ML020350476
| 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: |
| References | |
| Download: ML020350476 (8) | |
Text
AMERGEN-NRC Meeting Technical Specification Change Request No. 281 Heavy Load Handling - Reactor Building Crane
- 1.
Introduction
- 2.
Objectives Provide Information on Crane Modifications.
Obtain Clarification on Certain RAT Questions.
- 3.
Licensing Basis
- 4.
Background
Paul Czaya 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.
b) Structural Modifications.
Dave Weber Chuck Ramdeen
- 6.
Request for Additional Information a) Draft responses prepared.
b) Questions requiring additional clarification.
Paul Czaya/Chuck Ramdeen Paul Czaya Paul Czaya
Introduction o Reactor building crane upgraded August 2000.
- License amendment application 4/4/01.
(TSCR 281) submitted
- 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)
"* 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.
.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.
I