ML18078A864
| ML18078A864 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/12/1979 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7902230141 | |
| Download: ML18078A864 (3) | |
Text
e OPS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 Director of Nuclear Reactor Regulation U~S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
Mr. Olan D. Parr, Chief Gentlemen:
Light Water Reactors Branch 3 Division of Project Managemet REQUEST FOR EXEMPTION 10CFR50, APPENDIX G NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 February 12, 1979 Public Service Electric and Gas Company hereby requests an exemption to the requirements of 10CFRSO, Appendix G, Para-graph IV.A.4, regarding the Salem No. 2 Unit reactor vessel bolting material lateral expansion measurements and impact energy requirements.
Impact energy testing of the No. 2 Unit, reactor vessel bolt-ing material was* performed at 10°F and.lateral. expans*ion measurements were not required.
The results of the impact energy tests showed that all the bolting material meets the 45 foot-pound requirements of Appendix G at l0°F except 1 end of one bar used for closure head nuts and washers.
Data available on bolting material over a range of temperatures indicates that impact energy (and lateral expansion) values at a test temperature of 50°F will be higher than those made of the same material tested at 10°F.
Therefore, it is expected that all of the No. 2 Unit bolting materials would exhibit at least 45 foot-pounds if tested at 5-0°F, which is considered to be the lowest preload or servica temperature.
Although lateral expansion measurements for the bolting material are not available, it is expected that these materials would exhibit at least 25 mils if tested at so°F.
To demonstrate this, material properties for bolting material comparable to the No. 2 Unit bolting material are given in the attached table.
This comparable mater.ial exhibited at least 25 mils expansion at 40°F, which is The Energy People 7902230\\ L\\ \\
Director of Nuclear Reactor Commission 2/12/79 than the lowest preload or service temperature.
This data is representative of the lateral expansion measurements that would have been exhibited by the bolting material if tested at 50°F.
Based on the above information, it is expected that the Salem No. 2 Unit bolting material would exhibit at least 45 foot-pounds and 25 mils lateral expansion if tested at 50°F.
On this basis, PSE&G hereby requests an exemption to the requirements of 10CFR50, Appendix G, Paragraph IV.A.4.
Should you have any further questions in this regard, please do not hesistate to contact us.
3J2:53/54 Very truly yours,
-1
/_/ I 1;* I
- C L l it-T[(_ _/-.
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R. L. Mi ttl l~}j~_/
General Manager -
Licensing and Environment Eng~neering and Construction
REACTOR VESSEL BOLTING MATERIAL PROPERTIES CLOSURE HEAD STUDS r
l
't.~
InClication 0.2% YS UTS
- Elong, RA Energy at 40F Lat. Ex pans :i.on of Heat Grade Bar NO, KSI KSI BHN FT-LBS MILS A
AS40,.B23 281 130.3 lS0,8 18.0 60,8 341 SS-SS-54,5 33-30-33 A
AS40, 823 2Bl 133.3 lS0.8 17.0 SS.7 37S 46-48-48,5 26-29-29 A
AS40, B23 lB5 133.4 152,1 17.5 S7.7 363 4S-48-45 26-29-26 A
AS40, B23
!BS 140.2 1S8.6 16.5 55,Q 375 46-47-46.5 26-27-26 B
AS40 I B23 lDS 139.2 1S6.l 17.0 56.9 363 61-61-62 33-34-36 B
AS40 I B23 1B5 lS0.2 166. 6 15.0 5S.9 37S s2-so-so 29-29-29 B
AS40, B23 2BS 144 ;8 160.8 lS.S S7.8 341 S9.S-60-S9.5 33-32-32 B
AS40 I B23 2B5 1S3.0 168.8 15.0 S4.6 363 47-48.S-48 26-30-28 c
AS40, B23 BS 132.8 lS0.4 17.S S9.4 331 66.S-66-66.5 44-44-44 c
,11.S40 I B23 BS 139.0 1S6.6 17.0 S8.S 363 S2. S-S3-S4 31-31-33 D
AS40 I B23 BS 132.3 1S6.3 17.o S4.9 3S2 S6-S3.S-S6 32-33-31 D
AS40 I B23 BS 141.4 161.9 16.0 S4.8 37S 4S-46-4S.S 2S-26-26 e
E A540 I B23 B4 131.3 lSl.4 17.0 S9.4 331 68-66.S-67.5 43..;,44-4S E
AS40 I B23 B4 134.8 lS6.6 16.0 S7.4 363 S3-S3.S-S2.5 32-33-33 F
AS40 I B23 lA 138.0 1S2. s 17.0 S4.7 331 53, S4, 53 28, 28, 30 F
AS40 I B23 lB 140.0 1S3.5 18.0 56.S 3S2 52 I 53 I 54 31, 26, 29 F
AS40, B23 2A 137.0 153.0 18.0 54.7 331 56, 49, S7 43, 37, 37 F
A540 I B23 2B 141.5 156.o 17.0 54.1 3S2
~A 1 54 1 55 42, 37, 39 F
AS40, B23 3A 142.5 159.0 16.0
- 52. 5 331 4o, 48, 48 28, 27, 28 F
A540 I B23 3B l37.0 152.5 16.0 54.9 363 49, 48, 50 26, 25, 25 F
A540 I B23 4A 144.0 160.0 16.0 so.a 331 51, 48, 50 36, 32, 32 F
A540, B23 4B 152.o 165.o 15.0 49.2 363 46, 47, 47 28, 27, 28 F
AS40 I B23 5A 140.0 156.0 17.0 so.a 321 48 I 52 I 54 33, 35, 38 F
AS40, B23
- SB 148.0 162.s 17.0 52.5 363 52 I 46 I 48 33, 31, 26 F
AS40 I B23 6A 145,0 159.5 18.0 55.5 321 49 I 5Q I 50 31, 32, 29 F
AS40 I B23 6B 146.5 160. ()
15.0 58.6 363 49 I Sl I 51 26, 35, 33 F
A540 I B23 7A 140.o.
155.0 18.0 56.5 341.
55, 52, 51 32, 30, 2S F
A540 I B23 7B 149.5 164.0 16.0 s2.0 363 48 I *4a I 46 28, 32, 27 F
A540, B23 BA 143.0 157.5 17.0 56.8 341 4S, so, 47
- l8 I 3 2 I 2 6 F
A540 I B23 BB 146.0 161.5 16.0 52.e 363 47, 47, 46 28, 21, 26 G
A540 I B23 lA 142.0 157.5 16.0 56.5 321 52, 53, 53
. 34, 37, 34 G
A540 1 B23 lB 146.0 162.5 15.5 53.3 363 45, 49, 47 25, 31, 25 G
A540 I B23 2A 139.5 153.5 1*7.o 57.3 321 51, 53, 55 35, 34, 33 G
A540 I B23 2B 136.0 153.0 16.0 53.3 363 so, 48, 47 28, 29, 26 e
CLOSURE HEAD NUTS & WASHERS H
A540 I B23 3153A 142.5 161.1 17.9 56.0 341 55-54-52 29-27-28 H
A540 I B23 315~8 137.5 156.5 19.3 47.2 341 49-50-49 25-26-31 I
A540 I B23 lA 146 *. 9 161.2 18.l 55.l 341 50 I 55 I 58 38 I 40 I 42 I
A540 I B23 lB 146.8 163.8 19.9 57.4 341 53, 54, 52 40, 40, 38 I
A540 I 823 lA 157.l 169. 4 19.5 55.l 363 so, 51, so 38, 40, 40 I
A540 1 B23 lB 148.0 162.S 19.5 56.3 363 so, 45, 45 28; 25, 36 EAL:peg MP79 l 01
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