ML19317F740: Difference between revisions
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,l O fo 0 4 / '/ V REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) | ,l O fo 0 4 / '/ V REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) | ||
DISTRIBUTION FOR INCOMING MATERIAL 50-346 REC: STOLZ J F ORG: POC L E DOCDATE: 06/02/78 NRC TOLEDO EDISON DATE RCVD: 06/06/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED | DISTRIBUTION FOR INCOMING MATERIAL 50-346 REC: STOLZ J F ORG: POC L E DOCDATE: 06/02/78 NRC TOLEDO EDISON DATE RCVD: 06/06/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED | ||
| Line 29: | Line 27: | ||
: 1. SEND ALL AMENDMENTS TO J. ROE PSAR/FSAR AMDTS AND RELATED CORESPONDENCE (DISTRIBUTION CODE BOO 1) | : 1. SEND ALL AMENDMENTS TO J. ROE PSAR/FSAR AMDTS AND RELATED CORESPONDENCE (DISTRIBUTION CODE BOO 1) | ||
FOR ACTION: ASST DIR VASSALLO**LTR ONLY BR CHIEF LWRiti BC++LTR ONLY PRO. ' 1R ENGLE**W/ ENCL LIC ASST HYLTON**LTR ONLY INTERNAL: REG FILC W/ ENCL NRC PDR**W/ ENCL | FOR ACTION: ASST DIR VASSALLO**LTR ONLY BR CHIEF LWRiti BC++LTR ONLY PRO. ' 1R ENGLE**W/ ENCL LIC ASST HYLTON**LTR ONLY INTERNAL: REG FILC W/ ENCL NRC PDR**W/ ENCL | ||
*W/2 ENCL OELD**LTR ONLY OPERATOR LIC BR**W/ ENCL EMERGENCY PLAN BR**W/ ENCL QAB**W/ ENCL CASE **LTR ONLY MIPC**LTR ONLY AD FOR ENG**LTR ONLY MECH ENG BR**W/ ENCL STRUCTURAL ENG BR**W/ ENCL MATERIAL ENG BR**W/2 ENCL AD FOR REAG SFTY**LTR ONLY REACTOR SYSTEMS BR**W/ ENCL ANALYSIS BR**W/ ENCL CORE PERFORMANCE CR**W/ ENCL AD FOR PLANT SYSTEMS *+LTR ONLY AUXILI4RY SYS BR**W/ ENCL CONTAINMENT SYSTEMS **W/ ENCL I 8e C SYSLIMC BR**W/ ENCL POWER SYS GR**W/ ENCL AD FOR SITE TECH **W/4 ENCL AD FOR SITE ANLYS**LTR ONLY ACCIDENT ANALYSIS **W/ ENCL EFFLUENT TREAT SYS**W/ ENCL RAD ASSESSMENT BR**W/ ENCL KIRKWOOD**W/ ENCL EXTERNAL: LPDR'S ST-G Ll o f E40-MAdAVE2 W EMCb PT. CLINTON, OH**W/ ENCL y TIC **W/ ENCL ENG AJE6(fi A G OE-NSIC**W/ ENCL fe Acret 5 A FeW 8E W/N ACRS CAT B**W/16 ENCL gp g g gQ E.E B v3 / E 9cc c/L % . | *W/2 ENCL OELD**LTR ONLY OPERATOR LIC BR**W/ ENCL EMERGENCY PLAN BR**W/ ENCL QAB**W/ ENCL CASE **LTR ONLY MIPC**LTR ONLY AD FOR ENG**LTR ONLY MECH ENG BR**W/ ENCL STRUCTURAL ENG BR**W/ ENCL MATERIAL ENG BR**W/2 ENCL AD FOR REAG SFTY**LTR ONLY REACTOR SYSTEMS BR**W/ ENCL ANALYSIS BR**W/ ENCL CORE PERFORMANCE CR**W/ ENCL AD FOR PLANT SYSTEMS *+LTR ONLY AUXILI4RY SYS BR**W/ ENCL CONTAINMENT SYSTEMS **W/ ENCL I 8e C SYSLIMC BR**W/ ENCL POWER SYS GR**W/ ENCL AD FOR SITE TECH **W/4 ENCL AD FOR SITE ANLYS**LTR ONLY ACCIDENT ANALYSIS **W/ ENCL EFFLUENT TREAT SYS**W/ ENCL RAD ASSESSMENT BR**W/ ENCL KIRKWOOD**W/ ENCL EXTERNAL: LPDR'S ST-G Ll o f E40-MAdAVE2 W EMCb PT. CLINTON, OH**W/ ENCL y TIC **W/ ENCL ENG AJE6(fi A G OE-NSIC**W/ ENCL fe Acret 5 A FeW 8E W/N ACRS CAT B**W/16 ENCL gp g g gQ E.E B v3 / E 9cc c/L % . | ||
DISTRIBUTION: LTR W ENCL . CONTROL NER: '9-15?^nAS i SIZE: 1P+1P coco ******************************* THE END | DISTRIBUTION: LTR W ENCL . CONTROL NER: '9-15?^nAS i SIZE: 1P+1P coco ******************************* THE END | ||
[M | [M | ||
*****************************+++++- | *****************************+++++- | ||
800123 o hg | 800123 o hg | ||
A 4 l l | |||
A | |||
4 l l | |||
TOLEDO | TOLEDO | ||
%mm EDISON LOWELL E. ROE Docket No. 50-346 - | %mm EDISON LOWELL E. ROE Docket No. 50-346 - | ||
5.c,.... c . . -.a. | 5.c,.... c . . -.a. | ||
'"8'85'58'' | '"8'85'58'' | ||
| Line 56: | Line 43: | ||
As discussed between our Mr. F. R. Miller and your Licensing Project Manager, Mr. Leon Engle on May 30, 1978, Page 7-24a of the Revision 1 to the " Davis-Besse Nuclear Power Station Unit No. 1, Attachment 1 to Amend Operating License For Removal of Burnable Poison Rod Assemblies and Orifice Rod Assemblies," as submitted to you in my letter dated May 26, 1978 is in error. Twelve copies of the corrected page are attached. We apologize for any inconvenience this error may have incurred. | As discussed between our Mr. F. R. Miller and your Licensing Project Manager, Mr. Leon Engle on May 30, 1978, Page 7-24a of the Revision 1 to the " Davis-Besse Nuclear Power Station Unit No. 1, Attachment 1 to Amend Operating License For Removal of Burnable Poison Rod Assemblies and Orifice Rod Assemblies," as submitted to you in my letter dated May 26, 1978 is in error. Twelve copies of the corrected page are attached. We apologize for any inconvenience this error may have incurred. | ||
Very truly yours, | Very truly yours, ks c/8 Attachments Y .. Jg. | ||
ks c/8 Attachments Y .. Jg. | |||
THE TOLECO EDISCN COMPANY EDISCN PLAZA 300 MACISCN AVENUE TOLEDO. CHIO 43652 bo*'& | THE TOLECO EDISCN COMPANY EDISCN PLAZA 300 MACISCN AVENUE TOLEDO. CHIO 43652 bo*'& | ||
+ | + | ||
45 hetsk _ | 45 hetsk _ | ||
T TABLE 3.2-1 ~ | |||
T | |||
TABLE 3.2-1 ~ | |||
E | E | ||
* 5 DNB MARGItl . | * 5 DNB MARGItl . | ||
\" I g . | \" I g . | ||
LIMITS a . | LIMITS a . | ||
.'" Four Reactor c. | .'" Four Reactor c. | ||
Three Reactor One Reactor Coolant Pumps Coolant Pumps Coolant Pump 5 - Parameter Opera ting Opera tinq | Three Reactor One Reactor Coolant Pumps Coolant Pumps Coolant Pump 5 - Parameter Opera ting Opera tinq | ||
-4 Operating in Each Loop 7 -" Reactor Coolant llot Leg < 611.1 < 611.l II) y Temperature T *F < 611.1 o 11 ReactorCoolantPressure,psig.I2) > 2062.7 * | -4 Operating in Each Loop 7 -" Reactor Coolant llot Leg < 611.1 < 611.l II) y Temperature T *F < 611.1 o 11 ReactorCoolantPressure,psig.I2) > 2062.7 * | ||
> 2058.7(I) | > 2058.7(I) | ||
' > 2091.4 Reactor Coolant Flow Rate, gpm (3) >_ 395,700 > 296,500 > 195,200 l | ' > 2091.4 Reactor Coolant Flow Rate, gpm (3) >_ 395,700 > 296,500 > 195,200 l u , | ||
u , | |||
i | i | ||
. '?_ | . '?_ | ||
\ | \ | ||
03 i | 03 i | ||
| Line 101: | Line 67: | ||
; $ of RATED TitERMAL POWER. | ; $ of RATED TitERMAL POWER. | ||
(3) These flows include a flow rate uncertainty of 2.2%. | (3) These flows include a flow rate uncertainty of 2.2%. | ||
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _}} | _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _}} | ||
Revision as of 06:52, 1 February 2020
| ML19317F740 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/02/1978 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001230642 | |
| Download: ML19317F740 (3) | |
Text
.
,l O fo 0 4 / '/ V REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-346 REC: STOLZ J F ORG: POC L E DOCDATE: 06/02/78 NRC TOLEDO EDISON DATE RCVD: 06/06/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 12 FORWARDING CORRECTED PAGE TO APPLICANT"S 05/26/78 SUBMITTAL CONSISTING OF AMEND TO OPERATING LIC FOR RENEWAL OF BURNABLE POISON ROD ASSEMBLIES AND ORIFICE ROD ASSEMBLIES.
PLANT NAME: DAVIS BESSE - UNIT 1 REVIEWER INITIAL: XJM DISTRIBUTOR INITI AL: (
oc*oo************ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
NOTES:
- 1. SEND ALL AMENDMENTS TO J. ROE PSAR/FSAR AMDTS AND RELATED CORESPONDENCE (DISTRIBUTION CODE BOO 1)
FOR ACTION: ASST DIR VASSALLO**LTR ONLY BR CHIEF LWRiti BC++LTR ONLY PRO. ' 1R ENGLE**W/ ENCL LIC ASST HYLTON**LTR ONLY INTERNAL: REG FILC W/ ENCL NRC PDR**W/ ENCL
- W/2 ENCL OELD**LTR ONLY OPERATOR LIC BR**W/ ENCL EMERGENCY PLAN BR**W/ ENCL QAB**W/ ENCL CASE **LTR ONLY MIPC**LTR ONLY AD FOR ENG**LTR ONLY MECH ENG BR**W/ ENCL STRUCTURAL ENG BR**W/ ENCL MATERIAL ENG BR**W/2 ENCL AD FOR REAG SFTY**LTR ONLY REACTOR SYSTEMS BR**W/ ENCL ANALYSIS BR**W/ ENCL CORE PERFORMANCE CR**W/ ENCL AD FOR PLANT SYSTEMS *+LTR ONLY AUXILI4RY SYS BR**W/ ENCL CONTAINMENT SYSTEMS **W/ ENCL I 8e C SYSLIMC BR**W/ ENCL POWER SYS GR**W/ ENCL AD FOR SITE TECH **W/4 ENCL AD FOR SITE ANLYS**LTR ONLY ACCIDENT ANALYSIS **W/ ENCL EFFLUENT TREAT SYS**W/ ENCL RAD ASSESSMENT BR**W/ ENCL KIRKWOOD**W/ ENCL EXTERNAL: LPDR'S ST-G Ll o f E40-MAdAVE2 W EMCb PT. CLINTON, OH**W/ ENCL y TIC **W/ ENCL ENG AJE6(fi A G OE-NSIC**W/ ENCL fe Acret 5 A FeW 8E W/N ACRS CAT B**W/16 ENCL gp g g gQ E.E B v3 / E 9cc c/L % .
DISTRIBUTION: LTR W ENCL . CONTROL NER: '9-15?^nAS i SIZE: 1P+1P coco ******************************* THE END
[M
- +++++-
800123 o hg
A 4 l l
TOLEDO
%mm EDISON LOWELL E. ROE Docket No. 50-346 -
5.c,.... c . . -.a.
'"8'85'58
Operating License No. NPF-3 Serial No. 442 June 2, 1978 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Lightwater Reactors Branch No. 1 Division of Project Management United States Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Stolz:
As discussed between our Mr. F. R. Miller and your Licensing Project Manager, Mr. Leon Engle on May 30, 1978, Page 7-24a of the Revision 1 to the " Davis-Besse Nuclear Power Station Unit No. 1, Attachment 1 to Amend Operating License For Removal of Burnable Poison Rod Assemblies and Orifice Rod Assemblies," as submitted to you in my letter dated May 26, 1978 is in error. Twelve copies of the corrected page are attached. We apologize for any inconvenience this error may have incurred.
Very truly yours, ks c/8 Attachments Y .. Jg.
THE TOLECO EDISCN COMPANY EDISCN PLAZA 300 MACISCN AVENUE TOLEDO. CHIO 43652 bo*'&
+
45 hetsk _
T TABLE 3.2-1 ~
E
- 5 DNB MARGItl .
\" I g .
LIMITS a .
.'" Four Reactor c.
Three Reactor One Reactor Coolant Pumps Coolant Pumps Coolant Pump 5 - Parameter Opera ting Opera tinq
-4 Operating in Each Loop 7 -" Reactor Coolant llot Leg < 611.1 < 611.l II) y Temperature T *F < 611.1 o 11 ReactorCoolantPressure,psig.I2) > 2062.7 *
> 2058.7(I)
' > 2091.4 Reactor Coolant Flow Rate, gpm (3) >_ 395,700 > 296,500 > 195,200 l u ,
i
. '?_
\
03 i
Applicable to the loop with 2 Reactor Coolant Pumps Operating.
! k
- I2) Limit not applicable during either a TilERMAL POWER ramp increase in excess of 5% of RATED TilERMAL POWER per minute or a TilERMAL POUER step increase of greater than 10%
- $ of RATED TitERMAL POWER.
(3) These flows include a flow rate uncertainty of 2.2%.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _