ML17341B502
| ML17341B502 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 11/05/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| Shared Package | |
| ML17341B503 | List: |
| References | |
| NUDOCS 8211190309 | |
| Download: ML17341B502 (10) | |
Text
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Docket Nos. 50-250 and 50-251 Dr. Robert E. Uhrig, Vice President Advanced Systems and Technology
- Florida Power and Light Company Post Office Box 529100 Miami, Florida 33152
Dear Dr. Uhrig:
RE:
Single Failure - ECCS Valves NV OS 1982 DISTRIBUTION Docket NRC PDR L PDR NSIC ORB¹1 Rdg DEisenhut OELD JMTaylor ELJordan CParrish DMCDonald RBarr ett
- MKennedy, PTRB
- JKnight, PSB Gray The staff has completed its review of your submittals dated June 22, 1978, July ll, 1978 and August 9, 1978, relating to the above referenced safety concern.
Your submitttals propose. changes to the Technical Specifications for Turkey Point Plant, Units 3 and 4.
The enclosed safety evaluation concludes that the proposed changes to the Technic51 Specifications constitute a safetand reliable method of eliminating a single failure.
flowever, the acceptability of the changes are contingent on providing the following:
1.
The procedures for reinstating power during a LOCA shall include the fol11owing elements:
(a) a nuclear or nuclear-turbine operator must be assigned to each of the two Motor Control Cinters such that successful action on the.part of either operator is sufficient to allow switchover to r ecirculation, (b) these operators should be dispatched to their respective ttCC's as soon as a
LOCA has been identified, (c) they should have no other responsibilities until switchover to recirculation is
- complete, (d) power should n& be reinstated until the low level (115,000 gal) on the INST is reached and (e) this procedure should be emphasized in the training and reqdBification of nuclear operators and nuclear-turbine operators.
2.
Single continuous positive indication for valves 862 A&9, 893 A&B and 864 AR.
In addition, the procedures used for removal ofppowerrfrom the above valves shall include the requirements for visual verification of the proper valve position prior to power removal.
3.
The responses to our request for confkrmation of the items identified in our letter dated October 13, 1982.
lie will finalize our review and issue a supplement to the Safety evaluation upon resolution of the above items.
i'alil9asO9 82iiO5" PDR ADOCK 05000250 P
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PDR OFFICEI SURNAME/
DATE$
NRC FORM 318 (10-80) NRCM 0240
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Dr. Robert.E. Uhrig 2
This response is requested within 60 days from the date of this letter.
This letter affects fewer than ten respondents; therefore, OMB clearance is not required under P. L.96-511.
Enclosures:
1.
Proposed Technical Speci fication Changes 2.
Safety Evaluation cc w/enclosures:
See next page Sincerely,,
@~1 si""-d by.!
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Steven A. Varga, Chief Operating Reactors Branch ¹I O'Jvi sion of Licensing OFFICES SURNAME/
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Robert E. Uhrig Florida.Power and Light Company cc:
Harol d F.
Re is,, Esqui re Lowenstein, Newman, Reis and Axelrad 1025 Connecticut
- Avenue, N.W; Suite 1214 Washington, D.
C.
20036 Norman A. Coll, Esquire
- Steel, Hector and Davis 1400 Southeast First National Bank Building Miami, Florida 33131 Mr. Henry Yaeger, Plant Manager Turkey Point Plant Florida Power and'ight Company P. 0.
Box 013100 Miami, Florida 33101 Mr. Jack Shreve Office of the Publ'ic Counsel Room 4, Holland Building Tallahassee, Florida 32304 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Resident Inspector Turkey Point Nuclear Generating Station U. S. Nuclear Regulatory Commission Post Office Box 1207
'Homestead, Florida 33030 James P. O'Reilly Regional Administrator - Region II U. S. Nuclear Regulatory Commission
.101 Marietta Street - 'Suite 3100 Atlanta, Georgia 30303
41
0 ENCLOSURE li IVO residual heat removal pumps sha11 be, operablc.
"5.
TWO residual heat exchangers shall be operable I
- 7. Allvalves, interlocks and piping associated with the above compon nts and required for po t accident operation, shall be operable, except valves that are positioned. and locked.
Valves 862-A&B:
863-A&B; 864-A&B; 865-A.BKC; 866-A&B shall have power removed from their motor operators by locking open the circuit breakers at the Hotor Control Centers.
The air supply to valve 758 shall be shut, off to the valve operator.
b.
'During poMer operation, the requirements of 3.4 la may be modified to allov one of the following com-ponents to be inoperable (including associated valves and piping) at any one tIme except. for the cases stated In 3.4.1.b.2. If the system is not restored to meet the requirements of 3.4.Lx within the time period
.specified, the reactor shall be placed in the hot shutdown condition. If the requirements of 3.4.la are not satisfied within an.additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the 4
reactor shall be placed in the cold shutdown condition 1
ONEaccumulator may be out of service for a period of up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
2.
ONE of FOUR safety Ixijcction pumps may be out of service for 30 days.
A second safety in-
/ection pump may be out of service, provided the pump is restored to'perable*status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
TWO of -the POUR safety injection pumps shall be 'tested to demon'strate operability before.
initiating maintenance of the inoperable pumps-3.
ONE channel of heat tracing on the flow path may be out of service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
'.4-2
Qt
5.
ONE residual heat exchanger.
may be out of service for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
6.
Any valve in the system may be inoperable pro-vided repairs are completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.-
Prior to initiating maintenance, all valves that provide the duplicate function shall be tested to d monstrate operability.
7.
To. permit temporary operation of the valve, e.g., for surveillance of valve operability, for the purpose of valve maintenance, etc.,
the
-valves specified in 3.4.l.a.7 may be unlocked and may have supplied air or e'jectric power restored fear a ~ried'not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
EMERGENCY COf)TAINt<ENT COOLING SYSTEMS a.
The reactor shall not be made critical, except for low power physics tests, unless the following conditions are met:
b.
1.
THREE em rgency containman cooling units are operable.
2.
TVO containment, spray pumps are operable.
3.
ALL valves and piping associated with the above components, and required for post accident operation, are operable.
During. power operation, the requirements of 3.4.2a may be nodified to allow one of the following components to be inoperab1e (including associated valves and piping) at any one. time. 'If the system is not restored to meet the requirements of 3.4.2a within. the time period. specified, the reactor shall be placed in the hot shutdown condition.
If the requiremonts of 3.4.2a are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in 'the cold. shutdown.
condition.
3.4-3
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