ML20008G314
| ML20008G314 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/02/1981 |
| From: | Colbert W DETROIT EDISON CO. |
| To: | Kintner L Office of Nuclear Reactor Regulation |
| References | |
| EF2-53932, NUDOCS 8107070305 | |
| Download: ML20008G314 (3) | |
Text
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Detrol Ecison !E!!!!m-July 2, 1981 EF2 - 53932
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(b Mr. L. L. Kintner
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Division of Project Management NL
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Office of Nuclear Reactor Regulation li:
U. S. Nuclear Regulatory Caumission JUL O G 1981 Nashington, D. C.
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Dear Mr. Kintner:
//
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Reference:
Enrico Ferrli Atomic Power Plant, Unit 2 NRC Docket No. 50-341
Subject:
Additional Information on Bypass Leakage Testing The following items are in response to concerns stated during telecon on June 29 between Mr. John Lane and Mr. L. L. Kintner, NRC, and Mr. J. Honkala and Mr. M. Batch, Edison.
1.
LEAhAGE CRITERIA EOR, BYPASS LEAKAGE TESTING The two letters written on this subject (EF2-53495, June 8,1981 and EF2-53867, June 23,1981) are in-consistent. The first letter is correct. To sumarize that letter, the valves which have potential bypass leakage are:
V17 - 2009 V8 - 2198 V17 - 2010 V8 - 2200 V17 - 2036 V8 - 2232 V17 - 2037 V9 - 2044 V17 - 2024 V9 - 2005 V17 - 2025 V9 - 2022 V9 - 2023 The leak rate of these valves is measured as part of out Appendix J or Section XI programs. The testing medium is air or N, not water. The Bypass Icakage Program will 2
maintain a running total of these measurements and com-pare it with the maximum allowable. The decision on valve maintenance will be based on the closeness of these two numbers.
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~Mr. L. L. Kintner July 2, 1981.
EF2 - 53932-Page 2 i
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2.
ADDITIWAL INE0INATION IN BYPASS IEAKAGE V_ALVES WICH ARE NDP PRIMARY CONTADNENT ISO [ATIN VALW3
-'Ihere are four such lines:
1.
HPCI steam line drain to main condenser i
' 2.
RCIC steam line drain to main condenser 3.
HPCI punp discharge to condensate storage i
4.
RCIC pm p discharge to condensate storage
'ihe following items give additional information on the isola-tion valves in these lines.
a.
Each line has two valves in series.
t b.
'Ihe Design Criteria for these lines is Maan B through the second valve.
4 i
c.
Al' these valves are within secondary contain-ment.
d.
The valves on the HPCI steam drain pot (V17 - 2024, 2025) are supplied with divisional power; they I
close on HPCI block valve opening and on loss of power.
i e.
The valves on the RCIC steam drain pot (V17 - 2036, 2037) function same as HPCI valves.
f.
The valves on the HPCI pm p discharge to conden-sate stcrage (V8 - 2198. 2200) are supplied with l
Division II powdr - the same as HPCI. They close on containment isolation signals (RPV Ievel 2 and high drywell pressure).
g.' '1he valves on the RCIC punp discharge to condensate storage (V8 - 2232, 2200) are supplied with division-al power.
(Note that V8 - 2200 is omnon with HPCI).
V8 - 2232 is on same division as BCIC. It close.:
on RPV Invel 2 or RCIC injection valve opening.
3.
CONPADNENP LEAKAGE THROUGH C0tmOL ROD DRIVE SYSTEM PE2EITATIN Isakage from the CRD system into the-Reactor Building is detected for the full spectrum of leakage rates. Small leaks will be
I Mr. L. L. Kintner-July 2, 1981 EF2 - 53932 Page 3 detected by observation during daily inspection rounds of the control unit areas by operators. Large leaks will be detected by duty timers on Reactor Building floor drain sump pumps.
A large leak of reactor coolant from any INSERT line will be automatically isolated by the ball check valve in the CRD housing. Leaks of CRD supply water will be indicated by in-creased flow as continuously recorded in the control room.
The CRD directional control valves are normally closed and are automatically closed upon a reactor scram signal.
Ex-cessive leakages through the scram valves will be detected by duty timers on sump pumps.
Isakages through tr.e eight insert and eight withdrawa.. spare
,enetration tubes will be detected during Type A test 3.
We believe the above statements provide sufficient justification for concluding that these methods for leak testing of the control rr.d drives form an acceptable alternative to the requirement of Appendix J commensurate with the importance to reliability of this system.
Sincerely, hbdf ('t T/
W. F. Colbert 4%
Technical Director Enrico Fermi 2 WEC/MLB/dk I
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