ML20215N069
| ML20215N069 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/16/1986 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| KMLNRC-86-184, NUDOCS 8611040241 | |
| Download: ML20215N069 (3) | |
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KANEAS GAS AND ELECTRIC COMPANY THE ELECTAIC COMPANY otr~~t norsTra October 16, 1986 veCE PRE 5@ENT hvC6E AR
[+M@M:W/L@],
l Mr. E. H. Johnson, Director j
i 22 Division of Reactor Safety and Projects l
U. S. Nuclear Regulatory Commission
[
h Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 KMLNRC 86-184 Re:
Docket No. STN 50-482 Ref:
1)KMLNRC 86-137 dated 7/31/86, from GLKoester, KG&E, to EHJohnson, NRC 2)NRC letter dated 9/16/86, from JEGagliardo, NhC, to GLKoester, KG&E Subj:
Additional Information Concerning Inspection Report STN 50-482/86-08
Dear Mr. Johnson:
The purpose of this letter is to provide additional information to that submitted in Reference 1,
to address specific questions concerning Violations 482/8608-02 and 482/8608-03 This information was requested in Reference 2.
Violation 482/8608-02:
Why inadequate Fire Barriers were not recognized by Management and corrective actions taken in a timely manner?
During the start up program in June of 1985, Nuclear Plant Engineering of KG&E was notified by the A/E of a design error which required the necessity of adding fire proofing to the
'C' containment tendon buttress on Elevations 2047' and 2026'.
NPE issued a Plant Modification Request to add the required fire proofing but failed to recognize the Fire Hazards Analysis impact and Technical Specification applicability.
During this period of time, the emphasis was on construction completion and the preoperational test program and NPE personnel were not familiar with plant operational requirements.
Since this occurrence, station support personnel have become aware of operational requirements and the Plant Modification Process has been improved to receive appropriate supervisory / management reviews for determination of Technical Specification applicability of proposed design changes.
l 8611040241 861016
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PDR ADOCK 05000482
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PDR 201 N. Market - Wichita, Kansas - Mail Address: RO. Box 208 I w1chita, Kansas 67201 - Tclephone: Area Code (316) 261-6451
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Mr. E. H. Johnson October 16, 1986 KMLNRC 86-184 Page 2 Violation 482/8608-03 Have any other safety-related valves been modified in this manner?
A WCGS Internal Operations Program Deficiency (IOPD) was issued to:
1.
Reset ALHV32 and ALHV33 Limit Switches for Full Open and retest in accordance with PMR 1669.
2.
Review other valve stroke times in ISI program to identify those that may have had full stroke readjusted to meet required stroke time.
Any found to have been readjusted, notify Plant Manager so operability /LCO determination can be made and initiate a Work Request for Nuclear Plant Engineering evaluation'of increased stroke time.
3 Review all remaining valve stroke times in ISI program to verify readjustment of limit switches have not been done to satisfy stroke time requirement.
i Valves ALHV32 and ALHV33 were re-set to the full open position and re-tested satisfactorily on Work Request 2055-86 which was completed on May 10, 1986. The limits were set in accordance with PMR 1669 at that time.
A review of all system work requests was conducted-to identify all valves which could have had limit switch adjustment to meet stroke time limitations.-
The review conducted prior to June 20, 1986 revealed only one Work Request (#90761-84 on valve EFHV42) where a valve limit switch might have been adjusted for reasons similar to the limit switch adjustments for valves ALHV32 and ALHV33
_ The action taken block of Work Request 90761-84 described a situation where the valve limit switch was set to eliminate valve overtravel, therefore this was not an analogous situation.
All valves contained in the ISI program were researched and no further instances of limit switch adjustment to satisfy valve stroke times were identified.
Do current surveillance procedures, drawings, and ISI programs include adequate programatic controls to ensure the analyzed requirements will be met?
STS EC-201 was revised to incorporate a tolerance interpretation based on ASME Section XI Article IWV-3000. In summary,-the response to item
r.
uJ Mr. E. H. Johnson October 16, 1986 KMLNRC 86-184 Page 3-i 2 of the IOPD did not reveal any hidden problems in our historical limitorque records.
If you have any questions concerning this matter, please contact me or Mr.
O. L. Maynard of my staff.
Very truly yours, Glenn L. Koester Vice President - Nuclear GLK:see cc: P0'Connor JCummins JTaylor i
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