ML20037A153
| ML20037A153 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 06/30/1978 |
| From: | Turbak M COMMONWEALTH EDISON CO. |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7809220168 | |
| Download: ML20037A153 (2) | |
Text
h I
a-Commonwealth Edison Transmittal contains Ne :ms: Naticcai o'a:a CNcago !! hoc s Attachment C Accress Re::iy o Des Cthee Sox yg CNcage. "hnois 60690 June 30, 1978 hY fD$ $ $0776h $
& g 7 W_0LL 8 0 %
,l)/S7%/Gu? w
,S& W M 72,y I
Mr. George E. Lear, Chief Operating Reactors - Branch 3
(
L Division of Operating Reactors L
U.S. Nuclear Regulatory Con: mission Washington, DC 20555
Subject:
Dresden Station Units 2 and 3 Quad-cities Station Units 1 and 2 Evaluation of the Consequence of a Multiple Subsequent Relief Valve Discharge on the Mark I Containments NRC Docket Nos. 50-237/249 and 50-254/265 References (a) :
V.
Stello, Jr. letter to Commonwealth Edison dated March 20, 1978 '
(b) :
R. L. Bolger letter to D. K. Davis dated November 1, 1978
Dear Mr. Lear:
Enclosed is Commonwealth Edison's evaluation of the potential for and consequence of multiple subsequent relief valve discharge on the torus and torus support systems on Dresden Units 2 & 3 and Quad-Cities Units 1 & 2.
This evaluation provides the assessment requested in Reference (a).
As described in Attachments A and B to this letter, transient analyses results for the subject plants indicate that only the icw setpoint relief valve (setpoint - 1115 psig) will undergo a subsequent actuation.
The remaining four valves do not undergo a subsequent actuation after the initial cold actuation.
This result was described in Reference (b), at which time the cer:mitment was made to reduce the se: point of the icwest setpoint valve tc 1115 psig. The factors developed to establish the response of the Cresden and Guad-Cities contain-ments to a relief valve actuation are delineated in Attachment C.
?crtions of Attachment C are marked ' General Electric Company Proprieta y Information" because it contains menticello
/
ramshead test data.
This A achment contains test data fr m
- gt)
W the monticello ramshead test rescrt (Sir C-215Si-?) which was transmitted to the '.iRC 5taff On August 23, 1977.
Therefore.
g9
_7 8 0 i n o n 8 _----_ --
r-pp 4
t,,
Comm:nwerith Edison NRC Occket Nos. 50-237/249 50-254/265 Mr. George E. Lear: June 30, 1978 the affidavit which acccmpanied that transmittal is applicable to the infornation in Attachment C.
The results of this assessment satisfy the criteria defined in Reference (a) and indicate that the strength ratios for the torus shell and torus support system are, as required, less than 0.5.
For this reason no corrective action is required.
One (1) signed original and nine (9) copies of this letter and Attachments (including Attachment C) are provided for your use.
An additional fifty (50) copies of this transmittal without Attachment C are also provided.
Transmittals with Attachment C are appropriately marked.
Please direct any additional questions on this subject to this office.
Very truly yours, 3
j
)1.
c ux/
M.$S. Turbak Nuclear Licensing Administrator Boiling Water Reactors attachments I
I n--
n/n/n REOULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-237/249/254/265 REC: LEAR G E ORG: TURBAK M S DOCDATE: 06/30/78 NRC COMMONWEALTH EDISON OF IL DATE RCVD: 07/08/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED LTR 1 ENCL 60
SUBJECT:
REQUESTINO WITHHOLDINO PURSUANT TO 2.790 INFO.
FORWARDING PROP INFO CONSISTING OF APPLICANT"S EVALUATION OF POTENTIAL FOR & CONSEQUENCE OF MULTIPLE SUBGEQUENT RELIEF VALVE DISCHARGE ON THE TORUS AND TORUS SUPPORT SYSTEMS ON SUBJECT FACILITY"S... Oo f t *, Hald ptr Insfesac he yo deo nte n
PLANT NAME: DRESDEN - UNIT 2 REVIEWER INITI AL:
XJM DRESDEN - UNIT 3 DISTRIBUTER INITIAL:
QUAD-CITIES -- UNIT 1 QUAD-CITIES - UNIT 2 00000************
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
MARK I CONTAINMENT (RELATED INFO ON INDIVIDUAL DOCKETS)
(DISTRIBUTION CODE A025) gg p FOR ACTION:
BR CHIEF ORB #2 BC**W/7 ENCL $ $,1)Cj j
INTERNAL:.
REO FILE **W/ ENCL $ l NRC PDR*n90mEElabk ON0nP OELD**W/ ENCL T 2.
GOSSICK & STAFF **LTR ONLY DIRECTOR NRR**LTR ONLY DIRECTOR DPM**LTR ONLY DEPUTY DIR DPMu*LTR Or;i_Y I & E**W/2 ENCL W/$j/(se STRUCTURAL ENG DR**W/ENCLS C GRIMES **W/ ENCL P /7 PLANT SYSTEMS BR**W/2 ENCL 5
AD FOR SYS & PROJ**W/ENCLI/I AD FOR PLANT SYSTEMS **W/ ENC
(,
CONTAINMENT SYSTEMSuW/ENCLf/T ENGINEERING BR**W/ ENCL S$ 7 AD FOR ENG**W/ ENCL T3e EXTERNAL:
LPDR'S heLtt)
N.Sm3A tnt TERA **W/ ENCL # 4 ACRS CAT B**W/16 ENCL F M tA d l DISTRIBUTION:
LTR 44 ENCL 40 CONTROL NCR:
780720291 SIZE: 2P+22P
- u * * * * * * * ;+ * * *
- u u n * * * * * * * * * * * * *
- THE END
- u4 ***
l
- - _ - -