ML20204H199

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Forwards Request for Addl Info Re Integrity of Reactor Coolant Pumps in Light of 860103 Sheared Shaft Event.Info Requested within 45 Days of Ltr Receipt
ML20204H199
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 07/25/1986
From: Stolz J
Office of Nuclear Reactor Regulation
To: Campbell G
ARKANSAS POWER & LIGHT CO.
References
NUDOCS 8608080035
Download: ML20204H199 (4)


Text

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  • Omg -.cy f July 25,1986 Docket No. 50-31 Mr. Gene Campbell Vice President, Nuclear Operation .

Arkansas Power and Light Company i P. O. Box 551 Little Rock, Arkansas 72203

Dear Mr. Campbell:

We have reviewed your response of May 13,1986,toour10CFR50.54(f) letter relating to the integrity of your reactor coolant pumps in light of the i sheared shaft event at Crystal River 3 on January 3,1986. We have found that you nave not been totally responsive to our request for information in the 10 CFR 50.54(f) letter and we need clarification on other information within your response. The enclosed request for additional information identifies the information which is needed to complete our review. We request your response within 45 days from receipt of this letter, i The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, e

vs.M12aL EIGED 14 JC G I 7.,b w 4*i' John'F. Stolz, Director i PWR Project Directorate #6 Division of PWR Licensing-B

Enclosure:

As stated 1

cc w/ enclosure:

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Docket No. 50-313 i

Mr. Gene Campbell Vice President, Nuclear '

Operation Arkansas Power and Light Company P. O. Box 551 Little Rock, Arkansas 72203

Dear Mr. Campbell:

e

We have reviewed your response of May 13,1986,toour10CRF50.54(f) letter relating to the integrity of your reactor coolant pumps in light of the sheared shaft event at Crystal River 3 on January 3,1986. We have found that you have not been totally responsive to our request for information in the 10 CFR 50.54(f) letter and we need clarification on other information within
your response. The enclosed request for additional information identifies the
information which is needed to complete our review. We request your response within 45 days from receipt of this letter.

i

! The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, 7

i j John F. Stolz, Director i '

PWR Project Directorate #6 Division of PWR Licensing-B i

Enclosure:

As stated i

cc w/ enclosure:

j See next page i

DISTRIBUTION ACRS-10 DCrutchfield DbcTeT Tf1T BGrimes '

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Mr. G. Campbell Arkansas Power & Light Company Arkansas Nuclear One, Unit I cc:

Mr. J. Ted Enos Manager, Licensing Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203 Mr. James M. Levine

  • General Manager Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Mr. Nicholas S. Reynolds Bishop. Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street, N.W.

Washington, D.C. 20036 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodnont Avenue Bethesda, Maryland 20814 Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations ,

611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Mr. Frank Wilson, Director Division of Enviannmental Health Protection Department of Health Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72201 Honorable William Abernathy County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801

Enclosure REQUEST FOR ADDITIONAL INFORMATION CONCERNING RESPONSE TO THE APRIL 23,1986,10CFR50.54(f)

REQUEST ON INTEGRITY OF REACTOR COOLANT PUMPS FOR ARKANSAS NUCLEAR ONE, UNIT 1 DOCKET NO. 50-313

1. You have indicated that you 'itend to perform UT inspections on the RCP shafts during the next refb .ng outage. In light of the unsatisfactory Davis-Besse experience with Ur inspecting of their RCP shafts, do you still intend to conduct UT examinations? If so, justify their validity.

If UT examinations are not to be conducted provide your plans for using other examination alternatives.

2. Your response requires additional details with respect to the extent of your plans. In light of the failure of bolts and drive pins at Crystal River 3, and cracks found in these same components at Davis-Besse provide your plans for inspection, and any corrective action which might be required including replacement with a less susceptible material.
3. Your response indicates that the operators at ANO-1 have been told to expect a reactor trip following a sheared shaft event, but if a trip does not occur to secure the pump and comence an orderly shutdown. In addition, your FSAR indicates that ANO-1 will ride through a sheared shaft event depending on the number of RCPs in operation. For example, a power to flow trip is designed to occur only when one RCP is lost when two are operating, when one RCP pump in each loop is lost, or when two RCPs in the same loop are lost. Clarify how the operator will identify a RCP sheared shaft event and what signal automatically trips the reactor.

The staff believes that the operator would manually trip the reactor if a sheared shaft event is indicated and an expected reactor trip has not occurred automatically. Provide the rationale as to why the operator does not manually trip the reactor if a trip does not occur as discussed above.

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