ML20081K865
| ML20081K865 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/23/1995 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081K866 | List: |
| References | |
| DRR-28-A-143, NUDOCS 9503290324 | |
| Download: ML20081K865 (8) | |
Text
2 p.nnog fi UNITED STATES g
,g NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20!M@01
't, * *.. *,o VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.143.
License No. DPR-28 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by the Vermont Yankee Nuclear Power Corporation (the licensee) dated December 16, 1994, as supplemented by letter dated February 15, 1995, 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 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:
9503290324 950323 PDR ADOCK 05000271 P
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l 9.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.143, are hereby incorporated in the license. The i
licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION f\\#1%
Phillip F. McKee, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to +he Technical Specifications.
Date of Issuance:
fiarch 23, 1995 i
i ATTACHMENT TO LICENSE AMENDMENT NO.143 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical 1.ines indicating the area of change.
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Remove Insert 152 152 153 153 I
i 154 154 166 166 166a P
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' 3.7 LIMITING CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMDITS OPERATION AP is reduced to
<1.7) during required operability testing of the HPCI system pump, the RCIC I
system pump, the drywell-suppression chamber vacuum bfoakers, and the suppression i
chamber-reactor building vacuum l
breakers, and SCTS testing.
[
d.
If the i
specifications of i
3.7.A.9.a cannot be met, and the differential I
pressure cannot be restored within the i
subsequent six (6) hour period, an orderly shutdown shall be initiated i
and the reactor 1
shall be in a Hot Shutdown condition in six (6) hours and a Cold Shutdown condition in the following eighteen (18) hours.
B.
Standbv Gas Treatment System B.
Standbv Gas Treatment System I
l 1.
a.
Except as specified 1.
At least once per in Specification operating cycle, not to l
3.7.B.3.a below, exceed 18 months, the whenever the following conditions j
reactor is in Run shall be demonstrated.
Mode or Startup Mode, both circuits a.
Pressure drop j
of the Standby Gas across the combined Treatment System HEPA and charcoal i
shall be operable f11ter banks is i
at all times when less than 6 inches secondary of water at containment 1500 cfm tlot.
integrity is required.
b.
Inlet heater input is at least 9 kW.
b.
Except as specified in Specification 3.7.B.3 b below, whenever the reactor is in Refuel Mode, both circuits of the Standby Gas Amendment No. M, 49, w, H3 152
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VYNPS j
.3.7 LIMITING CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS l
OPERATION Treatment system 2.
a.
The tests and and an alternate sample analysis-of i
electrical power specification j
source, consisting 3.7.B.2 shall be of the associated performed initially asergency Diesel and at least once j
Generator or Vernon per operating cycle i
tie, for each not to exceed i
standby gas 18 months, and
~ treatment circuit following painting, shall be operable fire or chemical at all times when release in any i
secondary ventilation zone containment casssaicating witit integrity is the system, while required.
the system is-operating, that-2.
a.
The results of the could contaminate in-place cold DOP the NEPA filters or and halogenated charcoal adsorbers.
hydrocarbon tests at design flows on b.
Cold DOP_ testing l
HEPA and charcoal shall be performed i
filter banks shall after each complete i
show 1994 DOP or partial l
removal and 1994 replacement of the j
halogenated HEPA filter bank.
j hydrocarbon removal.
c.
Halogenated
-hydrocarbon testing l
b.
The results of shall be performed 1aboratory carbon after each complete l
sample analysis
- or partial shall show 195%
replacement of the l
radioactive methyl charcoal filter l
iodide removal.
bank.
e (130*C, 954 RH).
Laboratory analysis In addition, the
-i results shall be sasple analysis of verified acceptable specification l
within 31 days 3.7.B.2.b and the following masple halogenated i
removal or the hydrocarbon test j
applicable train of shall be performed the Standby Gas after every l
Treatment system 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of normal l shall be considered system operation, i
in-operable and the requirements of d.
Each circuit shall specification be operated with 3.7.B.3 shall the heaters on at apply.
least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> J
I every month.
c.
System fans shall be shown to operate e.
An ultrasonic leak within t10% of test shall be design flow, performed on the gaskets sealing the housing panels
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downstream of the HEPA filters and J
adsorbers at least Amendment No. M, M. 143 153 i
VYNPS i
r 3.7 LIMITING CONDITIONS FOR 4.7. SURVEILLANCE REQUIRDfENTS ~
OPEPATION l
3.
a.
Freie and after the once per operating date that one cycle not to exceed circuit of the 18 months.
If the Standby Gas ultrasonic test Treatment System is indicates the made or found to be presence of a leak, inoperable for any the condition will reason, reactor be evaluated and
- peration is the gasket repaired o
permissible only or replaced as during the necessary.
succeeding seven days unless such f.
DOP and halogenotted circuit is sooner hydrocarbon test made operable, shall be performed provided that following any during such seven design modification days all active to the Standby Gas components of the Treatment System other standby gas housing that could treatment circuit have an effect on shall be operable.
the filter efficiency.
3.
b.
From and after the date that one g.
An air distribution circuit of the test demonstrating Standby Gas uniformity within Treatment System is t20% across the made or found to be HEPA filters and inoperable for any charcoal adsorbers reason, operations shall be performed requiring secondary if the SGTS housing l containment are is modified such permissible only 2at air during the distribution could I
succeeding seven be affected.
days unless such circuit is sooner 3.
a.
At least once per made operable, operating cycle provided that automatic during such seven initiation of each days all active branch of the components, Standby Gas including the Treatment System associated shall be Bnergency Diesel demonstrated.
Generator of the other standby gas b.
Operability testing treatment circuit of valves shall be i
shall be operable, in accordance with i
specification 4.
If this condition cannot 4.6.E.
be met, procedures shall be initiated immediately c.
When one circuit of to establish the the Standby Gas conditions listed in Treatment System is specifications made or found to be 3. 7. C.1 (a ) through (d),
inoperable, the 1
and compliance shall be other circuit shall completed within have been or shall 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter.
be demonstrated to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No. M, 49, H4, Me, 143 154
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3.7 (Cont'd)
-l The Standby Gas Treatment System (SGT3) is designed to filter and exhaust the Reactor Building atmosphere to the stack during secondary containment isolation conditions, with a minimum release of radioactive materials from the Reactor Building to the environs. To
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insure that the standby gas treatment system will be effective in i
removing radioactive contaminates from the Reactor Building air, the system is tested periodically to meet the-intent of ANSI N510-1975.
l Both standby gas treatment fans are designed to automatically start upon containment isolation and to maintain the Reactor Building pressure to approximately a negative 0.15 inch water gauge pressures l
all leakage should be in-leakage. Should the fan fail to start, the redundant alternate fan and filter system is designed to start automatically. Each of the two fans has 100% capacity. This substantiates the availability of the operable circuit and results in no added risk; thus, reactor operation or refueling operation can i
continue.
If neither circuit is operable, the plant is brought to a condition where the system is not required.
When the reactor is in cold shutdown or refueling the drywell may be open and the Reactor Building becomes the only containment system.
During cold shutdown the probability and consequences of a DBA LOCA are substantially reduced due to the pressure and temperature i
limitations in this mode. However, for other situations under which l
significant radioactive release can be postulated, such as during operations with a potential for draining the reactor vessel, during I
core alterations, or during movement of irradiated fuel in the l
secondary containment, operability of standby gas treatment is required. An alternate electrical power source for the purposes of Specification 3.7.B.l.b shall consist of either an meergency Diesel Generator (EDG) or the Vernon Hydro tie line. Maintaining i
availability of the Vernon Hydro tie line as an alternative to one of the EDGs in this condition provides assurance that standby gas I
treatment can, if required, be operated without placing undue constraints on EDG maintenance availability.
Inoperability of both circuits of the SGTS or both EDGs during refueling operations requires suspension of activities that represent a potential for releasing radioactive material to the secondary containment, thus t
placing the plant in a condition that minimizes risk.
Use of the SGTS, without the fan and the 9 kW heater in operation, as i
a vent path during torus venting does not impact subsequent adsorber capability because of the very low flows and because humidity control is maintained by the standby 1 kW heaters, therefore operation in this manner does not accrue as operating time.
D.
Primary containment Isolation Valves Double isolation valves are provided on lines that penetrate the primary containment and coaununicate directly with the reactor vessel and on lines that penetrate the primary containment and communicate with the primary containment free space. Closure of one of the valves in each line would be sufficient to maintain the integrity of the pressure suppression system. Automatic initiation is required to minimize the potential leakage paths from the containment in the event of a loss-of-coolant accident.
4.7 STATION CONTAINME!TP SYSTEMS A.
Primary Containment System f
The water in the suppression chamber is used only for cooling in the event of an accident, i.e.,
it is not used for normal operation; therefore, a weekly check of the temperature and volume is adequate to assure that adequate heat removal capability is present.
Amendment No, M, 49 143 166 m-.
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'miPS DEES:
3.7 (cont'd)
Tho' interiors of the drywell and suppression chamber are painted to prevent rusting. The inspection of the paint during each major refueling outage, approximately once per year, assures the paint is intact. Experience with this type of paint at fossil fueled generating stations indicates that the inspection interval is i
adequate.
Because of the large volume and thermal capacity of the suppression pool, the volume and temperature normally changes ery slowly and monitoring these parameters daily is sufficient to establish any temperature trends. By requiring the suppression pool temperature to be continually monitored and frequently logged during periods of significant heat addition, the temperature trends will be closely followed so that appropriate action can be taken. 'Ihe requirement for an external visual examination following any event where potentially high loadings could occur provides assurance that no significant damage was encountered. Particular attention should be focused on structural discontinuities in the vicinity of the relief valve discharge since these are expected to be the points of highest stress. Visual inspection of the suppression chamber including water line regions each refueling outage is adequate to detect any changes in the suppression chamber structures.
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l Amendment No. 143 166a