A04839, Responds to 850419 Request for Addl Info Re post-trip Review Program,Per Generic Ltr 83-28.Revised Procedure Sp 2671, Duty Officer Requirements After Trip or ESF Actuation & Procedure EOP 2525, Std Post-Trip Actions Encl: Difference between revisions
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1s | 1s NORTHEAST UTHJTIES o.n.,.i Orric... seio n st,..t. s.<iin. Conn.ciicut EsYENEsSNc P.O. BOX 270 x.cn cia w cwa' HARTFORD. CONNECTICUT 06141-0270 L | ||
NORTHEAST UTHJTIES | L J CZO702%".l. | ||
(203) 665-5000 May 28,1985 Docket No. 50-336 A04839 Director of Nuclear Reactor Regulation Attn: | |||
Mr. James R. Millers, Chief Operating Reactors Branch #3 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 | |||
==References:== | ==References:== | ||
(1) | (1) | ||
(2) | : 3. R. Miller to W. G. Counsil, dated April 19,1985. | ||
(2) | |||
W. G. Counsil letter to D. G. Eisenhut, dated March 16,1984. | |||
Gentlemen: | Gentlemen: | ||
Millstone Nuclear Power Station, Unit No. 2 Response to Generic Letter 83-28 Generic Implications of Salem ATWS Events Reference (1) requested Northeast Nuclear Energy Company (NNECO) to provide additional information regarding its post-trip review program and procedures for Millstone Unit No. 2 (Item 1.1 of Generic Letter 83-28). | Millstone Nuclear Power Station, Unit No. 2 Response to Generic Letter 83-28 Generic Implications of Salem ATWS Events Reference (1) requested Northeast Nuclear Energy Company (NNECO) to provide additional information regarding its post-trip review program and procedures for Millstone Unit No. 2 (Item 1.1 of Generic Letter 83-28). | ||
This information was previously provided in Reference (2), which was apparently not reviewed for the Reference (1) Safety Evaluation. However, the procedure included in Reference (2) has since been revised. This levised procedure, SP 2671, Duty Officer Requirements Af ter a Trip or ESF Actuation, and a related procedure, EOP 2525, Standard Post Trip Actions, are attached for your use. | This information was previously provided in Reference (2), which was apparently not reviewed for the Reference (1) Safety Evaluation. However, the procedure included in Reference (2) has since been revised. This levised procedure, SP 2671, Duty Officer Requirements Af ter a Trip or ESF Actuation, and a related procedure, EOP 2525, Standard Post Trip Actions, are attached for your use. | ||
These procedures provide information sufficient to resolve the open items of Reference (1), but if you should have questions, please feel free to contact us. | These procedures provide information sufficient to resolve the open items of Reference (1), but if you should have questions, please feel free to contact us. | ||
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY d ,%.B | Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY d,%.B | ||
: 3. F. Opeka Senior Vice President t | : 3. F. Opeka Senior Vice President t | ||
By: C. F. Sears | 8506070284 850528 By: C. F. Sears O | ||
I PDR ADOCK 05000336 Vice President P | |||
PDR f | |||
T 1 | T 1 | ||
Docket No. 50-336 Attachment Millstone Nuclear Power Station, Unit No. 2 Post Trip Procedures r}} | |||
Latest revision as of 11:13, 12 December 2024
| ML20129G471 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/28/1985 |
| From: | Opeka J, Sears C NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | John Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20129G476 | List: |
| References | |
| A04839, A4839, GL-83-28, NUDOCS 8506070284 | |
| Download: ML20129G471 (2) | |
Text
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1s NORTHEAST UTHJTIES o.n.,.i Orric... seio n st,..t. s.<iin. Conn.ciicut EsYENEsSNc P.O. BOX 270 x.cn cia w cwa' HARTFORD. CONNECTICUT 06141-0270 L
L J CZO702%".l.
(203) 665-5000 May 28,1985 Docket No. 50-336 A04839 Director of Nuclear Reactor Regulation Attn:
Mr. James R. Millers, Chief Operating Reactors Branch #3 U. S. Nuclear Regulatory Commission Washington, D. C. 20555
References:
(1)
- 3. R. Miller to W. G. Counsil, dated April 19,1985.
(2)
W. G. Counsil letter to D. G. Eisenhut, dated March 16,1984.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Response to Generic Letter 83-28 Generic Implications of Salem ATWS Events Reference (1) requested Northeast Nuclear Energy Company (NNECO) to provide additional information regarding its post-trip review program and procedures for Millstone Unit No. 2 (Item 1.1 of Generic Letter 83-28).
This information was previously provided in Reference (2), which was apparently not reviewed for the Reference (1) Safety Evaluation. However, the procedure included in Reference (2) has since been revised. This levised procedure, SP 2671, Duty Officer Requirements Af ter a Trip or ESF Actuation, and a related procedure, EOP 2525, Standard Post Trip Actions, are attached for your use.
These procedures provide information sufficient to resolve the open items of Reference (1), but if you should have questions, please feel free to contact us.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY d,%.B
- 3. F. Opeka Senior Vice President t
8506070284 850528 By: C. F. Sears O
I PDR ADOCK 05000336 Vice President P
PDR f
T 1
Docket No. 50-336 Attachment Millstone Nuclear Power Station, Unit No. 2 Post Trip Procedures r