ML20215L546
| ML20215L546 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/15/1987 |
| From: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-87-06, GL-87-6, LIC-87-384, NUDOCS 8706260092 | |
| Download: ML20215L546 (13) | |
Text
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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 402/536 4000 l
June 15, 1987
{
LIC-87-384 i
U. S. Nuclear Regulatory Commission l
1 Document Control Desk Washington, DC 20555 f
l Gentlemen:
SUBJECT:
Periodic Verification of Leak Tight Integrity of Pressure l
Isolation Valves (Generic Letter 87-06) l
Reference:
Docket No. 50-285 The Omaha Public Power District received the subject letter dated March 13, i
1987.
Pursuant to the provisions of 10 CFR 50.54(f), please find enclosed i
0 PPD's responses to the information requested in that letter. Table I provides a list of those pressure isolation valves that interface with the Reactor Cool-ant System. Table 11 provides a tabulation of the periodic tests performed for each of the valves.
Sin rely, l
R. L. Andrews Division Manager Nuclear Production RLA/rh Attachments c:
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, DC 20036 A. Bournia, NRC Project Manager R. D. Martin, NRC Regional Administrator P. H. Harrell, NRC Senior Resident Inspector 1
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.is sic.i emps men rgugopponunny u
l UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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t Omaha Public Power District
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Docket No. 50-285 (Fort Calhoun Station,
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Unit No. 1)
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AFFIDAVIT R. L. Andrews, being duly sworn,-hereby deposes and says that he is duly author-ized to sign and file with the Nuclear Regulatory Commission the attached re-sponse.to Generic Letter 87-06 dated March 13, 1987; that he is familiar with the content thereof; and that the matters set forth therein are true and correct'to the best of.his knowledge, inf m tion and belief.
R. L. Andrews Division Manager i
Nuclear Production
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i STATE OF NEBRASKA)
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ss COUNTY OF DOUGLAS)
Subscribed and sworgto before me, a Motary Public in and for the State of Nebraska on the 15 day of June,1987.
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TABLE I VALVE PAIRS
_ Safety-Iniection Pressure Isolation Valves A.
1 First Isolation.'
Second Is'ola' tion ~
Pathway f
Loo'p 1A-SI-216 SI-215 To SI-6B SI-216 SI-200 LPSI-SI-216 SI-201-HPSI SI-216 SI-202 HPSI SI-216 PCV-2929 Leakage SI-216 SI-368 SI-200 Bypass Loop'1B SI-220 SI-219 To SI-6A SI-220~
SI-203 LPSI-SI-220 SI-204 HPSI SI-220 SI-205 HPSI SI-220 PCV-2909 Leakage
].
SI-220 SI-369 SI-203 Bypass Loop 2A SI-208-SI-207 To SI-6C SI-208 SI-194
'LPSI SI-208' SI-195 HPSI SI-208 SI-196 HPSI SI-208 PCV-2949 Leakage-1 SI-208 SI-366 SI-194 Bypass Loop 28 SI-212 SI-211 To SI-60 SI-212.
SI-197 LPSI I
~SI-212 SI-198 HPSI I
SI-212 SI-199 HPSI SI-212 PCV-2969 Leakage SI-212 SI-367 SI-197 Bypass i
B.
Shutdown Coolina Pressure Isolation Valves Penetration'M-16 First Isolation Second Isolation Loop 2 HCV-348 HCV-347 i
C.
_ aste Discosal Pressure Isolation Valves W
First Isolation Second Isolation Pathway l
Loop 1A-RC-124 RC-132 Reactor Coolant Drain Tank Loop 1A SI-216 SI-307 LPSI Drain To Reac. Coolant Drain Tank j
Loop 18.
RC-123 RC-130 Reactor Coolant Drain Tank Loop 2A.
RC-113 RC-134 Reactor Coolant Drain Tank Loop 28 RC-112 RC-135 Reactor Coolant Drain Tank
.Locp 28' SI-212 SI-308 LPSI Drain to Reac. Coolant Drain Tank i
Loop'1 RC-128 RC-122 Reactor Coolant Drain Tank Loop 1 RC-163 RC-162 Reactor Coolant Drain Tank c
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1 TABLE I VALVE PAIRS D.
Samolina System Pressure Isolation Valves Penetration M-45 First Isolation Second Isolation Pathway l
HCV-2504A HCV-2504B Primary Sampling E.
CVCS (Chemical and Volume Control System) Pressure Isolation Valves 3
First Isolation Second Isolation Pathway CH-377 CH-378 To Vent CH-353 VD-609 To Containment Sump 1
CH-353 VD-610 To Containment Sump CH-388 VD-609 To Containment Sump j
CH-388 VD-610 To Containment Sump F.
Reactor Coolant Pumns Pressurf Isolatioq Valves First Isolation Second Isolation Pathway RC-3A RC-379 RC-383 To Reactor Coolant Drain Tank RC-3B RC-380 RC-384 To Reactor Coolant Drain Tank RC-3C RC-381 RC-385 To Reactor Coolant Drain Tank RC-3D RC-382 RC-386 To Reactor Coolant Drain Tank G.
RCGVS (Reactor Coolant Gas Vent System) Pressure Isolation Valves First Isolation Second Isolation Pathway HCV-176 HCV-180 Reactor Head to Quench Tank HCV-177 HCV-180 Reactor Head to Quench Tank HCV-176 HCV-181 Reactor Head to Vent HCV-177 HCV-181 Reactor Head to Vent HCV-176 HCV-178 Reactor Head to Pressurizer, PORV's, Sampling HCV-177 HCV-178 Reactor Head to Pressurizer, PORV's, i
Sampling l
l' HCV-176 HCV-179 Reactor Head to Pressurizer, PORV's, Sampling HCV-177 HCV-179 Reactor Head to Pressurizer, PORV's, Sampling w-
TABLE-II LEAKAGE TESTS A.
Safety In.iection Pressure Isolation Valves Valve Igit limit Freauency SI-194 ST-CV-2 Leakage Limit 1 5 gpm Each refueling outage or-l Per Tech. Spec.
cold shutdown longer than 2.1.1(12) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if not tested within the previous 9 months.
SI-195 ST-CV-1 Leakage Limit s 5 gpm Each refueling outage or Per Tech. Spec.
cold shutdown longer than 2.1.1(12) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if not tested
)
within the previous 9 months.
SI-196 Note'l i
SI-197 ST-CV-2 Leakage Limit-s 5 gpm Each refueling outage or Per Tech. Spec.
cold shutdown longer _than 2.1.1(12) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if not tested within the previous 9 months.
SI-198 ST-CV-1 Leakage Limit 5 5 gpm Each refueling outage or Per Tech. Spec.
cold' shutdown longer than j
2.1.1(12) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if not. tested within the previous 9 months.
i SI-199 Note 1 SI-200 ST-CV-2 Leakage Limit 1 5 gpm Each refueling outage or Per Tech. Spec.
cold shutdown longer than i
2.1.1(12) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if not tested within the previous 9-months.
SI-201 ST-CV-1 Leakage Limit s 5 gpm Each refueling outage or Per Tech. Spec.
cold shutdown longer than 2.1.1(12) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if not tested within the previous 9 months.
SI-202 Note 1 1
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TABLE II LEAKAGE TESTS
' A.-
Safety Iniection' Pressure Isolation Valves (Continued)
Valve 19.11 Limit Freauency i
SI-203 ST-CV-2--
Leakage Limit s 5 gpm Each refueling outage or Per Tech. Spec.
cold shutdown longer than 2.1.1(12) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if not tested within the previous 9 months.
j SI-204 ST-CV-1 Leakage Limit s 5 gpm Each refueling outage or Per Tech. Spec.
cold shutdown longer.than-2.1.1(12) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if not tested within the previous 9 months.
SI-205~
Note 1
'SI-207 Note'2
.SI-208
~ Note'3 SI-211 Note 2 SI-212 Note 3 SI-215-Note 2-SI-216 Note 3-SI-219 Note 2
'SI-220 Note 3 SI-366 Note 4 L
SI-367 Note 4 SI-368 Note 4 SI-369 Note 4 PCV-2909 Note 5 PCV-2929 Note 5 i
PCV-2949 Note 5 PCV-2969 Note 5 j
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TABLE II 6
LEAKAGE TESTS 8.
' Shutdown Coolina Pressure Isolation Valves Valves Int Limit Freauency HCV-347/ ST-CONT-7 Test to pressurize containment to 3 times HCV-348 ST-CONT-3 60 psig Leak Rate Limit < 0.75%
in 10 weight per day years l
C.
hne_ Disposal Pressure Isolation Valves Valves Test limit Freauency RC-112/
ST-RLT-3~
Change in RCS Inventory:
Daily q
RC-135 Limit:
1 0.3 gpm unknown leakage s 10 gpm total leakage RC-113/
ST-RLT-3 Change in RCS Inventory:
Daily RC-134 Limit:
$ 0.3 gpm unknown leakage 1 10 gpm total leakage RC-123/
ST-RLT-3 Change in RCS Inventory:
Daily RC-130 Limit:
1 0.3 gpm unknown leakage j
s 10 gpm total leakage RC-124/
ST-RLT-3 Change in RCS Inventory:
Daily RC-132 Limit:
1 0.3 gpm unknown leakage a
s 10'gpm. total ' leakage j
RC-128/
ST-RLT-3 Change in RCS Inventory:
Daily
'RC-122 Limit:
s 0.3 gpm unknown leakage
$ 10 gpm total leakage RC-163/
ST-RLT-3 Change in RCS Inventory:
Daily RC-162 Limit:
5 0.3 gpm unknown leakage 1 10 gpm total leakage SI-216/
ST-RLT-3 Change in RCS Inventory:
Daily SI-307 Limit:
s 0.3 gpm unknown leakage 1 10 gpm total leakage SI-212/
ST-RLT-3 Change in RCS Inventory:
Daily SI-308 Limit:
$ 0.3 gpm unknown leakage s 10 gpm total leakage D.
Samolina System Pressure Isolation Valves Valve Tgg Freauency HCV-2504A/B ST-CONT-3 Leakage Limit:
Refueling 2000 sccm at Outage 60 psig O
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l TABLE II.
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LEAKAGE TESTS a;
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CVCS (Chemical & Volume Control System) Pressure Isolation Valves a
L Valves M
Limit Freauency l
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CH-377/
- Change-in RCS-Inventory:
Daily l
CH-378-Limit:-
1 0.3 gpm unknown leakage-110 gpm total leakage CH-353/
ST-RLT-3 Change in RCS Inventory:
' Daily 1
VD-609-'
Limit:
1 0.3 gpm unknown leakage j
s 10 gpm total leakage W
CH-353/.
ST-RLT-3 Change in RCS Inventory:
Daily l
-VD-610 Limit:
s 0.3 gpm unknown leakage 3
$ 10 gpm total leakage l
CH-388/
ST-RLT-3 Change.in RCS Inventory:
Daily l
VD-609 Limit:
1 0.3 gpm unknown leakage l
$ 10 gpm total leakage i
CH-388/-.ST-RLT-3 Change in RCS Inventory:
Daily
~VD-610 Limit:
s 0.3 gpm unknown leakage s 10-gpm total leakage i
F.
. Reactor Coolant Pumos Pressure Isql3 tion Valves Valves ~
M Limit Freauency RC-379/
ST-RLT-3 Change in RCS Inventory:
Daily U
RC-383 Limit:
1 0.3 gpm unknown leakage
$ 10 gpm total leakage.
RC-380/
ST-RLT-3 Change in RCS Inventory:
Daily l
RC-384' Limit:
s 0,.3 gpm unknown leakage 1 10 gpm total leakage j
RC-381/
ST-RLT-3 Change in RCS Inventory:
Daily RC-385 Limit:
1 0.3 gpm unknown leakage s 10 gpm total leakage RC-382/
ST-RLT-3 Change in RCS Inventory:
Daily RC-386 Limit:
s 0.3 gpm unknown leakage s 10 gpm total leakage i
G.
ECGVS (Reactor Coolant Gas Vent System) Pressure Isolation Valves j
Valves M
Limit freauency HCV-176/ ST-RLT-3 Change in RCS Inventory:
Daily HCV-180:
Limit:
s 0.3 gpm unknown leakage 1 10 gpm total leakage C1
I TABLE II LEAKAGE TESTS f'-
G.
RCGVS (Reactor Coolant Gas Vent System) Pressure Isolation Valves (Continued)
Valves Igit Limit Freauency l
L HCV-177/ ST-RLT-3 Change in RCS Inventory:
HCV-180 Limit:
1 0.3 gpm unknown leakage Daily 1 10 gpm total leakage HCV-176/ ST-RLT-3 Change.in RCS Inventory:
Daily HCV-181 Limit:
10.3 gpm unknown. leakage l
110 gpm total leakage HCV-177/ ST-RLT-3 Change in RCS Inventory:
Daily HCV-181 Limit:
s 0.3 gpm unknown leakage 1 10 gpm total leakage HCV-176/ ST-RLT-3 Change in RCS Inventory:
Daily HCV-178 Limit:
's 0.3 gpm unknown leakage s 10 gpm total leakage HCV-177/.ST-RLT-3 Change in RCS Inventory:
Daily l
HCV-178' Limit:
10.3 gpm unknown leakage i
110 gpm total leakage q
J HCV-176/ ST-RLT-3 Change in RCS Inventory:
Daily I
HCV-179 Limit:
1 0.3 gpm unknown leakage i
110 gpm total leakage
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HCV-177/ ST-RLT-3 Change in RCS Inventory:
Daily l
HCV-179 Limit:
$ 0.3 gpm unknown leakage J
s 10 gpm total leakage l
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l NOTES TO TABLE II l
NOTE 1:
SI-196, 199, 202 and 205 are check valves in 2500 psi: design lines.
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'For this reason they are not leak tested.
Reference:
Franklin i
Research Institute Technical Evaluation Report (NRC-03-79-118).
NOTE 2:
SI-207, 211, 215 and 219, if leaking, would gradually fill the SI tanks, which are alarmed with LO/LO and HIGH/HIGH alarms. This, to-gether with the-fact that the SI tanks relieve in containment, as-sures sufficient protection against accidental-releases due to leak-age through these valves.
Reference:
OPPD submittal LIC-83-285, dated November 15, 1983.
1 NOTE 3:
SI-208, 212, 216 and 220 are required by Technical Specification i
2.1.1(12) and Table 2-9 to have maximum allowable leakage of s 5 l
gpm. Any leakage past these valves will be detected by ST-RLT-3 as unknown leakage.
Technical Specification 2.1.4's limit on unknown leakage is 1 gpm. The current administrative limit on unknown leakage is 0.3'gpm.
Reference:
OPPD submittal LIC-84-196, dated June 19, 1984.
I NOTE 4:
No leak testing is currently performed on these valves.
NOTE 5:
PCV-2909, 2929, 2949 and 2969 are located downstream of the Safety Injection Leakage Coolers.
If leakage through,the check valves from the reactor coolant system causes the pressure to increase to a preset value, the valves open and allow leakage to drain to the l
radioactive waste treatment system or the chemical and volume control
(
system.
If these valves were leaking, it would be detected by a drop in safety -injection tank level, which would be alarmed as noted previously.
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CLARIFICATIONS TO RESPONSE' According to the' definition of Reactor Coolant' Pressure Boundary, per 10 CFR 50.2, all. containment isolation valves associated with connected systems can perform a pressure isolating function duringLpostulated accident conditions, but they do not normally constitute a pressure isolation boundary.. Also included in the defini-
' tion are safety and relief valves on reactor coolant and associated systems.
Per the scope of this. Generic' Letter, OPPD has addressed pairs ~of. pressure isola-tion valves within the Reactor Coolant Pressure Boundary which separate the high.
R pressure reactor coolant system from a low pressure ~ system and which are both closed during normal operation. 'Therefore, not all containment-isolation valves are listed.: Safety and relief valves are also not. listed.
Single isolation -
n-valves are also not included in 'the. lists.
For Penetration M-16, valves.HCV-348 and SI-375 also formia pressure isolation pair,:but SI-375 is locked closed and is not a normal flow path. - Attached to Reactor Coolant Loop 1,. valves RC-128 'and RC-129 are ~ both normally closed, but RC-129. leads to level indicator LI-199. c There is no flow through RC-129.
In the unlikely-event of leakage passing. through SI-375 or RC-129, it would be detected.
,using ST-RLT-3.
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f EXPLANATION-0F SURVEILLANCE TESTS'.
m ST-CV-1:
' Leak Test of HPSI System Secondary Check Valves I
Purpose:
-To detect and quantify leakage past the primary coolant -
's
. system secondary check.' valves.
Reference:
l Technical Specification-2.1.1(12) and Table. 2-9.
j ST-CV-2:
- Leak: Test of LPSI System Secondary Check Valves
Purpose:
- To detect and quantify leakage past'LPSI check valves.-
Reference:
Technical Specification 2.1.1(12) and Table 2-9.
ST-RLT-3:
Reactor Coolant System Leak Rate Test-
Purpose:
'To. verify the leak tight performance of the Reactor Cool-ant System boundary and to' determine if leakage is-within the. limits specified by the Technical Specification Sec-tions 2.1.1(12), 2.1.4 and Table.3-5, Item 8.
ST-CONT-3:
Containment Isolation. Valve Leakage Rate Test - Type C
Purpose:
- To measure containment. isolation. valve leakage by loca'i pressurization with air or nitrogen at a pressure of 60 psig.
ST-CONT-7:
Contairment Leak Rate Test
Purpose:
To measure ~ containment building leak rate at 60 psig and verify that the measured leak rate is below the allowable test leakage _of 0.75 L or 0.75% by weight per day.
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E-23866-210-11(%.
E-23866-210-120,sh'eet 1..
Cheinical & Vo10ce' Control System, Sheet I r
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E-23866-210-120' Sheet 2 '-
Chemical & Volume Control System, Sheet.2 '
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E-23866-210-130.Sneet l' L
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SafetyJnjection Containment Spray System, Sheet 1 p.<
g-s SafetyInjectionContainmentSpraySy.<tr+ Sheet _2 E-23866-210-130 Sheet-2 q.
D-23866-210-111
- Reactor Coolant Pump ~
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D-4078,
Reactor. Coolant Gas Vent' System
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11405-M45' Primary Plant Sampling System
.11405-M-6' Waste Disposal System, Sheet 1 1
11405,-H 7' Waste Disposai Syste:n, Sheet 2 -
jl405-M-98.
Waste Disposal System,- Sheet 5 i
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