ML20086L053

Forwards Response to Draft Technical Evaluation Rept Re Control of Heavy Loads,Per 821007 Telcon

ML20086L053
Person / Time
Site:	FitzPatrick
Issue date:	01/31/1984
From:	Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Vassallo D Office of Nuclear Reactor Regulation
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR JPN-84-06, JPN-84-6, NUDOCS 8402070158
Download: ML20086L053 (6)

Text

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January 31, 1984 JPN-34-06 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Control of Heavy Loads - Response to Draft Technical Evaluation Report

References:

1) NRC letter, D.G. Eisenhut to all Operating Reactors, December 22, 1980.

2) " Control of Heavy Loads at Nuclear Power Plants," NUREG-0612, July 1980.

3) PASNY letter , J .P. Bayne to T.A. Ippolito, October 15, 1981 (JPN-81-82).

. 4) " Control of Heavy Loads," draft Technical Evaluation Report, Franklin Research Center, March 25, 1982.

Dear Sir:

Reference 1 requested that the Authority review heavy load-handling operations at FitzPatrick and required a two phase submittal of evaluations of their conformance to the guidelines of NUREG-0612 (Reference 2). The Authority completed the first phase of the review and submitted an evaluation to the NEC in October 1981 (Reference 3).

In March 1982, Franklin Research Center, under contract to the NRC, completed a draft Technical Evaluation Report (Reference 4) of the Authority's phase 1 submittal. This report identified a number of items which required further analysis or protective measures. The Authority discussed these items with the NFC, Franklin Research Center, TERA Corporation a.nd Westec Services, Inc. in a telephone conference on October 7, 1982. In that conference call, the NRC requested that a response be provided that would document certain agreements reached during the call and answer outstanding questions. That response is included as an attachment to this letter.

8402070158 840131 PDR ADOCK 05000333

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If.you have any questions regarding this matter, please centact Mr. J.A. Gray,.Jr. of my staff.

Very truly yours, T

J . Bayne Executive Vice President Nuclear Generation cc: Office of the Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 136 '

Lycoming, New York 13093 i

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ATTACHMENT TO JPN-84-06 NEW YORK PUdER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POdER PLANT CONTROL OF HEAVY LOADS i RESPONSE TO DRAFT TECHNICAL EVALUATION REPORT

I. Load Handling Procedures A. The Authority will mcdify applicable heavy load-handling procedures except those governing movement of shipping casks. (Refer to Section VI of this attachment for information regarding movement over spent fuel.) The modified procedures will require that either a load handling supervisor be present or that safe load paths be identified by floor markings prior to making a lift. To allow flexibility in managing load-handling operations, the procedures will also specify safe load path options, where applicable.

B. The Authority will verify that all heavy load-handling procedures comply with of NUREG-0612, Section 5.1.1 Guideline 2 as applicable to the FitzPatrick plant.

This guideline defines proper procedures for handling heavy loads over or near irradiated fuel or safe shutdown equipment.

II. ANSI Standards for Special Lifting Devices A. The Authority will satisfy the inspection requirements for special lifting devices in accordance with ANSI N14.6-1978, Section 5.3.1. In addition, testing and inspections will be performed in accordance with Section 5.3.3 if lifting devices are inadvertently overstressed.

B. The FitzPatrick reactor vessel head strongback was load tested at 125% of the head strongback rated load (80 tons). The applicable load testing standard in ANSI N 14.6-1978 indicates that the load test safety margin should be 150% of the maximum load to whicn the device will be subjected, rather than 150% of the rated capacity of the lifting rig. On that basis, the test load applied by tne manuf acturer amounted to 147% of the maximum load (the vessel head, wh.ch weighs 68 tons). The Authority considers that this test complies with the intent of ANSI N14.6-1978 and that the three percent difference does not warrant retesting.

C. The Authority will verify that lifting devices are adequate for their intended load by analysis, or alternatively, that the consequences of drops of these loads are acceptable with regard to NUREG-0612 Section 5.1, Criteria I - IV.

D. The Authority will require that lifting yokes for shipping casks meet the applicable requirements of ANSI N14.6-1978 prior to their use in the handling of shipping casks at FitzPatrick.

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E. For the reactor vessel head strongback and the dryer /

-separator sling assembly, the Authority will verify that designs incorporate appropriate safety margins, in accordance with Sections 3 and 4 of ANSI N14.6-1978.

III. . ANSI Standards for Cranes The Authority will verify that Guideline 6 of NUREG-0612, Section 5.1.1 is met for the Reactor Building Crane.

IV. ANSI Standards for Slings When purchasing new slings, the Authority will specify compliance with ANSI B 30.9-1971. For existing slings used with the reactor building crane that are used to carry loads over spent fuel or safe snutdown equipment the Authority will comply with ANSI B 30.9-1971 with regard to markings, storage, inspection, repair, proper use, working load limits and safe operating practices.

V. Effects of Dynamic Loads For special lifting devices designed to lift heavy loads over irradiated fuel or safe shutdown equipment, the Authority will either demonstrate that the effects ot dynamic loads are negligible or ensure that the lifting devices have sufficient design margins to accommodate dynamic loads.

VI. Interim Protection Measure I In accordance with Interim Protection measure I of NUREG-0612 Section 6.4, the Authority will modify the FitzPatrick Tecnnical Specifications to prohibit nandling of heavy loads over irradiated fuel in the spent fuel pool until measures are taken to satisfy the guidelines of NUREG-0612, Section 5.1.

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VII. . Screenwell Auxiliary Crane l

The Screenwell Auxiliary Crane is located in the west end of the Screenwell and Water Treatment Building. The crane has a hoist capacity of 8 tons and is used for removal of hatch pidgs to provide access to RHR service water pumps i

and motors, and to emergency service water pumps. The crane would be used to service these pumps only when a pump is already out ot service for maintenance or repair.

The pumps are separated so that the Division A and B RHR service water pumps are in separate rooms with the pumps

. spaced 25 feet apart. The emergency service water pumps are separated by 10 feet with a wall between them.

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-In the Authority's NUREG-0612 Phase I submittal (PASNY

-letter, J. P..Bayne to T. A. Ippolito, dated October 15, 1981, JPN-81-82), it was stated that a load drop when servicing inoperable pumps with this crane would not affect operable safe shutdown equipment. To accomplish this,.the Authority will modify the appropriate procedures to prohibit movement of heavy loads over operable safe shutdown equipment using this crane. Alternately, an analysis will'be performed to shoi that the consequences of a load-drop are acceptable.

VIII. Commitment Schedule The Autliority will fulfill thb above commitments by December 7, 1984.- ~

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