ML20038C150
| ML20038C150 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 11/20/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20038C147 | List: |
| References | |
| NUDOCS 8112100160 | |
| Download: ML20038C150 (8) | |
Text
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION e
WASHtNGTON, D. C. 20555
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CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213
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HADDAM NECK PLANT p
s AMENDMENT TO FACILITY OPERATING LICENSE' Amendment No. 44 L canse No. DPR-61
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1.
The Nuclear Regulatory Commission (the Commission),has found that:
A.
The applications for amendment by Connecticut Yankee Atomic Power Company (the licensee) dated August 27, 1980 and April 16, 1981, as supported by letters dated November 30 and December 4 and 6, 1979, January 17 and 30, April ll, May 19, June 10 and September 29, 1980, May 26, June 30, August 14, August 27 and September 9,1981, comply 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 CFP, Chapter I; B.
The facility will operate in conformity with the applications 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 without endangering the health and safety af 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 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.
8112100160 811120 S PDR ADOCK 05000213-P PDR
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. 2.
Accordingly, the license is amenddd by changes to the Technical E,
Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C(2) of Facility'0perating License No. DPR-61 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 44, 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.
FOR THE NUCLEAR REGULATORY COMMISSION A-Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 20, 1981
ATTACi1 MENT TO LICENSE AMENDMENT NO. 44 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET N0. 50-213 Replace the following pages of the Appendix A Technical Specifi ations with the enclosed _pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 3-12 3-12 3-13 3-13 3-13A 3-13B 4-17 4-17 4-17A*
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- Included for pagination purposes only s.
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3.8 WRBINE CYC17.
Applicability:
Applies to the operating status of turbine cycle ecesponents for removal of reactor core decay beat.
Obj ective :
To specify conditions of the turbine cycle equipment necessary to insure the capability to reove decay heat fra the reactor core.
Specification:
A.
The reactor shall not be critical (escept for determination of "just critical" rod position and low power physics tests at or below 10 percent of full power) unless the following conditions are met:
1.
A minimum turbine cycle steam relieving capability of 7,000,000 lb/ hour up to and ir.cluding 1473 NWt and at power levels in excess of 1473 MWt a minimum turbine cycle steam relieving capability of 9,504.000 lbs-per-hour shall be available.
2.
a.
Two staan-driven auxiliary feedwater pumps operable or; b.
With one auxiliary feedwater pump inoperable, restore the inoperable auxiliary f eedwater pump to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOW within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
s s
c.
With both auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to
'-~
OPERABLE status as soon as possible l
and reduce power within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the lowest stable power level consistent with reliable main feedwater system
's operation.
3.
a.
The domineralized water storage tank (DWST) shall be OPERABLE with a g
N minima contained volume of 50,000 gallons of water and the primary water storage tank (FWST) shall be
' -. s WERABLE with a minimum contained volume of 80,000 gallons of water or; b.
With the DWST inoperable, restore N
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the DWST to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT 3:
SETTDOW within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or;
's v
With the PWST inoperable, within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s:
c.
+
1.
Restore the PWST to OPERABLE status, or s
s.
'3-12 Amendment No. #,JA,44 N '
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2.
Provide an equivalent supply from an alternate source, or; if 3.
Be in at least BOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the foliowing I
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
4.
System piping and valves directly associated with the above; componsats operable.
s B.
1.
The auxiliary feedwater actuation syntaa instrumentation shall be operable as shown in Table 3.8-1 except that one steam generator vide range level channel at a time may be resoved from service for surveillance testing as required.
2.
The auxiliary feedwater actuation system contacts and relays from the main steam generator feed pump breakers shall be operable whenever the auxiliary feedwater systan is in au tomatic.
Basis:
A reactor trip from power requires subsequent removal of core decay heat. Isumediate decay heat removal requirements are normally satisfied by the stem bypass to the condensers. Thereafter, core decay heat can be continuously dissipated via the steam bypass to the condenser as feedwater in the steam generator is converted to steam by heat absorption. Normally, the-capability to return feedwater flow to the steam generators is provided by operation of the turbine cycle feedveter system.
AmendmentNo.[,44 3-13
In the event the main feedwater system should fail, the auxiliary system is aut matically initiated upon coincidence,.
in either train, of any 2 out of 4 steam generator low low level signals or the coincidence of both electric driven main feed pmp circuit breakers being open if in the automatic mode. Feedwater to the steam generators is maintained by the auxiliary feedwater system, consisting of 2 steam driven, auxiliary steam gererator feedwater p eps.
In addition, the auxiliary feedwater system can be initiated manually. In this case, feedwater is available from the demineralized water storage tank by gravity feed to the auxiliary feedwater pump. The specified 50,000 gallons of water in the demineralized water storage tank is adequate for decay heat removal for a period of at least two hours.
Within this period, decay heat removal demands are reduced to approximately 150 gpm. Makeup water is available during this period fr a the primary water storage tank which con-tains a minimjm volme of 80,000 gallons. The primary water transfer p mps can transfer 200 gpm from the primary water tank to the demineralized water tank. An alternate supply can be provided from the 100,000 gallon capacity Recycled Primary Water Storage Tank.
A steam relieving capability of 7,000,000 lbs-per-hour is
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required at power levels up to and including 1473 W t to maintain the pressure in turbine cycle components within A9fE code allowable values in the event of a full load rejection at 1473 W t, without a reactor trip or other control action and without feedwater flow to the steam generators. Similarly, at 1825 Et, a steam relieving capacity of 9,504,000 lbs-per-hour is required to maintain the pressure in turbine cycle components within code values in the event of a full load rejection at 1825 W t.
References:
(1) FDSA Section 8.1 (2) FDSA Section 8.3 3-13A Amendment No. 44
l TABLE 3.8-1 AUT(MATIC AUXILIARY FEEDWATER SYSTEM ACnlATION INSTRUMENTATION TUTAL NO.
CHANNELS TO MINIMUM
. APPLICABLE ACTION FUNCTIONAL UNIT OF CHANNELS ACTUATE SYS.
CHANNELS MODE REQUIRED a) Manual
,2 1
1 1,2,3,4 1
2/4/ rain 4
1, > 10%*
2 4/ rain b) Automatic steam generator T
T I
wide range level 4 loops 2/3/ rain 3
1.P 10%*
2 c) Autcastic eteen generator 3 / Train T
wide range level 3 loops d) Autamatic main steam 7
2/2 2
1, > 101 1
generator feed pump breakers N
&g Action Statement:
1.
Maintain Mode 3 or 4 c>
g 2.
Place inoperable channel in trip condition when declared inoperable.
- For surveillance testing purposes, the train being tested will be placed in " manual" function.
3-138
o.
4.8 AUXILIARY STEAM GENERATOR FEEIMATER SYSTIN Applicability:
Applies to periodic testing requirements of the steam-driv a auxiliary steam generator feedwater system.
Objective:
To verify the operability of the auxiliary steam generator feedwater system and its ability to respond properly when required.
Specification:
1.
The auxiliary feedwater system shall be demonstrated OPERABLE at least once per 31 days by:
Verifying that each steam turbine driven pep a.
develops a discharge pressure of greater than or equal to 800 psig at a steam supply pressure of 300 psig.
b.
Functionally testing the automatic auxiliary feedwater initiation steam generator level instr mentation channels and their logic.
Verifying that each non-s tomatic valve in the f
c.
flow path that is not locked, sealed, or other-wise secured in position, is in its correct position.
2.
The DWST and PWST shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the contained water volme is within its limits.
3.
At refueling intervals, the auxiliary feedwater system shall be demonstrated OPERABLE by:
Verifying the capability of each pump to a.
attain rated flow of 450 gpm at 1050 psig.
I l
b.
Verifying that each automatic valve in the flow path actuates to its correct position u p.
receipt of each auxiliary feedwater actuation test signal.
Verifying that each auxiliary feedwater pump c.
starts as designed automatically upon receipt of each auxiliary feedwater actuation test l
signal.
Basis:
The monthly testing program will verify the operability of the auxiliary steam generator feedwater system. The refueling interval test will verify the capability of the turbine drive and pump to attain rated flow. A flow rate of 450 gpn is sufficient to prevent the steam generators from boiling dry during a period of coincident loss of offsite power and maximum decay heat removal requirenents.
AmendmentNo.g,j4,44 4-17
Proper functioning of the steam admission valve and subsequent pmp start will demenstrate the integrity of the system. Verification of correct.
operation will be made both from instnamentation within the main control room and direct visual observation of the pump.
Reference:
(1) FDSA - Section 8.3 4-17A
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