ML17157A029
| ML17157A029 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/16/1990 |
| From: | Thadani M Office of Nuclear Reactor Regulation |
| To: | Keiser H PENNSYLVANIA POWER & LIGHT CO. |
| Shared Package | |
| ML17157A030 | List: |
| References | |
| GL-88-01, GL-88-1, TAC-69158, TAC-69159, NUDOCS 9002270388 | |
| Download: ML17157A029 (5) | |
Text
February 16 90 Docket Nos.
50-387 and 50-388 Mr. Harold W. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
Dear Mr. Keiser:
DISTRIBUTION.
C~
NRC PDR Local PDR PDI-2 Reading SVarga BBoger WButler MO'Brien MThadani JStone OGC EJordan ACRS(10)
TMcLellan RClark SUBJECT e REVIEW OF
RESPONSE
TO GENERIC LETTER 88 01 NRC POSITION ON IGSCC IN BWR AUSTENITIC STAINLESS STEEL PIPING" tTAC NOS. 69158 AND 69159)
RE 'US(UEHANNA STEAM ELECTRIC STATIONs UNITS 1 AND 2 We have completed our review of your responses dated August 10 and 18, 1988, and October 2, 1989 to Generic Letter 88-01.
Our review was conducted with the assistance of our contractor, Viking Systems International (VSI).
Our Safety Evaluation and our contractor's Technical Evaluation Report are enclosed.
The staff has reviewed the TER and concurs with the evaluations, conclusions, and recommendations contained in the TER with the exception of VSI's evaluation of your position on crack evaluation.
The staff's exceptions are summarized in the Safety Evaluation (enclosure 1).
The staff has re-evaluated the requirements for frequency of leakage monitoring.
After discussions with several BWR licensees, the staff concluded that monitoring every four hours creates unnecessary hardship to the plant operators.
Therefore, RCS leakage measurements may be taken every eight hours instead of four hours specified in GL 88-01.
Our safety evaluation precludes the necessity for you to submit IGSCC inspection plans for each future outage.
However, if flaws are found that do not meet Paragraph IWB-3500 criteria of Section XI of the ASME Code for continued operation without evaluation, the evaluations and repairs of the flaws should be submitted to the NRC for review prior to start-up.
In GL-88-01 the staff requested the licensees to incorporate the leak detection and piping ISI requirements in the Technical Specifications (TS).
Accordingly, please submit the requisite TS change requests in a timely manner.
Sincerely
) WP9+
, ~OQ.
,', C4CI toa
>0 Q.
e g page
/A~
Thadani:mj 2 /lg/90 PDI-2/D WButler
Enclosures:
1.
Saf ety Evaluation 2.
Technical Evaluation Report cc w/enclosures:
/s/
Mohan C. Thadani, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
[69158/9j
L.
C
~ q h
~ r r ~
Ir
'-is(. 11'I I
1 1,
~
g I,
r i ~rft It, 1
I,
. ~
I I'
~ ~
~
FIT 'rh rh
~p,R RE'gy 0
A I
0O Qlp
+***>>
Docket Nos.
50-387 and 50-388 e
0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 February 16, 1990 Mr. Harold W. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvani a 18101
Dear Mr. Keiser:
SUBJECT:
REVIEW OF
RESPONSE
TO GENERIC LETTER 88-01, "NRC POSITION ON IGSCC IN BWR AUSTENITIC STAINLESS STEEL PIPING" (TAC NOS.
69158 AND 69159)
RE:
SUS(UEHANNA STEAM ELECTRIC STATION, UNITS 1
AND 2 We have completed our review of your responses dated August 10 and 18,
- 1988, and October 2, 1989 to Generic Letter 88-01.
Our review was conducted with the assistance of our contractor, Viking Systems International (VSI).
Our Safety Evaluation and our contractor's Technical Evaluation Report are enclosed.
The staff has reviewed the TER and concurs with the evaluations, conclusions, and recommendations contained in the TER with the exception of VSI's evaluation of your position on crack evaluation.
The staff's exceptions are summarized in the Safety Evaluation (enclosure 1).
The staff has re-evaluated the requirements for frequency of leakage monitoring.
After discussions with several BWR licensees, the staff concluded that monitoring every four hours creates unnecessary hardship to the plant operators.
Therefore, RCS leakage measurements may be taken every eight hours instead of four hours specified in GL 88-01.
Our safety evaluation precludes the necessity for you to submit IGSCC inspection plans for each future outage.
However, if flaws are found that do not meet Paragraph IWB-3500 criteria of Section XI of the ASME Code for continued operation without evaluation, the evaluations and repairs of the flaws should be submitted to the NRC for review prior to start-up.
In GL-88-01 th'e staff requested the licensees to incorporate the leak detection and piping ISI requirements in the Technical Specifications (TS).
Accordingly, please submit the requisite TS change requests in a timely manner.
Sincerely,
Enclosures:
1.
Safety Evaluation 2.
Technical Evaluation Report cc w/enclosures:
See next page Mohan C. Thadani, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
~I F
V' II
Mr. Harold W. Keiser Pennsylvania Power
& Light Company Susquehanna Steam Electric Station Units 1
& 2 CC:
Jay Silberg, Esq.
Shaw, Pittman, Potts
& Trowbridge 2300 N Street N.W.
Washington, D.C.
20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. J.
M. Kenny Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Scott Barber Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.
Box 35" Berwick, Pennsylvania 18603-0035 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Resources Commonwealth of Pennsylvania P. 0.
Box 2063 Harrisburg, Pennsylvania 17120 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O.
Box 1266 Harrisburg, Pennsylvania 17108-1266 Mr. S.
B. Ungerer Joint Generation Projects Department Atlantic Electric P.O.
Box 1500 1199 Black Horse Pike Pleasantvi lie, New Jersey 08232 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. R.
G.
Byram Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power'nd Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company 1009 Fowles Avenue Berwick, Pennsylvania 18603