ML20080N077
| ML20080N077 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/28/1983 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | John Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20080N080 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8310040353 | |
| Download: ML20080N077 (4) | |
Text
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A B ALTIM ORE GAS AND ELECTRIC CHARLES CENTER. P. O. BOX 1475. BALTIMOR E, MARYLAND 21203 ARTHUR E. LUNDVALL. JR.
Vict PRES 4 DENT Sumv Director of Nuclear Reactor Regulation Attention: Mr. 3. R. Miller, Chief Operating Reactors Branch #3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Calvert Cliffs Nuclear Power Plant Units Nos.1; Dockets Nos. 50-317 Performance Testing of Safety and Relief Valves Gentlemen:
Action Item II.D.1 of NUREG-0737 required all utilities to demonstrate that pressurizer safety and relief valves will open and shut under expected flow conditions. It
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piping reactions on safety and relief valve operability.further required det Reports certifying valve operability and analyzing discharge pipe effects are now complete for Unit 1.
The purpose of this letter is to transmit these reports and to outline our plans for completing certain pipe support modifications.
demonstrated based on a combination of applicable test data and an in addition, conservative analysis of safety and relief valve discharge piping Indicates that all design load stresses on piping and fittings are within allowable limits.
The analysis results also indicate that 10 of the 3/ existing pipe supports may 4
experience stresses that exceed code allowables with the potential for minor deformation; however, this deformation would not affect safety and relief valve operability.
Our review of the analysis results and methodology have led us to believe that although an analysis using less conservative methodology would yield resultant stresses well within the acceptable range, such an effort would not be cost effective.
Consequently, we have decided in this case to modify the 10 supports to increase their strength.
Field engineering to determine the optimum method of pipe support modification will be completed during the scheduled Fall,1983 outage.
Actual modification of the suoports will be completed during the next regularly scheduled outage for Unit 1 (Spring 1985).
/f/A 0310040353 830928 PDR ADOCK 05000317 P
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- Mr. 3. R. Miller Septsmber 28,1983 If you should have any questions, please do not hesitate to contact us.
Very truly yours, OieC-/bc AEL/KAM/BSM/vf
Enclosures:
- 1. Pressurizer Relief Valve Discharge Piping Qualification for Unit No.1, Calvert Cliffs Nuclear Power Plant, Bechtel Report on Task 05088, dated September 28,1983
- 2. Calvert Cliffs Units 1 and 2 Pressurizer Safety Valve Operability Report, CEN-248(B) Rev 1, dated September 1983.
cc: 3. A. Biddison, 3r. Esq.
G. F. Trowbridge, Esq.
Mr. D. H. Jaffe, NRC.
Mr. R. E. Archtizel, NRC I
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.s.,
BALTIMORE GAS AND ELECTRIC CHARLES CENTER R O. BOX 1475 BALTIMORE, MARYLAND 21203 l
September 28,1983 wee em. ova Supply Director of Nuclear Reactor Regulation l
Attention: Mr. 3. R. Miller, Chief l
Operating Reactors Branch #3 l
Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Calvert Cliffs Nuclear Power Plant Units Nos.1; Dockets Nos. 50-317 Performance Testing of Safety and Relief Valves Gentlemen:
i Action Item II.D.1 of NUREG-0737 required all utilities to demonstrate that pressurizer safety and relief valves will open and shut under expected flow conditions. It further required determination of the effects, if any, of safety and relief valve discharge piping reactions on safety and relief valve operability.
Reports certifying valve operability and analyzing discharge pipe effects are now complete for Unit 1.
He l
purpose of this letter is to transmit these reports and to outline our plans for completing l
certain pipe support modifications.
1 l
The operability of the Unit I safety and relief valves has been adequately I
demonstrated based on a combination of applicable test data and analysis. In addition, conservative analysis of safety and relief valve discharge piping indicates that all design load stresses on piping and fittings are within allowable limits.
De analysis results also indicate that 10 of the 84 existing pipe supports may experience stresses that exceed code allowables with the potential for minor deformation; however, this deformation would not affect safety and relief valve operability. Our review of the analysis results and methodology have led us to believe that although an analysis using less conservative methodology would yield resultant stresses well within the acceptable range, such an effort would not be cost effective.
Consequently, we have decided in this case to modify the 10 supports to increase their l
strength.
Field engineering to determine the optimum method of pipe support l
modification will be completed during the scheduled Fall,1983 outage.
Actual modification of the supports will be completed during the next regularly scheduled outage for Unit 1 (Spring 1985).
l i.
7,-
Mr. 3. R. Miller Sept 2mber 28,1983 If you should have any questions, please do not hesitate to contact us.
Very truly yours, 7
f.
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AEL/KAM/BSM/vf I
Enclosures:
- 1. Pressurizer Relief Valve Dischar e Piping Qualification for Unit No.1, Calvert Cliffs Nuclear ower Plant, Bechtel Report on Task 05088, dated September 28,1983
- 2. Calvert Cliffs Units I and 2 Pressurizer Safety Valve Operability Report, CEN-248(B) Rev 1, dated September 1983.
l cc: 3. A. Biddison, Jr. Esq.
G. F. Trowbridge, Esq.
Mr. D. H. Uaffe, NRC Mr. R. E. Archtizel, NRC l
1 I
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