ML20151T844: Difference between revisions

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#REDIRECT [[PY-CEI-NRR-0841, Forwards Addl Info on Util Program to Test & Evaluate motor- Operated Valves in High Pressure Eccs,In Accordance W/Ie Bulletin 85-003,per NRC 880405 Request]]
| number = ML20151T844
| issue date = 04/20/1988
| title = Forwards Addl Info on Util Program to Test & Evaluate motor- Operated Valves in High Pressure Eccs,In Accordance W/Ie Bulletin 85-003,per NRC 880405 Request
| author name = Kaplan A
| author affiliation = CLEVELAND ELECTRIC ILLUMINATING CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
| docket = 05000440
| license number =
| contact person =
| document report number = IEB-85-003, IEB-85-3, PY-CEI-NRR-0841, PY-CEI-NRR-841, NUDOCS 8804290168
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
}}
 
=Text=
{{#Wiki_filter:.
THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY P O. BOX 97  e  PERRY, OHIO 44081 e TELEPHONE (216) 259 3737  e  ADD R E S S - 10 CENTER ROAD Serving The Best Location in the Nation PERRY NUCLEAR POWER PLANT Al Kaplan VICE PRESCENT wuctem oaou ,                                        April 20, 1988 PY-CEI/NRR-0841 L U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Perry Nuclear Power Plant Docket No. 50-440 IE Bulletin 85-03 Final Report Gentlemen:
An NRC letter of April 5, 1988 requested additional information on the Cleveland Electric Illuminating Company's program to test and essluate motor-operated valves in high pressure emergency core cooling service, in accordance with IE Bulletin 85-03. Our November 13, 1987 correspondence on this subject had identified that our test period would be extended to January 31, 1988, with a final report submitted by March 31, 1988.
The final report was submitted by letter PY-CEI/NRR-0835L on March 31, 1988, and answers the bulletin-related questions in your April 5 letter as summarized in Attachment 1.
The oath and affirmation for the final report forwarded by letter PY-CEI/NRR-0835L is attached. Please call if you have any questions.
Very cruly yours,t l
Al Kaplan Vice President Nuclear Group AK: cab Attachment ec:    T. Colburn K. Coonaughton USNRC Region III
            '8804290168 88)420 h'll PDR    ADOCK 05000440 0                    DCD L
 
    * , eo                                                                                                                              ..
Attachment 1
        ,                                                                                                                  PY-CEI/NRR-0841 L i
3 Additional information on IE Bulletin 85-03 Final Report:
l '. MOV E51F0!9 was statically and dynamically tested as described in the final report.
: 2. The differential pressures are maximums during actf.ve safety function; stroking in the other direction, the tabulated ratings would not be exceeded.
: 3. As noted in response to question 2 above, the dif ferential pressures identified in the final report envelope the pressures which valves would experience. being returned to normal position. Our demonstrated teet methodology and setpoint adjustments of the 4 valves in question, as reported in the March 31 final report, demonstrate the capability to stroke in either direct. ion to restore system operability.                                                    In addition, the design provides alternate supply to the RCIC and HPCS systems (condensate storage tank or suppression pool), various control room indications / alarms, and other redundant features to facilitate correction of the problem or to provide adequate core cooling in spite of any valve being out of position.
: 4. The maximum design pressure differential is 1177 psid for 1E51F0063 per the final report.
b
: 5. Switch setting, MOVATS testing, and procedures for evaluation of results are described in the final report:
(a)    Procedures are in place and training has beer. instituted on the l
setting of switches, use of signature test equipment and maintaittance of valve operators.
(b)    As indicated in the final report, the Bulletin 85-03 actions are complete and valves were left operable. Safety-related valve                                                              ;
nonconformances are controlled by plant procedures for nonconformance reporting, including an engineering disposition to ascertain safety function.                          The Bulletin 85-03 valves are covered by the Perry Technical Specifications which address the actions required if the subject valves affect emergency core cooling system                                                        !
operability or containment isolations.
(c)    Stem thrust calculations and design margins are described in the final report.
(d)    Stroke test results are included in the final report.
: 6. As indicated in our letter of November 13, 1987 (PY-CEI/01E-0291L), the final report was submitted March 31, 1988.
 
g' ' 9 ' .9 Alvin Kaplan who, being duly sworn, deposed and said that (1) he is Vice
                    ' President, Nuclear Group of The Cleveland Electric Illuminating Company, (2) he is duly authorized to execute and file the final report on IE' Bulletin 85-03 _
for-the Perry Nuclear Power ?lant (letter PY-CEI/NRR-0835L, dated March 31,.
1988) and additional information provided by letter PY-CEI/NRR-0841L, dated April 20, 1988 on behalf of The Cleveland Electric. Illuminating Company and as duly authorized agent for Duquesne Light' Company, Ohio Edison Company, Pennsylvania Power Company and the Toledo Edison Company, and (3) the statements set forth therein are true and correct to the best of his knowledge, information and belief.
s Alvin'Kaplan Sworn to and subscribed before me, this      c28        day of  /c44 d        ,
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Eba/4> h hklA-6 .-a 4              som n7 1-
_}}

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