ML20141D441
| ML20141D441 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/27/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Vermont Yankee |
| Shared Package | |
| ML20141D444 | List: |
| References | |
| DPR-28-A-092 NUDOCS 8604080078 | |
| Download: ML20141D441 (6) | |
Text
' f tero f
g UNITED STATES y
g NUCLEAR REGULATORY COMMISSION 7.
E WASHINGTON, D. C. 20555 s
/
VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 92 License No. DPR-28 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Vermont Yankee Nuclear Power.
Corporation (the licensee) dated November 15, 1985, 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; 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 common 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.
l 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-28 is hereby amended to read as follows:
j l
I 9604080078 860327 PDR ADOCK 05000271 P
PDR i
L
. (2) Technical Specifications j
The Technical Specifications contained in Appendix A, as revised through Amendment No. 92, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the 1
Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Y
A/
ysm Daniel R. Muller, Project Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 27, 1986 P
k
ATTACHMENT TO LICENSE AMEND *'.ENT NO. 92 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised area are indicated by marginal lines.
Pages 109 110 124 l
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l I
i
VYNPS 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT E.
Structural Intezeity E.
Structural Integrity The structural intergrity of the primary The nondestructive inspections listed in system boundary shall be maintained at the Table 4.6.1 shall be performed per the level required by the original acceptance requirements of the 1974 edition of ASME, standards throughout the life of the plant.
Section XI, up to and including the 1975 Summer Addenda except piping examinations (Cat. F & J) shall be per the requirements of 1
ASME Section II, 1974 edition, 1976 Summer Addenda, Appendix III.
Recording levels shall be at 50% of the 1.
Whenever the reactor is in the reference level.
i startup/ hot standby or run modes, all I
jet pumps shall be intact and all F.
Jet Pumps j
operating jet pumps shall be operable.
l If it is determined that a jet pump is 1.
Whenever there is recirculation flow
}
inoperable, an orderly shutdown shall be with the reactor in the startup/ hot j
initiated and the reactor shall be in a standby or run modes, jet pump integrity
]
cold situation condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
and operability shall be checked daily by verifying that the following two 2.
Flow indication from each of the twenty conditions do not occur simultaneously:
jet pumps shall be verified prior to initiation of reactor strtup from a cold a.
The recirculations pump flow shutdown condition.
differs by more than 10% from the i
established speed-flow 3.
The indicated core flow is the sum of characteristics.
the flow indication from each of the j
twenty jet pumps. If flow indication b.
The indicated total core flow is failure occurs for two or more jet more than 10% greater than the core i
pumps, immediate corrective action shall flow value derived from established I
be taken.
If flow indication for all power-core flow reistionship.
but one jet pump cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> an orderly shutdown 2.
Additionally, when operating with one shall be initiated and the reactor shall recirculation pump,the diffuser to lower be in cold shutdown condition within plenum differential pressure shall be 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
checked daily, and the differential pressure of any jet pump in the idle l
loop shall not vary by more than 10%
from established patterns.
Amendment No. AK, 92, 109 i
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WWS 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT I
' 3.
The baseline data required to evaluate the conditions in Specifications 4.6.F.1 and 4.6.F.2 shall be acquired each operating cycle.
C.
Single Loop operation 1.
Operation with a single recirculation loop is permitted for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the recirculation loop is sooner made operable.
If the loop cannot be made operable, the reactor shall be in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
H.
Recirculation System 1.
This section deleted.
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Amendment No. )$f, 92',
110 l
VYNPS 3.6 & 4.6 (cont'd)
The following factors form the basis for the surveillance requirements:
A break in a jet pump decreases the flow resistance characteristic of the externsi piping loop causing the recirculation pump to operate at a higher flow condition when compared to previous operation.
The change in flow rate of the falled jet pump produces a change in the indicated flow rate of that pump relative to the other pumps in that loop. Comparison of the data with a normal relationship or pattern provides the indication necessary to detect a failed jet pump.
The jet pump flow deviation pattern derived from the diffuser to lower plenum differential pressure readings will be used to further evaluate jet pump operability in the event that the jet pumps fail the test in Specifications 4.6.F.1 and 2.
Agreement of indicated core flow with established power-core flow relationships provides the most assurance that recirculation flow is not bypassing the core through inactive or broken jet pumps. This bypass flow is reverse with respect to normal jet pump flow. The indicated total core flow is summation of the flow indications for the twenty individual jet pumps. The total core flow measuring instrumentation sums reverse jet pump flow as though it were forwarded flow. Thus, the indicated flow is higher than actual core flow by at least twice the normal flow through any backflowing pump. Reactivity inventory is known to a high degree of confidence so that even if a jet pump failure occurred during a shutdown period, subsequent power ascension would promptly demonstrate abnormal control rod withdrawal for any power-flow operating map point.
A nozzle-riser system failure could also generate the coincident failure of a jet pump body; however, the converse is not true. The lack of any substantial stress in the jet pump body makes failure impossible without an initial nozzle-riser system failure.
C.
Single Loop Operation An evaluation was not provided for ECCS performance during reactor operation with one recirculation loop out of service. Therefore, reactor operation for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> under such conditions will not be authorized until the necessary analyses have been perforned, evaluated and deemed acceptable.
H.
Recirculation System This section deleted.
i AmendmentNo.fif,92, 124