ML20080M923

Forwards Addl Info Requested in 830810 Telcon Re Franklin Research Ctr 830617 Draft Technical Evaluation Rept on Util Response to Phase 1 of NUREG-0612, Control of Heavy Loads at Nuclear Power Plants

ML20080M923
Person / Time
Site:	Point Beach
Issue date:	09/28/1983
From:	Fay C, Fay C WISCONSIN ELECTRIC POWER CO.
To:	John Miller Office of Nuclear Reactor Regulation
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR TAC-07727, TAC-08074, TAC-7727, TAC-8074, NUDOCS 8310040310
Download: ML20080M923 (8)

Text

insconsin Bectnc eowca coursur 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 September 28, 1983 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. J. R. Miller, Chief Operating Reactors Branch 3 Gentlemen:

DOCKET NOS. 50-266 AND 50-301 SUBMITTAL OF ADDITIONAL INFORMATION IN RESPONSE TO DRAFT TECHNICAL EVALUATION REPORT NUREG-0612, " CONTROL OF HEAVY LOADS" POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 On August 10, 1983 a telephone conference was held between Wisconsin Electric personnel, members of the NRC staff, and repre-sentatives of Franklin Research Center concerning the draft Technical Evaluation Report (TER) , dated June 17, 1983, regarding Wisconsin Electric's response to Phase 1 of NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants". During this telephone conference, Wisconsin Electric was requested to submit additional clarifications regarding a number of issues raised in this draft TER. This ad6itional information is to be incorporated in the final TER being prepared by the Franklin Research Center for the NRC.

The enclosure to this letter is Wisconsin Electric's response to the issues discussed during the August 10 telephone conference.

It is our intent to complete all actions specified in this response by December 31, 1983.

At this time, we are notifying you that the single-failure-proof auxiliary building crane trolley will not be installed by December 31, 1983. The installation of this trolley is being delayed to avoid interference with activities associated with the receipt of spent fuel assemblies at Point Beach and with replacement of Unit 1 steam generator lower assemblies. Our revised schedule calls for installation of the new trolley by August 31, 1984.

Please contact us if you have any further questions.

Very truly yours, 8310040310 830928 v/

PDR ADOCK 05000266 i. //

P PDR O'lU fG f -

C. W. Fay VicePresiden\-NuclearPower Enclosure a

Mo33 Copy to NRC Resident Inspector [f

.- Enclosure WISCONSIN ELECTRIC POWER COMPANY COMMENTS ON DRAFT TECHNICAL EVALUATION REPORT NUREG-0612, " CONTROL OF HEAVY LOADS AT NUCLEAR POWER PLANTS" e

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' Item 1:. IDENTIFICATION OF LOAD' HANDLING SYSTEM WITHIN-THE SCOPE OF NUREG-0612 1

TER FINDING' The following systems'should be further evaluated.for compliance with the guidelines of NUREG-0612 without regard for system ,

. redundancy

. , ,

l. Circulating / water pumphouse monorails .(N-S and E-W) .

2. Reactor pressure, vessel head monorails.

3. Containment buttress jib cranes.' ,

4. Main shop crane.-

Jib crane over'incore' instrumentation. seal tables.

5. i s s

RESPONSE

Wisconsin Electric'has previously provided information

indicating the compliance of.these lifting devices with NUREG-0612 guidelines Nos. l'through 6. Wisconsin. Electric has reviewed these devices, with.the exception of the jib cranes over;the incore instrumentation-seal tables, and considers that all of the devices are industrial grade commercial lifting devices manufactured by. reputable manu-facturers~in. compliance with industry standards applicable-at.the time of manufacturing. We consider these lifting

devices to be-in compliance with guideline No. 7 of NUREG-0612.

.The remaining jib cranes over the incore instrumentation-seal.

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tables will be reviewed during'the.next unit outages and will be replaced.if not in compliance with guideline No. 7.

J-Item 2: SAFE LOAD PATHS TER FINDING A system of further visual aids should be implemented to -

assist the crane operator in ensuring that the designated safe load paths are followed.

RESPONSE

Wisconsin Electric will revise current load handling procedures

'to require that a second individual be involved with lifts of 4 heavy loads. The second individual will assist the crane i~ operator in ensuring that prescribed safe load paths are-i followed.

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2-Item 3: . LOAD' HANDLING PROCEDURES TER FINDING The Licensee should identify specific procedures which control the handling of heavy loads and confirm that they contain the required'information:

1. . Identification of equipment.

2. Inspection and acceptance criteria.

3. Steps and proper. sequence.

4. Definition of safe' load paths. -

5. Safety precautions.

i RESPONSE' During the tele' phone discussion of August 10, 1983 between NRC and Wisconsin Electric personnel, Wisconsin Electric reaffirmed its' opinion that=a' limited number of generic-load handling procedures.is. preferable to a myriad of specific-procedures for each and every"possible lift. Wisconsin Electric has reviewed the listing of typical heavy. loads provided as Table 3.1-1 in NUREG-0612 and will develop additional specific procedures for the following lifts:

le . Spent fuel shipping cask.

2. Resin-cask.

3. Reactor-vessel head.

4. Reactor vessel internals.

These procedures will be developed 1to reflect the requirements of guideline No. 2 of NUREG-0612.

Item 4:. 'SPECIAL LIFTING DEVICES TER FINDING The' Licensee should verify the performance of a rated load test of the reactor coolant pump motor lifting rig and should verify that' visual examinations performed during annual inspection, after major maintenance, and following substantial overstress conditions contain provisions for dimensional and J

non-destructive testing in accordance with ANSI N14.6-1978.

' RESPONSE

-ANSI'N14.6-1978 requires a 150% proof-load test of the~ completed lifting rig.to verify adequacy of design.and construction and to assess the overall reliability of the lifting rig.

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A 150% proof' load test of-the completed reactor coolant

-ptunp motor lif ting rig .was ' not required atL the time of

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. manufacture and was not' performed. . However, proof load tests were-performed'on1the. individual. components of this lifting rig. The~ master link was proof load tested at 200% of the design load.and.the individual wire rope slings were tested at 250% of_their design load. Due to.a lack of -

adequate' testing equipment, the. triangular spreader assembly,'

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.which is fabricated from'4" diameter schedule 40 pipe, was not proof ^ load. tested. The spreader assembly'and the master . ,

link were subjected to-non-destructive examination, the i results of which were acceptable.

i The design-review'of the reactor coolant pump motor lifting

- rig performed by Westinghouse indicated substantial design '

stress margins. Further, the reactor coolant pump motor

lift rig is a relatively simple spreader beam device, and

the welds in the assembly have been non-destructively examined..

Wisconsin Electric considers-that load testing and.non-destructive-examination performed to.date, in conjunction with the' substantial i

' design' stress margins and simplicity of~ design, are sufficient to assure the adequacy of the lifting rig in lieu of a 150%

proof load test.

1 Wisconsin Electric will modify the requirements of the annual i ~ visual inspection for the reactor pressure vessel head lifting L rig,. internals lift rig, and reactor coolant pump motor to incorporate the NDE of critical.. welds into the ASME Section XI inservice 1 inspection program'.- 'These will.not.be considered' to be Section XI examinations, but will use'Section XI as a

! . guide. The examination's will consist of a surface examination -

L of the: critical welds. The personnel performing the examination will be-qualified in'accordance with,the applicable edition and addenda-of Section XI. The weld ~ examination will.be divided such that:100% of"thexcritical welds will be examined during'the ISI program-10-ye'ar. interval. An essentially

equal portion, within the; guidelines of Section XI, will be performed during;each'40-month' period.

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The acceptance s'tandards of Paragraphs NF5350 and NF5340 of

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ASME Section III, Division 1, will-be used. - The Section III edition and addenda corresponding to the Section XI edition and addenda.in effect for..the ISI program will be utilized.

In addition to the surface examination of the critical. welds, h'

a visualiexamination of lifting rigs will be performed each outage to check for. defects and deformation. This examination will not be performed by Section XI qualified personnel, but' i will be performed by competent and experienced maintenance personnel.

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The attachments illustrate the critical welds that will be. examined. At this time, it is our intent to examine all these critical welds.. However, should this be determined to be impracticable, we expect to modify our program as necessary.

Item 5: INTERIM PROTECTION MEASURES TER FINDING Plant technical specifications should be revised to prohibit all movement of heavy loads over the spent fuel in the spent

! fuel pool until the auxiliary building crane has been certified as a single-failure-proof crane.

RESPONSE ,

Point Beach Technical Specification 15.3.8, " Refueling and Spent Fuel Assembly Storage", will be modified to prohibit the movement of heavy loads over spent fuel in the spent fuel pool until such time as a single-failure-proof crane has been installed. In particular, Section 15.3.8.B4 will be revised to exclude the phrase "whenever possible".

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