ML19317F745
| ML19317F745 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/13/1978 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001230648 | |
| Download: ML19317F745 (2) | |
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REGULATORY INFORMATION DISTRIBU' ION SYSTEM (RIDS)50-346 D*STRIBUTION FOR INCOMING MATERIAL DOCDATE: 06/13/78 REC: STCLZ JF ORG: ROE L E DATE RCVD: 06/19/79 TOLEDO EDISON NRC COPIES RECEIVED COCTYPE: LETTER NOTARIZED: NO LTR 1 ENCL O
SUBJECT:
FURNISHING APPLICANT"S AGREEMENT TO DO A MEASUREMENT TO DETERMINE THE TEMFERATURE COEFF ICIENT WHEN CONTROL r.OD GROUF 7. IS WITHDRAWN AT MODERATOR 143 PLUS-MINUS 5 EFFECTIVE FULL PWR DAYS & CHANGE SECTION 8.2.3 CF 05/1 PROPSED TECH SPEC CHANGE RE BURNA6L4 90ttscA) PJI) MT(# M$g8,,(
REVIEWER INITIAL:
XJM PLANT NAME: DAVIS EESSE - UNIT 1 DISTRIBUTOR INITI AL: ff./
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DISTRIEUTION OF THIS MATERIAL IS AS FOLLOWS **** e n*** o o NOl IS :
1.
SEND ALL AMENDMENTS TO J.
ROE PEAR /FSAR AMDTS AND RE,;TED CORESPONDENCE (DISTRIEUTION COCE B001)
FOP ACTION:
AS?T DIR VASSALLO**LTR ONLY(1)
GP CHIEF LWR 91 FC**LTR ONLY(1 PRO.f
- N ENGLE*4LTR CMLY(1)
LIC ASGT LWR #1 LA*+LTR ONLY(1 INTERNAL:
PEG FILE 4x.TR ONLY(1)
NRC PDR**LTR ONLY(1)
OELDHLTR ONLY(1) c-s(R ONLY(2) 1 OPERATOR LIC ER**LTR ONLY(1)
EMERGENCY PLAN ER44LTR ONLY(1 DfRECTOR NPReLTR ONLY(1)
OAB**LTR ONLY(1)
AD FOR ENG4*LTR ONLYt1)
MIPC**LTR ONLY(1)
MECH ENO BR**LTR ONLY(1)
STRUCTURAL ENG BR++LTR ONLY(1 idATERIAL ENG BR*4LTR ONLY(2)
AD FOR REAC SFTY**LTR ONLY(1)
REACTOR SYSTEMS BR**LTR ONLY(1) ANALYSIS ER**LTR ONL((1)
CORE PERFORMANCE ER4*LTR ONLY(1 AD FOR PLANT SYSTEMS ++LTR AUX ILI ARY SYS ER t'*LTR ONLY( 1 )
CONTAINMENT SYSTEMS *LTR ONLY I & C SYSTEMS BR F LTR ONLY(1)
POWE.i SYS ER*4LTR ONLY(1)
AD FOR SITE TECH *rLTR ONLY(4)
AD FOR SITE ANLYS*LTR ONLY(1 ACCIDENT ANALYSIS *4LTR ONLY(1)
EFFLUENT TREAT EYS++LTR ONL
RAD ASSESSMENT ER nLTR ONLY(1)
KIPKWOOD**LTR CNLY(1)
);t40M//2 EXTERNAL:
LPDR'S 572E(_c0
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CLINTON. OH*4LTR ONLY(1) 6//d #/ M i
r gpG/vaarp6 BC gggcfog,5g/ dry 64.}i TIC **LTR ONLY(1)
NSIC*4LTR ONLY(1)
ACRS CAT E**LTR ONLY(16) fppj7fy5 44 EEA 1642 i i
CONTROL NER:
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DISTRIEUTION:
LTR 56 ENCL 0 SIZE: 1P
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THE END BOO 12.3 0h
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TOLEDO
%mm EDISON Docket No. 50-346 LOWELL E. ROE vice President License No. NPF-3 (4191 259-5242 June 13, 1978 Serial No. 446 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz, Chief Light Water Reactors Branch No. 1 Division of Project Management United States Nuclear Regulatory Co= mission Washington, D. C.
20555
Dear Mr. Stolz:
As discussed on the telephone with your Licensing Project Manager (Mr.
Leon Engle), Toledo Edison agrees to do a measurement to determine the moderator temperature coefficient when Control Rod Group 7 is withdrawn at 145 + 5 effective full power days.
In addition, Toledo Edison agrees to change the last sentence of Section 8.2.3 of " Attachment I to Application to Amend Operating License for Removal of Burnable Poison Rod Assemblies", as originally given you in our letter dated May 18, 1978 (Serial No. 435). The revised sent'ence will read as follows:
"The worth of control group 5 from the rod insertion limit to fully inserted and control group 4 will be measured, and acceptance criterion 2 will be applied to the sum of groups 7, 6, 5 and 4".
Yours very truly,
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THE TOLECO EDISON CCMPANY EDISCN PLAZA 300 MADISCN AVENUE TOLEDO. CHIO 43652 6
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