ML18227B291
| ML18227B291 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/09/1978 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| L-78-262 | |
| Download: ML18227B291 (8) | |
Text
Q <</>>(W REGULATORY XNFORMATXON DISTRIBUTION SYSTEM (BIDS)
DI TRIBUTION FOR INCOMING MATERIAL
-Rlt)/251
,REC:
STELLO V NRC QRG:
UHRIG R E FL Pl'JR
& LIGl lT DOCDATE: 08/09/78 DATE RCVD: 08/14/78 DOCTYPE:
I ETTER NQTARIZED:
YES
SUBJECT:
FORWARDING REVISION TO APPI XCANT"S 07/ii/78 PROPOSED AMEND OPERATING LIC NOS DPR-31
& 41 RE PROPOSAL TO INCLUDE MOTOR 863-A AND 863-B IN TECI.I SPEC
- 3. 4. 1. A. 7 AND MODIFICATION TQ
,REQUIREMENTS...
NOTARXZED 08/09/ 7Q COPIES RECEIVED LTR 3 ENCL 40 TO FACILITY OPERATED VALVES THE SURVEIL'LANCE PLANT NAME: TURKEY PT N3 TURKEY PT 04 REVIEWER XNITIAL:
XJM DISTRIBUTER INITIAL:
wHH~'~~~H~'t>>~~>>>>
DISTRIBUTION Or-THIS MATERIAL IS AS FOl COWS>>>>>>>>>>~~>>>>>>
GENERAL DXSTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE A001) roR AcTIQN:
INTERNAL:
EXTERNAL:
BR CH~F QRBNl BC44W/7 ENCL REG FIL ~~~~W/ENCL
>>W/2 ENCL.
I<ANAUER~~+W/ENCL AD FOR SYS
& PROJ>>W/ENCL REACTOR SAFETY BR>>W/ENCL EEB<4W/ENCL J.
MCGQUGH>>W/ENCL LPDR'S MIAMI(
FL>>W/ENCL TERA44W/ENCL NSIC>>W/ENCL ACRS CAT B~~~W/16 ENCL NRC PDR>>W/ENCL OELD>>LTR ONLY CORE PERF'QRMANCE BR>>W/ENCL ENGINEERING BR+>W/ENCL PLANT SYSTEMS BR<<W/EhlCL EFFLUENT TREAT SYS>>W/ENCL DISTRIBUTION:
LTR 40 ENCL 39
'IZE:
1P+2P CONTROL NBR:
782200243
>>>>>>>>%%%>>%%>>%"l&4%4>>%%%%0M 0&4 %%9F THE END
%%%0M+NM%%>>0$ >>4%4 %%>>%>>%%'%%%%>>%'
0 il II
FLORIOA POWER & LIGHTCOMPANY August 9, 1978 L-78-262 Director of Nuclear Reactor Regulation Attention:
Nr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission llashington, D. C.
20555
Dear.Nr. Stel lo:
Re:
Turkey Point Units 3'and 4
Docket Nos. 50-250 and 50-251 Revision to Proposed Amendment to 'Facility 0 eratin Licenses DPR-31 and DPR-41 f 8 C '5W I ~s~
C/7 i
- LV
~C A proposal to include motor, operated valves 863-A and 863-B in Technical
.Specification 3.4..l.a.7 and to. modify the surveillance requirements of Technical Specification 3.4.1.b.7 was forwarded to your office on July ll, 1978 (L-78-233).
Upon re-review of our submittal, we have determined that further revision of Technical Specification 3.4.l.b.7 is needed to permit temporary operation of the specified valves under a variety of circumstances.
The purpose of this revision is to provide maximum flexibilityfor the surveill'ance and maintenance of va'ives which, normally have the motive power source removed from their operating mechanisms.
The revised Specification 3.4.l.b.7 is attached.
The PNSC and.
CNRB have reviewed this revision and have concluded that, it does not involve an unreviewed safety question.
Very t ly yours, Robert E. Uhrig Vice Presi dent REU/NAS/cpc Attachment cc:
t1r.
James P. O'Reilly, Region II Robert Lowenstein, Esquire 782200243 PEOPLE... SERVING PEOPLE
4>>
l
0-5.
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 demonstrate 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 3.4.1.a.7 may be unlocked and may have supplied air or electric power restored for a period 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 CONTAINMENT COOLING SYSTEMS a.
The reactor shall not be made critical, except for low power physics tests, unless the following conditions are met:
1.
THREE emergency containment cooling units are operable.
2.
TWO containment spray pumps are operable.
3.
ALL valves and piping associated with the above components, and required for post accident operation, are operable.
b.
During power operation, the requirements of 3.4.2a may be modified to allow one of the following components to be inoperable (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 requirements 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
JI
-.Ig
STATE OF 'FLORIDA
)
)
ss COUNTY OF DADE
)
Robert E. Uhrig, being first duly sworn, deposes and. says:
That he is a Vice President of Florida Power 6 Light. Company.,
the Applicant herein:
That he has executed the foregoing document; that the statements made in this said document are true and correct to the best. of his knowledge, information and belief, and that he is authorized to execute the document on behalf of said Applicant.
Robert E. Uhrig Subscribed and sworn to before me this day of NOTARY PUBLIC, and for the County of Dade, State of Florida My commission expires:
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