ML19312B957
| ML19312B957 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/16/1975 |
| From: | Thies A DUKE POWER CO. |
| To: | Purple R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7911270741 | |
| Download: ML19312B957 (4) | |
Text
NRC ISTRIBUTION FOR PART 50 DOCK MATERI AL (TEMPORARY FORM)
FILE:
FROM: Duke Power Company DATE OF DOC DATE REC'D LTR TWX RPT OTHER Chati te, NC 4-16-75 4-24-75 XX TO:
ORIG CC OTHER SENT AEC POR XX Mr Purple one signed SENT t.OCAL PDR XX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOmer Nn:
-269h0/287 XXXXXXX 1
DESCRIPTION:
ENCLOSURES:
Ler notarized 4-16-75....trans the following:
Andt to OL/ Change to Tech Specs:
Consisting of revision to delete certain reporting requirements.....(40 cys enc 1 rec 'd)
KNOWLEDGED DO NOT REMOVE PLANT NAME:
Oconee l'3 FOR ACTION /INFORMATION 5-1-75 ehf BUTLER (L)
SCHWENCER (L) ZIEMANN (L)
REGAN (E)
W/ Copies W/ Copies W/ Copies W/ Copies CLARK (L)
STOLZ (L)
DICKER (E)
LEAR (L)
W/ Copies W/ Copies W/ Copies W/ Cooies PAR R (I I V A99A LLO (L)
"N!Gu793 ;c; envis W/ Copies W/ Copics W/ Copies W/ Copics KNIEL (L)
PURPLE (L)
YOUNGB LOOD (E)
LICENSING PROJECT MANAGIR W/ Copies
'.W/6 Copies W/ Copies W/ Copies 7
INTERNAL DISTRIBUTION REG Fil C d TECH REVIEW DENTON LIC ASST.
. A/T IND t jg % FUR SCHROEDER GRIMES R. DIGGS (L)
BRAITMAN OGC ROOM P 506A MACCARY GAMMILL H. GEARIN (L)
SALTZMAN jGOSSICK/STAF F KNIGHT KASTNER E. GOU LBOURNE (L)
ME LTZ j CASE DAWLICKI BALLARD P. KREUTZER (E)
GIAMBUSSO SHAO SPANG LER J. LEE (L)
P_LANS BOYD STELLO M. MAIGRET (L)
MCDONALD MOORE (L)
HOUSTON ENVIRO S. REEO (E)
CHAPMAN DEYCUNG (L)
NOVAK MULLER M. SERVICE (L)
DUBE (Ltr)
SKOVHOLT (L)
ROSS DICKER S. SHEPPARD (L)
E. COUPE GOLLc P (L) (Ltr)
IPPOLITO KNIGHTON
,,M. SLATER (E)
PETERSON P. CO L LINS TEDESCO YOUNGBLOOD H. ST.11TH (L)
HARTFIELD (2)
DENISE J. COLLINS REGAN S. TEETS (L)
KLECKER REG OPR LAINAS PROJECT LDR G. WILLI AMS (E)
EISENHUT
/ FILE & REGION (2)
BENAROYA MO V. WILSON (L)
WIGGINTON
".?I C VOLLMER
, HARLESS R. INGRAM (L)
STCELE 4, f (
EXTERNAL DISTRIBUTION
1 - TIC (ABERNATHY) (1)(
1 - PDR SAN /LA/NY f,1 - NSIC (BUCHANAN) 1 - W. PENNINGTON, Rm E 201 GT 1 - BROOKH AVEN NAT LAB 1 - ASLB 1 - CONSU LTANTS 1 - G. U LRIKSON. ORN L 1 - Newton Anderson NEWM ARK /8 LUM E/AG B ABI AN 1 - AGMED (RUTH GUSST. TAN) td - ACRS HOLDING /SENT Rm B-127 GT f
1 - J. D. RUNKLE'S, Rm E 201 79112b /p / [
1 DUKE POWER COMPANY Powza Burz.onto 4aa Sourn Cnunca SrazzT, CHARzhTTE,N. C. aesos a e imea P. o. Box as7s tenson vice Possecast Peo0WCoom amo Teamsesissiom April 16, 1975 REGULATORY DOCKET FILE COPYq
. ;/ /
g
'f Mr. R. A. Purple, Chief
~ ;
1 s
Operating Reactors Branch 1
' '; ~
Division of Reactor Licensing C.,/,,.
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Re: Oconee Nuclear Station Docket Nos. 50-269, -270, -287
Dear Mr. Purple:
Your letter of April 3, 1975 requested additional information necessary to complete your review of my March 12, 1975 request to delete the definition of refueling period (Section 1.2.8) for Oconee Nuclear Station Technical Specifications. Attached is the listing of all Oconee Nuclear Station surveillance requirements which are specified for performance prior to, during, or after a refueling shutdown with an explanation of why they can only be/or should be performed at this time.
The one-hour discharge test of the 125 volt DC batteries required by Technical Specification 4.6.6.c, currently required during a refueling outage, does not require a refueling outage for its completion. A change to Oconee Nuclear Station Technical Specifications is hereby requested which will make this an annual surveillance item.
N Very truly yours,
/
S
/
Uc A. C. Thies g
ACT:vr v.s. ga44,ecua q
mas s.m
~g Attachment
(
b W
,$w\\\\
t
=
Mr. R. A. Purple Page 2 April 16, 1975 A. C. THIES, being duly sworn, states that he is Senior Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Atomic Energy Commission this request for amendment of the Oconee Nuclear Station Technical Specifications, Appendix A to Facility Operating Licenses DPR-38, DPR-47, and DPR-55; and that all statements and matters set forth therein are true and correct to the best of his knowledge.
A.'C.
Thies, Senior Vice President ATTEST l.,dh,E*
ohn C. Goodman, Jr.
Assistant Secretary
/
Subscribed and sworn to before me this 16th day of April, 1975
.fI
' L/
l h !. :.,> - Mis.-s >u </
l La i
Notary Public i
My Commission Expires:
]
n
/ V Y'f L i f-du..
-- a l
_)
. s SURVEILIANCE ITEMS REQUIRED DURING REFUELING OUTAGE Technical Specification 4.1.2 1.
Functional Tests and Refueling System Interlocks 2.
Functional Test of Spent Fuel Cooling System
RESPONSE
These two items are scheduled prior to refueling.
The intention is to test these systems immediately prior to their use.
Technical Specification 4.6.3 During each refueling outage for the affected unit, a simulated emergency transfer from che 4160 volt main feeder buses to the startup transformer (i.e., CT1, CT2, or CT3) to the 4160 volt standby buses shall be made to verify proper operation.
RESPONSE
The performance of this test requires a complete unit blackout for approximately four hours.
Therefore, in order to ensure adequate decay heat removal, the test must be performed at the end of a refueling interval when decay heat generation is a minimum.
During the test, the reactor vessel head is removed and the fuel transfer canal is filled to provide heat transfer.
It is concluded that this test is not feasible at times other than a refueling outage.
Technical Specification 4.7.1 The control rod trip insertion time shall be measured for each control rod at either full flow or no flow conditions following each refueling outage prior to return to power.
RESPONSE
This test is performed following refueling to assure the proper installation of control rods after the installation of the reactor vessel head.
%