ML20203N579

Requests Plans & Schedules for Insp of Reactor Coolant Pump Shafts & Other Structural Components & Justification for Continued Operation Until Insp Can Be Performed,Per IE Info Notice 86-019

ML20203N579
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/23/1986
From:	Eisenhut D Office of Nuclear Reactor Regulation
To:	Jeffery Griffin ARKANSAS POWER & LIGHT CO.
References
IEIN-86-019, IEIN-86-19, NUDOCS 8605050520
Download: ML20203N579 (6)

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, i April 23,1986 Docket No. 50-313 J1SIRIBUTION GocketF3 nRC PDR-BGrimes JPartlow WRegan DCrutchfield Mr. John M. Gi-iffin L POR RIngram DEisenhut Senior Vice President PBD#6 Rdg GVissing HDenten of Energy Supply FMiraglia Gray File VStello Arkansas Power and Light Company OELD EBrach P. O. Box 551 ACRS-10 H0rnstein Little Rock, Arkansas 72203 EJordan FAllenspach

SUBJECT:

Safety Significance of Reactor Coolant Pump Shaf t Integrity Issue You have recently received IE Information Notice 86-19, REACTOR C00t ANT PUMP SHAFT FAILURE AT CRYSTAL RIVER, which was issued on March 21, 1986. The IE Information Notice provides notification of failure of a reactor coolant pump (RCP) shaft manufactured by Byron-Jackson Company. In summary, on January 1, 1986, Reactor Coolant Pump (RCP) "A" shaf t at Crystal River, Unit 3 failed completely within the hydrostatic bearing. Subsequent inspections of the shafts of the other three RCPs revealed crack indications in all shafts.

Also all eight cap bolts securing the impeller to the shaft on the "A" and "B" pumps were found to be cracked in multiple places (some were broken) and five of eight pins which take the torque between the impeller and the shaft on "A" and "B" pumps were cracked.

Crystal River 3 plant has a B&W NSSS. The RCPs are Byron-Jackson, type DFSS vertical centrifugal pumps. The shafts are ASTM A 461 Grade 660 Material, 65 3/4 inch long and 7 i to 8 inch in diameter. Crystal River, Unit 3, was licensed on January 28, 1977.

On March 21, 1986, Toledo Edison Company reported that ultrasonic exanination of the RCP shafts at Davis Besse 1, prompted by the experience of Florida Pcwer Corporation at Crystal River, Unit 3, has revealed two of four RCP shaf ts have cracked with indications of cracks on the remaining two shaf ts.

Toledo Edison is planning to replace all four pump shaft assemblies. Davis Besse 1 was licensed on April 22, 1977, and also has a B&W NSSS with Byron-Jackson RCPs similar to those at Crystal River, Unit 3.

We understand that Arkansas Nuclear One, Unit 1, (ANO-1), also a B&W NSSS, has Byron-Jackson RCPs similar to those at Crystal Piver, Unit 3, and Davis Besse 1. ANO-1 was licensed on May 21, 1974.

In v4.w of the experience of Crystal River, Unit 3, and Davis Besse 1, we believe a significantly high probability exists for cracks in your RCP shaf ts, cap bolts and pins, which could propagate to failure (the cap bolts secure the impellers to the shafts and the pins transfer the torque from the shafts to the impellers).

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Mr. John M. Griffin Therefore, pursuant to 10 CFR 50.54(f) of the Commission's regulations, you are requested to submit written statements, signed under oath or affirmation, to enable the Commission to determine whether or not your license should be modified. Specifically, you are requested to submit to the NRC, within 20 days from the date of this letter, your plans and schedules for inspecting the RCP shafts and other structural components of your RCPs.

In addition you are requested to provide the following information regarding your justification for continued operation until you inspect your RCP shaf ts and other structural components of your RCPs:

1. A description of the design and operational history of the ANO-1 RCPs, which are different from the design and/or operation of the Crystal River, Unit 3, and Davis Besse 1 RCPs.

2. The results of any analyses perfcrmed subsequent to analyses done for the FSAR which would address the consequences of a locked rotor or broken shaft event during plant operation.

3. Considering the higher probability than previously envisioned of a postulated RCP shaft failure, describe any actions you have implemented or have planned such as operator review and associated training concerning the specific events at Crystal River, Unit 3, and Davis Besse 1 and monitoring plant parameters such as primary to secondary reactor coolant leakage.

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, WIEfd. D9 Fl:"

Darrell G. Eisenhut, Acting Director Office of Nuclear Reactor Regulation cc: See next page

• See previous white for concurrences.

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Mr. John M. Griffin Therefore, pursuant to 10 CFR 50.54(f) of the Commission's regulations, you are requested to submit written statements, signed under oath or affirmation, to enable the Commission to determine whether or not your license should be modified. Specifically, you are requested to submit to the NRC, within 20 days from the date of this letter, your plans and schedules for inspecting the RCP shaf and other structural components of your RCPs.

In additio'ns you are requested to provide the follow ng infornation regarding your justification for continued operation until yo)u inspect your RCP shafts and other stru'equral components of your RCPs:

1. A descriptionNof the design and operational history of the ANO-1 RCPs, which are different from the design and/or operation of the Crystal River, Unit 3, and DavisxBesse 1 RCPs.

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2. The results of any analyses performed subsequent to analyses done for the FSAR which would address the consequences of a locked rotor or broken stiaft event during plant operation.

3. Considering the higher probability than previously envisioned of a postulated RCP shaft failure, describe.any actions you have implemented or have planned such as operator review.and associated training concerning the specific events. at Crystil River, Unit 3, and Davis Besse 1 and monitoring plant parameters such as primary to secondary reactor coolant leakage. x The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not recuired under P.L.96-511.

Sincerelh, Harold R. Denton, Director Office of Nuclear Reactor Regulation cc: See next page

• See previous white for concurrences. '.rh AD-PWR-B 'J:P DD:NRR D:NRR 0 DCrutchfield FF ia DEisenhut HDenton VS llo 3/ /86 ) 6 4/ /86 4/ /86 6 D-6 6 PBD-6 PBD#6 F0B-PWR-B R am - ssing;cf* CMcCracken* JStolz* FAllenspach WRegan 4/ 6 4 16/86 3/31/86 3/31/86 3/31/86 3/31/86 i

Mr. John M. Griffin -Therefore,pursuantto10CFR50.54(f)oftheCommission'sregulations,youare requested to submit written statements, signed under oath or affimation, to enab tha Commission to determine whether or not your license should be modifi . Specifically, you are requested to submit to the NRC, within 20 days fro the date of this letter, your plans and schedules for inspecting the RCP shafts nd other structural components of your RCPs.

In addition y are requested to provide the following information regarding your justificat~on for continued operation until you inspect your RCP shafts and other struct al components of your RCPs:

1. A description the design and operational history of e AN0-1 RCPs, which are differ nt from the design and/or operation of the Crystal River, Unit 3, and Davis esse 1 RCPs.

2. The results of your alyses perfomed subsequent t analyses done for the FSAR which would s ow the consequences of a 1 ked rotor or broken shaft event during plan operation including the otential consequences from the loss of other o rating RCPs consideri g a loss of offsite power.

3. Considering the higher prob bility than prev} usly envisioned of a postulated RCP shaft failure \, describe any ttions you have implemented

-or have planned such as operatgr review an associated training concerning the specific events Mt Crystal River, Unit 3, and Davis Besse1andmonitoringplantpar\ meters uch as primary to secondary reactor coolant leakage. N The staff has prepared reasons for this t _ formation request to assure that the burden to be imposed on you is justifie ig view of the potential safety significance of the issue to be addrese d1 the requested information. The evaluation of these justifications h been erformed by the staff and approved by the Executive Director for Opera onsor h designee. .

The reporting and/or recordkeepi g requirement of this letter affect fewer

- than ten respondents; therefor , OMB clearance ik not required under P.L.96-511.

Sincerely, Harold R. Denton, Di ctor Office of Nuclear Rea tor Regulation cc: See next page '

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• See previous white for concurrences. '

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Mr. John . Griffin Therefore,' ursuant to 10 CFR 50.54(f) of the Commission's regulations, you are requested t submit written statements, signed under oath o[affinnation, to enable the C .ission to determine whether or not your license should be modified. Spe ifically, you are requested to submit to Jfie NRC, within 20 days from the te, of this letter, your plans and sched/les for inspecting the RCP shafts and o er structural components of your R s.

In addition you art. requested to provide the folloy(ng information regarding your justification r continued operation until tu inspect your RCP shaf ts and other structural omponents of your RCPs:

1. A description of t e desigr. and operatio I history of the ANO-1 RCPs, which are different from the design and or operation of the Crystal River, Unit 3, and Davis Be se 1 RCPs.

2. The results of your anglyses perform d subsequent to analyses done for the FSAR which would sh w the conse uences of a locked rotor or broken shaft event at plant ope ation at ess than full power including the potential consequences f m the I ss of other operating RCPs considering a loss of offsite power.

3. Considering the higher proba' i}nty than previously envisioned of a postulated RCP thaft failure, describe any actions you have implemented or have planned such as opera (r review and associated training concerning the specific eveps ht Crystal River, Unit 3, and Davis Besse 1 and ironitoring pla t par'ameters such as primary to secondary reactor coolant leakage.

The staff has prepared reaso for this (nformation request to assure that the burden to be imposed on you is justified in view of the potential safety significance of the issue 'o be addressed the requested information. The evaluation of these justi ications has been performed by the staff and approved by the Executive Directo for Operation or ht designee.

The reporting and/or r cordkeeping requirements, of this letter affect fewer than ten respondents; therefore, OMB clearance is 1 not required under P.L.96-511. \

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Sincerely, \

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HaroldR.Denton,Djrector Office of Nuclear Reactor Regulation cc: See n xt page AD-PWR-B D:PWR-B DD:NRR D:NRR ED0 DCrutchfield FMiraglia DEisenhut lHDenton VStello 4/ /86 4/ /86 4/ /86 i4/ /86 4/ /86 PQD ' .

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Mr. J. M. Griffin 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. Bcrsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont 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 Operatinns 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Mr. Frank Wilson, Director Division of Environmental Health Protection Department of Health Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72201 Honorable Ermil Grant Acting County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801

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