ML19317F747
| ML19317F747 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/15/1978 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001230651 | |
| Download: ML19317F747 (3) | |
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'O REGULATORY INFORMATION 131s t hibu fl0N SYSTEM (RIDS)
DISTRISUTION FOR INCOMING MATERIAL 50-346 FEC-STCLZ J F ORG: ROE L E DOCDATE: 06/15/78 NRC
'JLEDO EDISON DATE RCVD: 06/19/78 OCCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED SUDJECT:
LTR 1 ENCL 0 FURNIS: LING REQUEST FOR AN EXTENSION ON THE REQUIRED DATE BY WHICH TO PERFORM T!'E NATUPP.L CIr.:ULATION TEST ON SUBJECT FACILITY, UNIT 1.
PLANT NAME. DAVIS EESSE - UNIT 1 REVIEWER INITIAL:
XJM DISTRIBUTOR INITIAL:
- r"p ********** DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ********+*********
NOTES:
1.
JEND ALL AMENDMENTS TO J.
ROE PSAR/FSAR AMDTS AND ' ELATED CORESPCNDENCE (DISTPISUTION CODE B001)
FOF ^CTTON.
ASST OIR VASSALLO**LTR ONLY(1)
BR CHIEF LWR #1 BC**LTR ONLY(1)
FROJ M 1 ENGLE*4LTR ONLY(1)
LIC ASST LWR #1 LA**LTR ONLY(1)
INTERNAL.
U LTR ONLY(1)
NRC PDR**LTR ONLY(1)
- i a d**LTR ONLY(2)
OELD**LTR ONLY(1)
OPERATOR LIC BR**LTR ONLY(1)
EMERGENCY PLAN BR**LTR ONLY(1)
CASHLTR ONLY(1)
DIRECTOR NRRML'R ONLY(1)
MIPC**LTR ONLY(1)
AD FOR ENG**LTR ONLY(1)
MECH ENG BR**LTR ONLY(1)
STRUCTURAL ENG BR**LTR ONLY(1)
MATERIAL ENO BR+*LTR ONLY(2)
AD FOR REAC SFTY**LTR ONLY(1)
REACTOR SYSTEMS BR**LTR ONLY(1)..NALYSIS BR**LTR ONLY(1)
CORE PEcFORMANCE ER**LTR ONLY(1 AD FOR PLANT SYSTEMS **LTR ONLY' AUXILIARY SYS BR**LTR ONLY(1)
CONTAINMENT SYSTEMS **LTR ONLY(1 I & C SYSTEMS ER**LTR ONLY(1)
FCWER SYS BR**LTR ONLY(1i AD FOR SITE TECH **LTR ONLY(4)
AD FOR SITE ANLYi+*LTR ONLY(1)
ACCIDENT ANALYSIS **LTR ONLY(1)
EFFLUENT TREAT SYS**LTR ONLY(1:
RAD ASSESSMENT BR**LTR ONLY(1)
KIRKWOOD**LTR ON.Y(1)
J 7"C S EXTERNAL.
LPCR'S j./p agg P T.
CLINTON, OH**LTR ONL7(1)
J ret.4 0 TIC **LTR ONLY(1) 6//hNOT NSIC**LTR ONLY(1)
MN ACRC CAT B**LTR ONLY(16)
N4 JAP 8ifrV4'd bW $*V N 66.8 Le4C DISTRIEUTION:
LTR 56 ENCL 0 CONTROL NER:
'91'2C _. T SIZE: 2P o w *
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- THE END
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TLEDO Docket No. 50-346 i!DISO N Operating License No. NPF-3 LOWELL E. ROE v.e. ar.....n.
Serial No. 448 r.c.ni... c....or.a.
14191 259-5242 June 15, 1978 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz, Chief Light Water Reactors Branch No. 1 Division of Projec: Management U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Stolz:
As related to your Licensing Project Manager, Mr. Leon Engle, by our Mr. George Hurrell in a telephone conversation on June 14, 1978, Toledo Edison requests an extension on the required date by which we must perform the Natural Circulatica Test on the Davis-Besse Nuclear Power Station Unit No. 1.
Mr. Roger S. Boyd's letter dated February 16, 1978 allowed us to proceed to 100% power but required that the Natural Circu-lation Test be performed at the first opportunity and within 120 days from the date of his letter (June 16, 1978). Unfortunately the problems encountered with the Burnabic Poison Rod Assemblies prevented any oppor-tunity for performance of the Natural Circulation Test, and the test will not be performed prior to June 16, 1978.
We request that the required date by which the Natural Circulation Test must be performed be extendad to the time at which Davis-Besse Nuclear Power Station Unit No. I has operated at 150 effective full power days.
(The present core burnup is approximately 90 effective full power days.)
This extension request is required to allow the Natural Circulation Test to be performed when the moderator temperature coefficient at hot zero power condition is zero or slightly negative. Until approximately 120 effective full power days of operation, the moderatcr temperature coeffi-cient at hot zero power will be slightly positive as stated in the
" Attachment 1 to Application to Amend Operating License for Removal of Burnable Poison Rod Assemblies" which was transmitted to you in o'tr letter dated May 18, 1978. Performance of the Natural Circulatio Test with a positive moderator ter?erature coefficient with the reactor at less than 5% power and no reactor coolant pumps running would result in an unstable condition. The Natural Circulation Test should therefore be performed at the first opportunity when the hot zero power moderator temperature coefficient is zero or slightly negative (120 effective full power days) but no later than 150 effective full power days.
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THE TCLEDO EOISON COMPANY EDISON PLAZA 300 MAOISON AVENUE TOLEDO. OHIO 43652 S#gy
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We believe that this further extension is justified, as was the first extension, by the results of the completed Oconee No. 1 tests and our calculations which demonstrate that the Davis-Besse Unit I raised loop design will have natural circulation flow at least comparable to the Oconee No. I tests.
Yours very truly, bj c/5 2
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