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.119 License No. DPR-28 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Vermont Yankee Nuclear Power Corporation (the licensee)-dated August 26, 1986 and as supplemented January 16,.1990 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 Chapter I; I
l B.
The facility will operate in conformity with the application, the l
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 compliance with the Comission's regulations set forth in 10 CFR
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Chapter I; L
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 l
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 Specifica-tions as indicated in the attachment to this license amerdment, and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.119, are hereby incorporated in the license.
I The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective within 30 days of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 7
Ric ard H. Wessman, Director Project Directorate I-3 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation Attachment..
Changes to the Technical Specifications.
Date of Issuance:
February 5,1990 i
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i ATTACHMENT-TO LICENSE AMENDMENT N0J19' I
. FACILITY OPERATING LICENSE NO. DPR,
DOCKET N0_. 50-271-
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Replace the following pages of the Appendix A Technical Specifications with I
.the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
w Remove Insert 127-127 139a 139a s
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'VYNPS 4.7 SURVEILLANCE REQUIREMENTS
. 3.7 LIMITING CONDITIONS FOR GPERATION 3.
Whenever primary containment is required, the total 3.
IPrior to violating the integrity of a system primary containment leziage rete shall not exceed
.outside-the primary containment, which is connected to any valve listed in Table 4.7.2b, the 0.8 weight. percent per day (L ) at a pressure a
isoletion valves bounding the opening shall have 44 psig (P ).
Type C tests performed.
If the opening cannot be a
isolated frots the containment by two isolation 4.
Whenever primary containment is required, tL valves which meet the acceptance criteria of' leakage from any one isolation valve shall not exceed 5 percent of the maximum allowable leak rate Appendix J (10CFR Part 50), a blank flange shall be installed on the opening.
(L ) at peak accident pressure (P ) and the a
a leakage from any one main steam line isolatica ~alve shall not exceed 15.5 scf/hr at 44 psig (F,).
4.
The leakage from any one isolation valve shall not.
exceed 5% of Ltm. The leakage from any one main steam line isolation valve shall not exceed 5.
Pressure Suppression Ch*=her - Reactor _
11.5 scf/hr at 24 psig (Pt). Repair and retest :
Building Vacuum Breakers shall be conducted to insure compliance.
Two of two pressure suppression chamber-reactor a.
5.
Pressure Suppreaaion c'-her -
building vacuum breaker systems shall be Reactor Building vac-- Breakers operable at all times when the primary containment integrity is required. The setpoint The pressure suppression chamber-reactor of the differential pressure instrumentatio5:
a.
which actuates the pressure suppression building vacuum breaker systems and associated instrumentation including setpoint chamber-reactor building air-operated vacuum breakers shall be 10.5 psid. The self actuating shall be checked for preper operation every -
vacuum breakers shall og,en fully when subjected three months.
to a force equivalent to or less than 0.5 p.21d b.
During each refueling outage, each vacuum acting on the valve disk.
breaker shall be tested to determine that the b.
With one Reactor Building - suppression chamber force required to open the vacuum breaker.'
does nor exceed the force specified in vacuum breaker inoperable for opening but known to be closed, restore the inoperable vacuum Specification 3.7.A.5.a and each vact'un breaker to OPERABLE status within seven (7) days breaker shall be ir.spected and verified to or then be in cold shutdown within the following meet design requirements.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With one Reactor Building - suppression chamber c.
vacuum breaker failed open - power operation may con _tinue provided the other vacuum breaker in that line is verified to be closed and conditions required by 3.7.D.2 are met.
127 Amendment flo.119 W
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3.F.A (Cont'd) i' t
The purpose of the wecuum rettet wetwee Le to egustLee the pressure h=*-
the dryum&& end esppresonen i
chamber and suppresekee chseher and reacter hellelag so that the structuret lategrity of the eentetement le
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i antatelmed.
I Technisel'. Specificetten 3.7.A.9.e he hooed en the ga== that the sporehtitty testems of the pressese supprenelium thesher-reacter buildles weemum bes=ene. ehen reestred, m&11 seenst&y he portenese earleg the some four hour teettag intervet es the pressure espyresolen etW1 seamos beenhees an eeder to mLmAotse operetten with d.F pot. different&st preneure.
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i The weemum rollef system from the pressure seppenesten ebeehor to ame a-gegadlag esentate of fans adK wecesism relief breeborp (2 parettet este of 2 welwoo in series). Spor-sta= et maahme speten e411 estateLa l
the pressure differe E % 1 lose than 2 peig; saa enterest deelde pressure le 2 po63 Mth esu seemum ihresher out of service there as ao lamediate threat to ese& dent ettleetAen er peleary===.a eng,,
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therefore, reseter operettest een De centlemed for 7 dopo m a repelps are hotes made.
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I the cepecity of the ten (le) drywell weeuma re!&ef selwee le steed te Almit the pensouse diffeeentant
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hetween the suppresstem chamber and drywott during post-seendent dryme&& esottes operettame to the doeles li=LL of 2 pois. They are sized en the beste of the Bedese Bay pressure seppemmestem teste. 'dhe 4 M Beller and pressure vessel Code, seetten III. Sehoettien B. for thts weaset e&Seus e4@k (e) spesehte j
~ wolves, therefore, with tue (2) selves emeared.
a.a====4 lategrity le est Sepeteed.
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Each drywell-empyreestem cheeber weeman breaker le fitted with e e pele of 14m&g w a.m to l
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provide fail-safe signets to penet mounted ledteatere la the meester smildtag emi eteens in the Centent asem whom the dieke are open more than G.950" at ett potete elems the seat sucfese a the etett. Mese l
euttches are capehle of tr====Attias the diett eleoed to eram sn mel with e.et" assemenE et the au6teh l
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plunger. Contiensed reacter operation with fetted *==y====*= le jesettfled homemos of the N es coopemente and ciremite enc. east layertently, the steeseehility of the volve Sewer enen and postbles i
reference externet to the valve. The felt este festore of the steen s& semite esauses operater ettest&en St l
e time fonelt occure.
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e.elt.e,preneu.,.eppressie.. set. inn.at,
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l saap-3596, sowember 17. 196e.
l (2) medess hay prelleinery Moserde >===ry Report, appendia 1. *==han 50-2e5. mW 23,1962.
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Code A11euehte peek emeldent preesure le 62 pelt.
amendment me. g. Ltc. etd. y/1/s5 Bases Change,119 nate i
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