ML17317B282
| ML17317B282 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/20/1979 |
| From: | Hering R INDIANA MICHIGAN POWER CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:00186B, AEP:NRC:186B, NUDOCS 7906220293 | |
| Download: ML17317B282 (5) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
SUBJECT:
submits addi info requested after review of AEP:NRC:00186A dtd 790504 L
NRC 790619 telecon re reanalysis of pressurizer surge linc'ISTRIBUTION CODE:
A001S COPIES RECEIVEDtLTR
~ ENCL Q SIZE: ~
TITLE: GENFRAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LIC TES
~ 7 ac. 5 8 MS 8L.L
)&78 TZ-.
OTES
~
~ ~>>>>>>>>>>>>>>>>>>>>>>>>>>
>>>>>>>>>>wae >>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>w>>>>>>>>>>>>>>>>
REC IP IENT COPIES COPIES ID CODE/NAi41E LTTR ENCL LTTR ENCL RECIPIENT ID CODE/NAME ACCESSION NHR'7906220293 DOC ~ DATE'9/06/20 NOTARIZED NO DOCKET FACIL:50-31'5 Donald CD Cook Nuclear Power Plantr Unit lr Indiana 8
05000315 50'-316 Donald C.
Coca Nuclear Power
- Plant, Unit 2r indiana IL OSO~
AUTH ~ tNAi'sE AUTHUR AFFILIATION HERINGP R ~ F ~
Indiana 8 Hichigan Power Co ~
REC IP ~ NAiRE REC IPIENT AFFILIATION SCHNENCERPA
~
Operating Reactors Branch 1
ACTION:
INTERNAL:
05 BC DR8 ¹'I l
Rgg F.-
8E 15 CORE PERF BR 17 FNGR BR 19 PLANT SYS BR 21 EFLT TRT SYS OELD 02 NRC PDR 14 TA/EDO 16 AD SYS/PROJ 18 REAC SFTY BR
?0 EEB 22 BRINKHAN 1
1 1
1 1
1 1
1 1
1 1
1 EXTERNAL: 03 LPDR 23 ACRS 1
16 1
04 NSIC 1
1 JUN 3 6 f979 Q
TOTAL NUMBER OF COPIES REUULRED:
LTTR 39 ENCL
0 0
INDIANA II MICHIGAN POWER COMPANY P. O. BOX 18 BOWLING GREEN STATION NE W YOR K, N. Y. 10004 June 20, 1979 AEP: NRC:00186B Donald C. Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos. 50-315 and 50-316 License Nos.
DPR-58 and DPR-74 Mr. A. Schwencer, Chief - Branch No.
1 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.
C.
20555 Attention:
Mr.
D. L. Wi inton
Dear Mt. Schwencer:
This letter transmits additional information concerning our submittal No. AEP:NRC:00186A dated May 4, 1979 and requested by members of the NRC staff in a telephone conversation held on June 19, 1979.
Each item requested and our response is presented below:
Topic:
Additional Information Regarding the Regnal sis of Pressurizer Sur e Line s
i N
Do both units. of the Cook Plant have a 14 inch surge line to the pressurizer?
~Res onse Both units of the Cook Plant have a 14 inch surge line to the pressurizer.
s Are the physical geometry and pipe support locations the same for both units of the Cook Plant?
~Res onse Yes, the geometry and support locations are the same for both units except Unit No.
2 is the "opposite hand" of Unit No. l.
V906220 g Q3 zn(
S ig
Nr. A. Schwencer June 20, 1979 AEP:NRC:00186B uestion No.
3 Were the terminal ends of the surge line checked against the stress criteria of the B31.1 - 1967 Power Piping Code?
~Res onse The calculated stresses at the terminals of the surge lines were checked and are within the allowable limits of the B31.1
- Code, 1967 edition.
uestion No. 4 What piping code was used for the pressurizer surge line?
~Res onse The surge line was designed in accordance with the 1967 B31.1 Power Piping Code and was erected in accordance with the B31.7 Code, 1969 edition.
uestion No.
5 Confirm that the reanalysis utilized "as built" conditions.
How and when was this fact verified?
~Res onse The physical parameters used in the reanalysis of the surge line were obtained after initial installation of the line.
A review of our records indicates that the surge line geometry has not been modified since initial installation.
Thus, the physical parameters used in the reanalysis represent "as built" conditions.
Furthermore, atter the phone conversation with your staff, the pressurizer surge lines were "walked" and the preceding fact confirmed.
uestion No.
6 Does the reanalysis result in a change in the break locations?
~Res onse The results of the reanalysis have no effect on the break point locations.
When the original analysis of the surge line was performed, breaks were postulated at each change in direction of the line.
This criterion is more conservative than the present requirements, which postulate circumferential breaks at high stress points in the line.
g i
N.7 What version of the WESTDYN code was used for the reanalysis?
~Res ense The current revision of WESTDYN was used.
This version of the code has been verified and its documentation submitted to the NRC in WCAP-8252 Rev. l.
Nr. A. Schwencer June. 0, 1979 AEP: NRC: 00186B uestion No. 8 What method of stress combination was used in the reanalysisl
~Res ense The intramodal responses due to each horizontal and vertical shock wave were combined by absolute summation.
The intermodal responses were then combined by the square-root-sum of the squares (SRSS) method.
uestion No.
9 Are any Velan valves installed in the pressurizer surge lines7
~Res onse No, there are no valves in the pressurizer surge lines.
As the information transmitted herein is being submitted at the request of members of the NRC staff, AEP interprets 10 CFR 170.22 as requiring that no fee accompany this submittal.
Very truly yours, R. F. Hering Vice President RFH clb cc:
John E. Dolan R. S. Hunter R.
W. Jurgensen D. V. Shaller - Bridgman R.
C. Callen G. Charnoff