ML20028C032
| ML20028C032 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 12/27/1982 |
| From: | Lentine F COMMONWEALTH EDISON CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-1.A.1.3, TASK-2.E.1.1, TASK-2.E.1.2, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.K.2.08, TASK-2.K.2.13, TASK-2.K.3.03, TASK-2.K.3.12, TASK-TM 5663N, GL-82-16, NUDOCS 8301050302 | |
| Download: ML20028C032 (4) | |
Text
[
5 Commonwrith Edison
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,'J Address Reply to: Post Office Box 767
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One First National Plaza. Chicago. Ilhnois
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Chicago. Illinois 60690
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December 2 7, 1982 Mr. Darrell G.
Eisenhut, Director Division o f Licensing U.S.
Nuclea r Regulatory Commissio n Washington, DC 20555
Subject:
Zion Station lhits 1 and 2 Response to Generic Le tter No. 82-16, NUREG-0737 Technical Specifications NRC Docket Nos. 50-295 and 50-304
References:
(a)
September 29, 1982, letter f rom D. G.
Eisenhut to all PWR Licensee s (b)
January 11, 1982, letter from S. A.
Va rg a t o L. O. De 1Geo rge (c)
January 12, 1982, letter from S. A.
Varga to L. O. De 1 Ge o rg e (d)
June 15, 1982, letter from D.
G.
Eisenhut to all Licensees (e)
December 31, 1979, letter from D.
L.
Peoples to D.
G.
Eisenhut (f)
March 12, 1980, letter from W. F.
Naughton to D.
G.
Eisenhut (g)
Decembr 15, 1982, letter f rom F.
G.
Lentine to H.R.
Denton (h)
November 22, 1982, letter from S. A.
Varga to L.
O. De l Geo rg e (i)
December 14, 1979, letter from D.
L.
Peoples to D.
G.
disenhut (j)
September 17, 19 81, l e t te r f r o m S. A.
Varga to L. O.
De l Geo rg e (k)
September 9, 19 81, l e t t e r f r o m S. A.
Va rg a t o L. O.
De 1 Geo rg e (1)
November 2, 1981, letter f rom F.
G.
Lentine to H. R. Denton (m)
January 15, 1981, letter from S. A.
Varga to J. S.
Abe l (n)
October 20, 1982, letter from S. A.
Varga to L. O.
De lGeo rg e (o)
April 12, 1982, letter from E.
D. Swartz to D.
G.
Eisenhut (p)
September 2, 1981, letter from S. A.
Varga to L. O.
De 1 Geo rg e 8301050302 821227 PDR ADOCK 05000295 g
P PDR
Dear Mr. Eisenhu t :
Re ference (a) provided guidance on Technical Specifications for a number o f NUREG-0737 items and requested Licensees to submit license amendments as appropriate.
Th e Attachment to this letter provides Commonwealth Edison's response for Zion Station.
One (1) signed original and f orty (40) copies of this tranmittal are provided for your use.
Please address questions regarding this matter to this office.
Ve ry truly yours, Frank G.
Lentin e Nuclea r Licensing Administrato r FGL /p1 Attachment
Attachment (1)
ST A Training (I.A.1.1)
Re ference (b) provided the results of the NRC's review o f this item, which indicated that our STA training program is acceptable.
However, since reference (a) indicated that further guidance will be provided pending the decision on the requirements by the Commission, we will await further clarification before submitting Technical Specifications on this item.
(2)
Limit Overtime (I.A.l.3)
Reference (c) provided the results of the NRC's review of this item, which indicated that our policy for limiting overtime is acceptable.
Reference (a) provided a revised version o f the Commission's policy statement on this subject.
Technical Specifications to require administrative procedures that implement our policy will be submitted under separate cover.
(3)
Short Term Auxiliary Feedwater System Evaluation (II.E.1.1)
In references (e) and (f) we submitted proposed Technical Specifications to comply with the NRC staff recommendations on this item.
In reference (g) we provided comments on the NRC's draf t Technical Specification transmitted in reference (h).
We are presently awaiting issuance o f the Technical Specifications by the NRC.
(4)
Safety Grade AFW System Initiation and Flow Indication (II.E.1.2)
In reference (1), we provided justification for our position that the existing automatic initiation and flow indication systems did not require modification and that no Technical Specification changes were required.
(5)
Dedicated Hydrogen Penetrations
( I I. E. 4.1 )
Reference (j) provided the results of the NRC's review of this item, which indicated that our design for containment hydrogen control penetrations is acceptable.
No additional containment isolation valves were added to meet the requirements, and therefore no Technical Specification changes are required.
( 6)
Containment Pressure Setpoint (II.E.4.2.5)
Re ference (k) provided the results o f the NRC's review of this item, which indicated that our containment pressure setpoint is acceptable.
Th ere fo re, no Technical Specification changes are required.
e (7)
Containmen t Pu rg e Val ve s (I I. E. 4. 2. 6)
In Reference (1) we provided comments on the model Technical Specifications transmitted in reference (k).
Thos e Technical Specifications that are applicable to our plant will be submitted following completion of the analytical work being perf ormed to demonstrate purge valve operability.
Pending completion o f the NRC's long-term review o f this item, we will i
continue to comply with the NRC's Interim Position o f January 15, 1981 (Reference (m)).
(8)
Radiation Signal on Purge Valves (II.E.4.2.7)
Reference (k) provided the results of the NRC's review o f this item, which indicated that our design is acceptable.
- However, we noted in our response of reference (1) that the radiation monitors that provide the closure signal are not safety-grade.
In any event, the existing Technical Specifications adequately specify the requirement for this function.
(9)
Upgrade B & W AFW System (II.K.2.8)
This item is not applicable for Zion.
- 11) 8&W Thermal - Mechanical Report (I I.K. 2.13)
This item is not applicable for Zion.
- 12) Reporting of SV and RV Failures and Challenges (I I.K. 3. 3)
Re ference (n) provided the results of the NRC's review of this item, which indicated that our commitment to report SV and RV f ailures and challenges is acceptable.
That commitment was reaffirmed in reference (o).
Technical Specifications that confirm this commitment will be submitted along with other Technical Specification changes intended to consolidate and clarify the various reporting requirements.
This project is scheduled for completion in 1983.
(13)
Anticipatory Trip on Tu rbine Trip (II.K.3.12)
Reference (p) provided the results o f the NRC's review of this item, which indicated that our design is acceptable.
This item is covered by the existing Technical Specifications.
5663N
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