ML020350476

Summary of Meeting with Amergen Energy Company, LLC, Enclosure 3, on Oyster Creek Nuclear Generating Station Concerning the Handling of Heavy Loads Over Irradiated Fuel

ML020350476
Person / Time
Site:	Oyster Creek
Issue date:	01/11/2002
From:	Pastis H NRC/NRR/DLPM/LPD1
To:	NRC/NRR/DLPM/LPD1
Pastis H, NRR/DLPM, 415-1261
Shared Package
ML020350586	List: ML020350476 ML020350481 ML020350530
References
Download: ML020350476 (8)

Text

AMERGEN-NRC Meeting Technical Specification Change Request No. 281 Heavy Load Handling - Reactor Building Crane

1. Introduction Paul Czaya

2. Objectives Paul Czaya

- Provide Information on Crane Modifications.

- Obtain Clarification on Certain RAT Questions.

3. Licensing Basis Paul Czaya

4. Background Tom Quintenz a) Crane modified to single-failuwe-proof criteria.

I. Rating increased from 100 tons to 105 tons.

2. Design changed to comply with NUREGs 0554 and 0612, Appendix C.

b) Building structure modified to meet seismic loads with rated load.

c) Rigging specified per Section 5.1.6 ofNUREG-0612.

5. Modifications/Upgrades to Reactor Building Crane/Structure a) Crane Modifications. Dave Weber b) Structural Modifications. Chuck Ramdeen

6. Request for Additional Information Paul Czaya/Chuck Ramdeen a) Draft responses prepared.

b) Questions requiring additional clarification.

Introduction o Reactor building crane upgraded August 2000.

• License amendment application (TSCR 281) submitted 4/4/01.

• NRC RAI issued 8/24/01.

Objectives

• Provide Information on Crane Modifications.

• Obtain Clarification on Certain RAI Questions

Current Licensing Basis for Heavy Loads Technical Specifications

• Technical Specifications 5.3.1 .B and 5.3.1 .C were introduced by Amendment 22 on March 30, 1977 in association with fuel pool expansion as 5.3.1 .D and 5.3.1 .E, respectively.

• 30 ton cask weight limit removed from 5.3.1.E by Amendment 77 on October 29, 1984 (renumbered by Amendment 121 on April 11, 1988).

• Shield plug exclusion added to 5.3.1 .B by Amendment 187 on November 7, 1996.

Current Licensing Basis for Heavy Loads (CONTINIJED)

NUREG-0612 NRC SER dated June 21, 1983 documented Oyster Creek compliance with NUREG-0612 (Phase 1).

- Section 5.1.1 general guidelines and 5.3 interim protection measures met.

"*Generic Letter 85-11 issued in June 1985 cancels Phase 2 of NUREG-0612.

"*Full-term operating license SER (NUREG-1382, Section 9.1.2, January 1991) reiterates NUREG-0612 Phase I compliance as licensing basis.

"*In addition, Bulletin 96-02 response (6/11/96) committed to evaluate heavy load drops during power c~peration to ensure no loss of safety function.

Current Licensing Basis for Heavy Loads (CONTINUED) 10 CFR 50.59

• Reactor building crane upgraded August 2000.

- Single-failure-proof guidelines met (NUREG-0612, Section 5.1.6 and Appendix C, and NUREG-0554).

- Combined with Phase 1 guideline compliance the criteria of Section 5.1 are met for Phase 2.

• Use of the reactor building crane does not require consideration of load drops.

- 10 CFR 50.59 evaluation concluded no unreviewed safety questions involved.

Proposed Changes to Technical Specifications

• TSCR 281 proposes to delete Specifications 5.3.1.B and 5.3.1.C. based on:

- Reactor building crane and lifting devices satisfy NUREG-0612, Section 5.1.6 criteria for a single-failure-proof handling system.

- NUREG-0612, Section 5.1 requirements are met by single-failure proof handling system combined with Phase 1 NUREG-0612, Section 5.1.1 general guideline commitments already in place.

- Load drop consequences need not be considered.

• NUREG-0612, Section 5.3 interim protection measures no longer applicable.

- Guidelines of Section 5.1 are satisfied.

- Heavy load Tech Spec restriction no longer required.

. . I

.0 Background

"*Reactor building crane modified to single-failure-proof criteria.

- Rating increased from 100 tons to 105 tons.

-Design changcd to comply with NUREGs 0554 and 0612, Appendix C.

"*Reactor building structure modified to meet seismic loads with rated load on crane.

"*Rigging specified per Section 5.1.6 of NUREG-0612.