ML20245D853
| ML20245D853 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/28/1988 |
| From: | Withers B WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| IEB-88-008, IEB-88-8, WM-88-0246, WM-88-246, NUDOCS 8810070242 | |
| Download: ML20245D853 (4) | |
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7 W$LF CREEK NUCLEAR OPERATING CORPORATION aset.o. weers p
.a we cew amame oman September 28, i.38 WM 88-0246 U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Station F1-137 Washington, D. C. 20555
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Subject:
Docket No. 50-482:
Response to NRC Bulletin 88-08 Gentlemen The purpose of this letter is to transmit Wolf Creek Nuclear Operating Corporation's (WCN00) response to NRC Bulletin 88-08, " Thermal Stresses in Piping Connected to Reactor Coolant Systems".
The bulletin was issued by the NRC on June 22,
- 1988, to request licensees to (1) review the reactor coolant aystem to identify any connected, unisolable piping that could be subjected to temperature distributions which would result in unacceptable thermal stresses and (2) take action, where such piping is identified, to ensure that the piping will not be subjected to unacceptable thermal stresses.
The attachment to this letter provides the results of the review conducted by WCN00 and describes actions planned to comply with the actions requested in the bulletin.
If you have any questions concerning this matter, please contact me or Mr. O. L. Maynard of my staff.
Very truly yours,
.W: y Bart D. Withers President and Chief Executive Officer BIN /jad Attachment oc:
B. L. Bartlett (NRC), w/a D. D. Chamberlain (NRC), w/a R. D. Martin (NRC), w/a P.: W. O'Connor (NRC), w/a (2)
Y~~b P.O. Box 411/ Burtengton, KS 86639 / Phone: (316) 364-8831 k
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Bart D. Vithers, of lawful age, being first duly sworn upon oath says -
91 he is President and Chief Executive Officer of Wolf Creek Nuclear Opera-3g that he has read the foregoing document and knows the con,
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Corporations thereof; that he has executed that same for and on behalf of f Corporation with full power and authority to do sol and that the fr g ('
therein stated are true and correct to the best of his knowlei information and belief.
By 1)
Bart D. Withers
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President and Chief Executive Officer SUBSCRIBED and sworn to before me this 4 8 day of ;dep., 1988.
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Attachment to WM 88-0246 Page 1 of 2 i..
RESPONSE TO NRC BULLETIN 88-08 Regulatory Commission (NRC) issued O'
On June 22, 1988, the Nuclear Stresses in Piping Connected to Reactor Oc
,. I Bulletin 88-08,
" Thermal bulletin was to request all holder Systems".
The purpose of theconstruction permits for light-water-cooled nt actions.
The bulletin requested I
operating licenses or SI power reactors to take certainreactor coolant systems (RCS) to identi!
6 licensees (1) review their S(
connected unisolable piping that could be subjected to tempe2 distributions which would result in unacceptable thermal stresses at take action, where such piping is identified, to ensure that the pipint
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i not be subjected to unacceptable thermal stresses.
Upon receipt of NRC Bulletin 88-08, Wolf Creek Nuclear Operating connected to the (WCNOC) initiated an engineering review of systemsdetermine whet This review was made to RCS could be subjected to stresses from tempe.
or temperature oscillations that could be induced by 1-connected to the stratification the p'
valves and that were not evaluated in the design evaluation of RCS h This review included piping used for RCS cold leg injection, injection, and Pressurizer Spray.
During the review, one line was determined to meet th NRC Bulletin 88-08.
has sufficient driving pressure-head and temperature differential acro single normally closed isolation valve (BG-HV-8145) to be a pot line down candidate for developing a thermal stratified layer in the of BG-HV-8145.
non-destructively examine (NDE) this line during Refuel 3 1988.
The NDE will i WCNOC will is currently scheduled to begin on October 6, zones and high stre the welds, heat-affected Any indications l
provide assurance that there are no existing flaws.be e If stratification is determined to be the root cause, WC will repairs in to preclude unacce required l
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upstream valve (BG-HV-8145) and/or piping system l
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thermal stresses.
i to provide assurance in the future that thermal stratifica-I SI not occurring in the line downstream of valve BG-HV In order i
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the valve, this acceptable leakage through the valve and that thermal stratificatio p
g If the leak test shows that there is unacceptable leaka g, g'4 the valve, the piping will be instrumented to determine if i
occurring.
If stratification is occurring, steps stratification is occurring.
and to preclude taken to assure that there are no existing flaws thermal stratification.
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Attichmsnt'to WM 88-0246.
Page 2 of 2.-
-o Since valve BG-HV-8145 is in a normally closed position during normal plant -
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operations, the leak. test will be performed on a refueling outage basis to provide continuing assurance that there is no unacceptable lekkage past.the valve.- The frequency of leak testing will be evaluated depending on the result of previous testing experience.
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