ML20137E976
| ML20137E976 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/07/1986 |
| From: | Beckham J GEORGIA POWER CO. |
| To: | Muller D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20137E981 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM 2253N, NED-85-806, TAC-56049, TAC-59542, NUDOCS 8601170379 | |
| Download: ML20137E976 (6) | |
Text
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Georgia Power Company 333 Piedmont Avenue Attnta Georgia 30308 Telephone 404 526-7020 Maihng Address:
Post Office Box 4545 Atlanta, Georgia 30302 h
Georgia Power J. T. Beckham, Jr.
tre southern electic system Vice President and General Manager Nuclear Operations NED-85-806 2253N January 7, 1980
. Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 Division of Boiling Water Reactor Licensing U. S. Nuclear. Regulatory Commission Washington, D. C.
20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REVISION TO PROPOSED TECHNICAL SPECIFICATION AMENDMENT PURGE / VENT ISOLATION-Gentlemen:
By letter dated August 20, 1985 (NED-85-577), Georgia Power Company (GPC) proposed to amend the Hatch Unit 1 Technical Specifications to reflect the addition of a high radiation isolation signal to the containment purge and vent valves.
In accordance with 10 CFR 50.90 as required by 10 CFR 50.59(c)(1), GPC proposes to revise that submittal.
The proposed revision clarifies which isolation signals will cause automatic closure of the containment purge and vent valves.
Attachnent 1 provides a detailed description of the proposed change and circumstances necessitating the change request. details the basis for our determination that the proposed change does not constitute an unreviewed safety question. details the basis for our determination that the proposed change does not involve significant hazards considerations. provides page change instructions for incorporating the proposed change.
A filing fee for this proposed revision is not required.
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Georgia Power A Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 Division of Boiling Water Reactor Licensing January 7, 1986 Page 2 In order to allow time for procedure revision and orderly incorporation into copies of the Technical Specifications, we request that the proposed amendment, once approved,by the NRC, be issued with an effective date to be no earlier than 30 days from the date of issuance of the amendment.
Pursuant to the requirements of 10 CFR 50.91, Mr. J. L. Ledbetter of the Environmental Protection Division of the Georgia Department of Natural Resources will be sent a copy of this letter and all applicable attachments.
J. T. Beckham, Jr. states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.
GEORGIA POWER COMPANY By:
Ik
[/J.T.Beckham,Jr.'
Sworn to and subscribed before me this 7th day of January, 1986.
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Notary PutWic'Geoqsa. State at Large Notary Public My Commissen Expires Aug 26,1986 JH/ht Enclosure xc: Mr. H. C. Nix, Jr.
Senior Resident Inspector Dr. J. N. Grace, (NRC-Region II)
Mr. J. L. Ledbetter 700WS
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j ENCLOSURE'1 e.
NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1
. REVISION TO PROPOSED TECHNICAL SPECIFICATION ' AMENDMENT PURGE / VENT ISOLATION
. The proposed change revises Table'3.7-1 to specify that either a Group 2 4
signal or a high containment radiation isolation ' signal will cause automatic
. closure of valves T48-F307, F308, F319, F320, F309, F324, F318, and F326.
. This. revision is necessary to make Table 3.7-1' accurately reflect the.
modifications to be made-to the isolation logic during the fall 1985 refueling outage as a result of design changes required to resolve NUREG 0737 Item II.E.4.2 (7).
The high' radiation. isolation trip setting is based on limiting the site boundary radiation dose to'the EPA Protective Action Guide (PAG) limit.
The technical specification trip setting limit of 138 R/hr ensures that the site boundary dose would _ not exceed a small fraction of. the PAG limits of.1 Rem Whole Body and.5 Rem Thyroid.
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ENCLOSURE 2 NRC DOCKET 50-321 7
OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAit PLANT UNIT l 6
REVISION'TO-PROPOSED TECHNICAL < SPECIFICATION AMENDMENT PURGE / VENT ISOLATION u
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Pursuant to 10 CFR 50.59, the Plant Review Board has reviewed the attached. proposed - amendment to the Plant Hatch Unit 1
Technical 1
Specifications 'and has determined that implementation of the-proposed amendment would not constitute an unreviewed safety question..
'^
PROPOSED CHANGE-Specify in ' Table 3.7-1 that-the containment purge and vent valves s
-close automatically on either a Group 2 containment isolation
, signal or a high containment radiation signal.
BASIS' 1The probability of-occurrence or the consequences of an accident or malfunction of1 equipment important to safety are not increased
~ above those analyzed in the-FSAR because the _ change has-no effect
-on the _opei ation of safety - related equipment.
n The possibility of-an accident or malfunction of.a different type than those_ analyzed 'in the FSAR is not _ created by this change c,
because no new failure made is introduced.
The margin of safety as defined in the Technical Specifications -is not reduced because the change has no effect on any existing n -
-Technical Specification.
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ENCLOSURE 3 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REVISION-TO PROPOSED-TECHNICAL SPECIFICATION AMENDMENT PURGE / VENT-ISOLATION Pursuant to 10 CFR 50.92, Georgia Power Company has evaluated the attached-proposed amendment to the Plant Hatch Unit 1
Technical Specifications: and has determined that implementation of the proposed
-amendment would not involve a significant hazard.
The basis for this
~ determination is as follows:
. PROPOSED-CHANGE Specify in Table 3.7-1 that the containment purge and vent valves close automatically on either a Group 2 containment isolation signal or a high containment radiation signal.
BASIS The proposed change is a purely administrative change which achieves consistency in the Technical Specifications.
This change does not affect the probability or consequences of an accident or malfunction analyzed in the FSAR. This change does not create the possibility of an accident or malfunction of a different type than any analyzed in the FSAR.
The margin of safety as defined in the basis for any Technical Specification is not affected.
The effect of this change is therefore within the acceptance criteria and the change is consistent with the Item (1) of the " Examples of Amendments That are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983 issue of the Federal' Register.
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c ENCLOSURE-4 NRC DOCKET 50-321 OPERATING LICENSE DPR-57
~EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REVISION T0 PROPOSED TECHNICAL SPECIFICATION-AMENDMENT PURGE / VENT ISCLATION The proposed-change to the Hatch Unit 1 Technical Specifications (Appendix Alto Operating License DPR-57) would be incorporated as follows:
Remove:Page Insert Page' 3.7-16 3.7-16
-3.7-20 3.7-20 F
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TABLE 3.7-1 PRIMARY CONTAINMENT ISOLATION VALVES' Isalation Number of. Power.
Max 1 mum Normal Action on.
Group Operated Valves Operating Position-Initiation (b)-
Valve Identification (d)
Inside outside Time (sec)
-(a)-
Signal (a) 1 Main steam line 4.
4 3<T<5 0
GC (B21-F022 A,B,C,D; B21-F028 A,B,C,0)
.1 Main steam line drain 1
1 15 C
SC (B21-F016,B21-F019) 1 Reactor water sample line 1
1 5
C SC (B31-F019,831-F020) 2 H2 -02 Analyzer system 2 each 5
0 GC (P33-P001) line 2(f)
Drywell purge inlet 2
5 C
SC w
'y (T48-F307,T48-F308) 2(f)
Drywell main exhaust 2
5 0
GC (T48-F319,T48-F320) 2 Drywell exhaust valve bypass to 2
5 C
SC standby gas treatment (T48-F341,T48-F340) 2 Drywell nitrogen make-up line 1
5 0
GC (normal operation) i (T48-Fll8A) 2(f)
Suppression chamber purge inlet 2
5 C
SC l
(T48-F309,T48-F324) 2(f)
Suppression chamber main exhaust 2
5 0
GC (T48-F318,T48-F326)
P
' Notes-t'o Table 3.7-1 (Concluded)
(f) Requires a Group 2 signal or a Primary Containment high radiation.
isolation signal For all-entries in Table 3.7-1 where.the number of isolation valves is equal to ~one outside containment and none inside containment-the : valve is in a
- series
- path with. at least one other containment isolated valve in the Table... For - example, T48-F118 is-in a series path with T48-F104, thus providing two in series power. operated containment isolation valves.
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3.7-20
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DirdctorofNuclearReactorRegulation Attention: Mr. a,....
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U. S. Nuclear Regulatory Commiss on Washington, D. C.
20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REVISION TO PROPOSED TECHNICAL SPECIFICATION AMENDMENT PURGE / VENT ISOLATION Gentlemen:
By letter dated ' August 20, 1985 (NED-85-577), Georgia Power Company (GPC) proposed to amend the Hatch Unit 1 Technical Specifications to reflect the addition of a high radiation isolation signal to the cont'ainment purge and vent valves.
In accordance with 10 CFR 50.90 as requirkd by 10 CFR 50.59(c)(1), GPC proposes to revise that submittal.
The proposed revision clarifies which isolation signals will cause automatic closure of the containment purge and vent valves. provides a detailed description of the proposed change ano.
circumstances necessitating the change request. details the basis for our determination that the proposed change does not constitute an unreviewed safety question. details the basis for our determination that the proposed change does not involve significant hazards considerations. provides page change instructioy for incorporating the proposed change.
A filing fee for this proposed revision is not required.
Director of Nuclear Reactor Regulation Attention: Mr.-John F. Stolz, Chief Operating Reactors Branch No. 4 ctober;25, 1985 Page
/
In order to allow time for procedure revision and orderly incorporation into copies of the Technical Specifications, we request that the proposed amendment, once approved by the NRC, be issued with an effective date to be no earlier than 30 days from the date of issuance of the amendment.
Pursuant to the requirements of 10 CFR 50.91, Mr. J. L. Ledbetter of the Environmental Protection Division of the Georgia Department of Natural Resources will be sent a copy of this letter and all applicable attachments.
J. T. Beckham, Jr. states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.
GEORGIA POWER COMPANY By:
J. T. Beckham, Jr.
Sworn to and subscribed before me thi day of Octob Notary Public JH/ht Enclosure xc: Mr. H. C. Nix, Jr.
Senior Resident Inspector Dr. J. N. Grace, (NRC-Region II)
Mr. J. L. Ledbetter-r
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r ENCLOSURE 1 NRC DOCKET 50-321 1
~
OPERATING-LICENSE DPR-57 4
~ EDWIN I.* HATCH NUCLEAR PLANT UNIT 1
. REVISION T0 PROPOSED TECHNICAL SPECIFICATION AMENDMENT PURGE / VENT' ISOLATION The' proposed change revises Table 3.7-1 to specify that either. a Group 2 isolation signal or a high containment radiation signal will cause automatic closure of valves T48-F307, F308, F319, F320, F309, F324, F318, and F326.
This _ revision' is necessary to make Table 3.7-1 accurately reflect the modifications to be made. to-the jsolat n logic dur g the fall 1985
- refueling outage % A a p y j
p,4 ' vun56 073 7 jb M. & 2 C h
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