ML20085J551
| ML20085J551 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/04/1983 |
| From: | Tauber H DETROIT EDISON CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20085J552 | List: |
| References | |
| EF2-65-368, NUDOCS 8310130229 | |
| Download: ML20085J551 (7) | |
Text
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Harry Tauber Group Vce Presglent Detroit Edison !Wi!!==
October 4, 1983 EF2 - 65,368 Director of Nuclear Reactor Regulation Attention: Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Youngblood:
Reference:
(1) Enrico Fermi Atomic Power Plant, Unit 2 NRC Docket No. 50-341 (2)
Letter, Detroit Edison to NRC, EF2-59173, September 22, 1982 (3)
Letter, NRC to Detroit Edison, March 16, 1983 (4) NRC Summary of May 17-18, 1983 Meeting with Detroit Edison, August 18, 1983
Subject:
Submittal of Revision 2 of Report on Inservice Testing of Pumps and Valves Attached for your review are forty (40) copies of Revision 2 to the Fermi 2 Inservice Testing Program for Pumps and Valves.
As agreed, this revision incorporates the necessary modifica-tions and clarifications to the reference (2) program as a consequence of your reference (3) letter and the reference (4) meeting.
Attachment A to this letter includes some comments relevant to the revised program and status of the current applicable drawings.
Copies of color coded drawings are being transmitted separately to Mr. Gary Hammer, Mechanical Engineering Branch (MEB) and to your consultants at EG&G, Idaho to aid in your review.
In addition, Attachment B to this letter summarizes Edison's response to the open items identified in the reference (4) meeting minutes.
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8310130229 831004 PDR ADOCK 05000341 A
PDR j
Mr. B. J. Youngblood October 4, 1983 EF2 - 65,368 Page 2 4
If you should have any further questions, please contact Mr. Larry E. 'Schuerman, (313) 586-4207.
Sincerely, i!
h dttachment cc:
P. Byron (w/o attachment)
C. G. Hammer, NRC-MEB W. H. Hubble, EG&G, Idaho M. D. Lynch, NRC-DOL (w/o attachment) t i
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ATTACHMENT A IST Program Comments
- 6M721-2023 Feedwater System 1.
The installed excess flow check valves V13-2392 and V13-2393 are in the IST program, but do not appear as excess flow check valves on 6M721-2023, Revision N.
6M721-2032 Sump Pump - Radwaste System 1.
The enclosed color coded P&ID is Revision R for drawing 6M721-2032. The IST program, Revision 2, used Revision Q.
The changes from Revision Q to Revision R have no impact on @ IST program.
61721-2145-66 Traversing In-Core Probe System 1.
The check valve C51-J009 does not appear on Revision A of 61721-2145-66. Exactly what drawing C51-J009 will appear on has yet to be decided.
6M721-2027 Closed Cooling Water and Emergency Equipment Cooling Water Systems 1.
The information in 6M721-2027 has been transferred to 6M721-5357 and 6M721-5444. Drawing 6M721-2027 has been cancelled.
6M721-2081 Control Rod Drive Hydraulic System 1.
Valve C11-144 at coordinate A-8 should be valve C11-114, as shown in the IST program.
6M721-2083 Residual Heat Removal System, Division II 1.
Valve V13-7688 had been installed, however, they do not l
appear in Revision M of 6M721-2083. Valve V13-7688 is
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on a 1" bypass line around the containment isolation l
valve E11-F050B (V8-2164). Valve V13-7688 allows the l
pressure to be equalized across E11-F050B so that this i
testable check valve can be exercised during cold shutdown.
2.
Valve V8-3874 has also been installed and is not shown on l
Revision M of 6M721-2083. This valve is on a 3/4" bypass line around the containment isolation valve E11-F608 (V8-3407). This bypass line allows heated water trapped i
inside the RHR shutdown cooling suction line to be relieved l
into the reactor vessel.
'Ihe comments generally note variances between the color coded drawings submitted for review and the Pump and Valve Program. The variances reflect approvedengineering changes not yet formally incor-porated in drawings. Drawings are revised in accordance with approved l.
procedures and may have up to five changes against the11 before revision is required.
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t 6M721-2084 Residual Heat Removal, Divison I 1.
Valve V13-7687 has been installed but does not appear on Revision P of 6M721-2084. Valve V13-7687 is on a 1" bypass line around the containment isolation valve E11-F050A(V8-2163). Valve V13-7687 allows the. pressure to be equialized'across E11-F050A so that this testable check valve can be exercised during cold shutdown.
GM721-4100 Torus Water Management System 1.
The enciosed color coded P&ID is Revision H for drawing 6M721-4100. The IST program, Revision 2, used drawing Revision G.
The changes between Revision G and Revision H have no impact on the IST program.
6M721-5449 Control Rod Drive Hydraulic System - Part 2 1.
Relief valve C11-F012 (V22-2027) originally was located on P&ID 6M721-2081, Revision I.
It should appear with the scram discharge volume on 6M721-5449, however, C11-F012 is not shown on Revision 0 of 6M721-5449.
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ATTACHMENT B 4
Responses to NRC Comments F.
RBCCW and EECW (6M721-2027)
Note: The information on 6M721-2027 has been transferred to 6M721-5357 and 6M721-5444. 6M721-2027 has been cancelled.
F.1 As stated in FSAR Section 9.4.5 and paragraph 6.2.2 of the EF2 Safety Evaluation Report, NUREG-0798, "The Drywell cooling system is not required for postaccident contain-ment cooling." Therefore, valves P44-F246 (V8-3056) and P44-F274 (V8-2488) are not important to safety in the accident condition. However, these valves are important for maintaining Class C EECW integrity, therefore they must close.
F.2 Valves P44-F608 (V8-2487) and P44-F614 (V8-3058). These valves must close for reasons given in F.1.
F.3 Valves P44-F282A (V8-3888), P44-F282B (V8--3887), P44-F615 (V8-3889) and P44-F616 (V8-3890) are containment isolation valves and must be able to close to provide containment isolation. Because drywell cooling is not required for postaccident containment cooling, these valves need not open.
H.
H.1 Detroit Edison is investigating the removal of the valve internals from check valves E21-F0178 (V8-3181) which are lines that lead from relief valves to the suppression pool, since these valves do not perform a safety related function. Because there is a high probability that the valve internals will be removed, these check valves along with Relief Request VR-19 have been deleted from the program.
If removal of the valve internals is not possible, valves E21-F107A and E21-F017B will be put back into the program and appropriate testing procedures will be developed.
H.2 The pairs of valves E21-F029A and E21-F030A, and E21-F029B and E21-F030B will be confirmed closed by a positive method as described in Relief Request VR-40.,
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H.3 According to FSAR Section 5.5.13, valves E21-F032A (V22-2109) and E21-F032B (V22-2004) provide an overpressure protection function. -Therefore, they have been categorized A/C.
H.4 Refer to response H.2.
M.
Control Rod Drive Hydraulic (6M721-2081)
M.1 An appropriate testing method and frequency for C11-115 and C11-138 will be submitted in October, 1983.
O.
Resideual Heat Removal (6M721-2083) 0.1 The "V" number for E11-F001B has been changed from V22-2024 to V22-2642. According to FSAR Section 5.5.13, this valve and valve E11-F029 (V22-2033) perform over-pressure protection functions and are categorized as active A/C valves. Valve E11-F097 (V22-2585) has been removed from the RHR system due to the deletion of the steam condensing mode of operation.
0.6 Valves E11-F035B (V8-3245) and E11-F039B (V8-3153) have currently been deleted from the IST program for the reason given in H.1.
-0.
Residual Heat Removal (6M721-2084) 0.1 The "V" number for E11-F001A has been changed from V22-2026 to V22-2643. According to FSAR Section 5.5.13, this valve performs an overpressure protective function.
l Therefore, E11-F001A will be exercised in accordance with Table IWV-3510.
0.3 Valves E11-F035A (V8-3244) and E11-F035B (V8-3155) have currently been deleted from the IST program for the reasons given in H.1.
' O.6 Valve V8-3205 has been removed from the plant due to deletion of steam condensing mode. Valve V8-3411 is not currently included in the IST program for the reason given in H.1.
P.
Combustible Gas Control (6M721-2087)
P.1 The Combustible Gas Control System must be available during postaccident conditions. Therefore, valves T48-F-16A (V22-2121) and T48-F0168 (V22-2122) provide an overpressure protection function and are included in the IST program as active valves. The check valves V4-2145 and V4-2146 will not currently be included in the IST program for the reason give in H.1.
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