ML20133B077
| ML20133B077 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/20/1985 |
| From: | Jens W DETROIT EDISON CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| RC-LG-85-0004, RC-LG-85-4, NUDOCS 8510030010 | |
| Download: ML20133B077 (25) | |
Text
ce Nuclear Operatms Detroit.
-6400 North Dme Hghway Mh9m 48166 Nuclear IXW September 20, 1985 operations.
RC-LG-85-0004 Mr.
B.
J. Youngblood Director of Nuclear Reactor Regulation Licensing Branch No. 1 Division of Licensing U.
S.
Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Youngblood:
References:
(1)
Fermi 2 NRC Docket No. 50-341 NRC Operating License No. NPF-43 (2)
Detroit Edison letter to NRC " Inservice Testing of Pumps and Valves", EF2-65368, dated October 4, 1983 (3)
Detroit Edison letter to NRC, " Inservice Testing of Pumps and Valves", EF2-72769, dated September 5, 1984 (4). Detroit Edison letter to NRC, " Inservice Testing Program Clarification", EF2-72004, dated November 21, 1984
Subject:
Revisions to Inservice Testing Program for Pumna and Valven Revisions to the Fermi 2 Inservice Testing Program for pumps and valves are provided in Attachments 1 and 2 in accordance with 50.55a(g)(5)(iii).
These revisions are to be incorporated into Revision 2 of the IST Program (Reference 2) and. complement similar program revisions previously submitted via References 3 and 4.
The enclosed Program revisions are being implemented to support the Fermi 2 startup program.
8510030010 850920 i
PDR ADOCK 05000341
\\
p PDR
) NO
Mr.
B.
J. Youngb lo od September 20, 1985 RC-LG-85-0004 Page 2 Please direct any questions to Mr.
R.
L. Woolley at (313) 586-4211.
Sincerely, w.
-l k cc:
(all with attachment)
Mr. P.M.
Byron Mr.
S.
G. DuPont Mr.
J. Page Mr.
M.
David Lynch Mr.
G.
C.
Wright USNRC Document Control Desk Washington, D.C. 20555
Mr.
B.
J. Youngblood September 20, 1985 RC-LG-85-0004 Page 3 bec:
F.
E.
Agosti L.
P.
Bregni W.
F.
Colbert J.
E.
Conen*
- 0. K.
Earle J.
H.
Flynn E.
P.
Griffing W.
R.
Holland W.
H.
Jens R.
S.
Lenart*
S. :H. Noetzel G.
R.
Overbeck A. Papadopoulos T.
D.
Phillips T.
Randazzo B.
J.
Sheffel*
L.
J.
Simpkin G.
M.
Trahey A.
E.
Wegele R.
L. Woolley Approval Contro1*
R.
L.
Woolley (Bethesda Office)
Secretary's Office (2412 WCB)
NRR Chron File NOC Satellite Service Center Licensing File - ISI Pump and Valve *
- with attachment
ATTACHMENT 1:
SUMMARY
OF PROPOSED PROGRAM CHANGES
Mr.
B.
J.
Youngblood September 20, 1985 RC-LC-85-0004 Page 1 of 3
SUMMARY
OF PROPOSED CHANGES 1.
Deletion of Valven E11-1073 and E11-F078 Valve Ell-F073'is a Category B valve which is normally c lo s e d /k'e y-lo c k ed closed on the cross-tie line between the RHR Service Water System and the RHR System.
Ell-F073 is not required to change position to accomplish its safety function.. Therefore, Ell-F073 is a passive valve. Ac c o rd ing to ASME Section XI.
Table IWV-3700-1, no testing is required for Category B passive valves.
Therefore, Ell-F073 has been deleted from the IST Program.
Valve Ell-F078 was originally in the IST boundary for the RHR System and had a safety function to c lose.
The ISI boundary has been extended to Ell-F075.
Consequently -Ell-F078 no longer has a safety function andLdoes not require testing and has been deleted from the IST Program.
Valve Ell-F075 is a Category B, passive valve (similar to Ell-F073) and does not require testing according to Table IWV-3700-1.
2.
Core Snrav Two Pumn Testing Relief Request PR-6 is being submitted to allow two pump testing in each Core Spray division in lieu of single pump testing.
PQ-5 is provided in Attachment 2.
3.
RHR Service Waterj g 7-gn Testing Relief Request PR-7 is being submitted to allow two pump t e's t in g in each RHR Service Water Division in lieu of single pump testing.
PR-7 is provided in.
4.
Core Snrav Minimum Flow Check Valven Relief Request VR-45 is being submitted to allow the disassembly of a typical core spray minimum flow check valve in. lieu of exercise tests.
VR-45 is provided in.
Mr.
B.
J.
Youngb lo od l
September 20. 1985 RC-LG-85-0004 1
Page 2.of 3 5.
RHR Pumns During preoperational testing, the vibration velocity measurements for the RHR pumps were high relative to the vibration velocity acceptance ranges provided in Relief Request PR-1, with three of the four pumps falling into the alert range.
Relief Request PR-8 provides the justification for departing from the current acceptance criteria, provided in Relief Request PR-1, for the RHR pumps.
Relief Request PR-8 further provides the proposed acceptance criteria to be used.
6.-
NRC Onen Item 341/84-46-02 NRC.Open Item 341/84-46-02 is identified in NRC' Inspection Report 50-341/84-46 and states that ~ Detroit Edison will comply with Section XI, Sub-articles IWV-3426 and 3427.
In response to this open item.
Relief Request VR-ll, VR-24, VR-27 and VR-31 will be deleted and maximum allowed leakages assigned to individual valves.
There are cases where Category A valves cannot be individually tested.
These cases are addressed in Items 7, 8, 10 and 11.
7.
Air Lemkage Test For Category A Valves Relief Request VR-46 is being submitted to allow air leakage testing of containment isolation valve groups instead of testing individual ~ valves.
VR-46 is provided in Attachment 2.
8.
Water Lemkage Tests For Categorv_A Valves Relief Request VR-47 is being submitted to allow water testing'of containment isolation valve groups instead of testing valves individually.
VR-47 is provided in.
9.
Emergenev E n_ u i n m e n t Cooling Water Check Valves Relief Request VR-48 is being submitted to allow the disassembly of a typical Emergency Equipment Cooling' Water back flow check valve in lieu of exercise tests.. VR-48 is provided in Attachment 2.
4
Mr. B.
J. Youngblood September 20. 1985 RC-LG-85-0004 Page 3 of.3 10.
High Pressure Lankage Testa For Category A - PIVs 4
L
-Relief Request VR-49 is being submitted to allow high pressure leakage testing of pressure isolation valves Ell-F009 andE11-F608 together instead of separately.
VR-49 is provided in Attachment 2.
11.
Evpana Lankage Valven Relief Request VR-50 is being submitted to allow air leakage testingoof bypass leakage valve groups instead of testing individual valves.
VR-50 is provided in 12.
Solenoid valve Operating Relief Request VR-51 is'being submitted.to revise the manner and frequency of verifying solenoid valve operation in -the diesel generator system.
VR-51 is provided 'in Attachment 2.
~
13.
Excena Flow Check Valves Currently, excess flow check valves are classified as Category A valves subject to an AT-3 test.
The description of the AT-3 test states that the excess flow check valves will be tested-in accordance with Technical Specification paragraph 4.6.3.4.
Paragraph an operability test and identifies no 4.6.3.4 requires leakage requirements.
Because there are no leakage requirements for excess flow check valves, Detroit
~
Edison proposes changing the Category from'A to C.
i~
+
s t
~,,,,.. -..
,,,.m,_
.y
-.,_n.m._.,,,__m.,,,
.y
.~.._.m, m...
..m_,
m.,
' ATTACHMENT 2:
PROPOSED RELIEF REQUESTS
Mr.
B.
J. Youngb lo od September 20, 1985 RC-LG-84-0004 Page 1 of 17 Relief Request No. PR-6 PUMP (s):
Core Spray PUMP NO. (n):
E2101C001A, E21010001B, E21010001C, E21010001D CLASS:
2 FUNCTION:
Provide emergency core cooling SECTION XI REOUIREMENTS:
Articles IWP-1500 and IWP-3000 indicate that a set of basic reference parameters must be established for each pump.
BASIS FOR RELIEF:
Each~ core spray division is designed to have two pumps operating in parallel in accordance with Technical Specification Paragraph 3.5.1.a.
If one pump is determined to be inoperable, then the division is dec'lared inoperable.
Due to this two pump design, the system configuration does not allow for single pump testing.
The throttle valves (E21-F0'15A and B)
'o n the test lines-for each core spray division tend to close due to reduced flow during one pump operation.
Consequently, both pumps in each division must be running during performance operability testing.
Detroit Edison proposes measuring flow rate and differential pressure while both pumps in each division are operating.
Also, acceptance criteria have been developed which are more restrictive for' flow rate and differential pressure than the criteria given in Table IWP-3100-2.
The reduced ranges compensate for the loss in sensitivity from the eingle pump test to the two pumps in parallel test.
The reduced ranges are based on an evaluation of each pump curve.
Curve 1 in Figure PR-6 represents the pump curve (differential pressure, P.
versus flow rate, Q) for a normally operating pump.
Curve 2 represents the performance of a similar pump but at a degraded state (0.9 P versus Q).
For a given differential pressure, the flow rate from Curve 1 was added to the corresponding flow rate from Curve.2.
This summation produces Curve 3 which reflects the parallel operation of two pumps, one operating normally (Curve 1) and one operating in a degraded state (Curve 2).
Comparing Curve 3 to Curve 4, which reflects acceptance criteria is two normally operating pumps, a new
Mr.
B.
J.
Youngblood September 20, 1985 RC-LG-85-0004 Page 2 of 17 Relief Request No. PR-6 Cont.
determined.
Because of instrument error limitations, the upper alert and required action ranges given in Tab le IWP 3100-2 will be retained.
ALTERNATE TESTING:
Flow rate will be set to a reference value and dif ferential pressure will be measured while both
-pumps in each division are operating.
The following acceptance criteria will be applied:
Acceptable Range Alert Range Required Action Range Low Values High Values Low Values High Values 0.96 to 1.02 Pr 0.94 to 1.02 to 0.94 Pr 1.03 Pr 0.96 Pr 1.03 Pr
m 2 x ex.
E 4, r e ?
P ma
~
w e 'P 8."
0 2 $ E.
mgg o m-<
""R.8o 4wer m-mg a
800 X Curve I 2(Curve 4)
N l
N N
t 700 g
=
N i
N N
N
- 625 N
s, Exarple Point Only I
s 600.
'N N
7 N
N
-=
I 4
l l
g z
i 5
N 2
i s.
500 x
e 3
O Curve 2 N
t u
Curve 1 Cur.Yes I+2
\\
=(Lurve3)
\\
zo I
110 0- -
t 2L i
a a
e j
1400 806 E-3J0 525 600 Flow Rate (GPM)
Figure PR-6 Two Pump Acceptance Criteria
{
i i
t
4 Mr.
B.
J. Youngblood September ~20, 1985 RC-LG-85-0004
. Page 4 of 17 Ralief Ranumat No. PR-7 PUMPfa):
RHR Service Water PUMP NO. (m):
~E1151C001A, E1151C001B, Ell 51C001C, E1151C001D GLA11:
3 FUNCTION:- Provide cooling water to the RHR heat exchangers.
SECTION XI REOUIREMENTS: -Articles IWP-1500 and IWP-3000 indicate that a set of basic reference parameters must be established for each pump.
i l
BASIS FOR RELIEF:
Each RHR service water division is required to have two pumps operating in parallel in
' ~
accordance with Technical Specification Paragraph 3.7.1.1.
LIf one pump is' determined to'be inoperable, then the division is declared inoperable.
Due'to this two-pump 4
design, the system configuration does not' allow for. single pump testing.
The throttle valves (E11-F068A and B) are sized for two pump-operation with flows greater than 9000 GPM.
During single pump operation, the pumps experience runout at approximately 6000 GPM.
To keep flow'in the stable range (approximacely 5000-GPM) the valves must throttle from 3 to 8 percent open.- This reduced flow causes valve vibration and control instabilities.
Consequently.both pumps in each division must be running g
during performance operability testing.
i
. Detroit Edison proposes measuring flow rate and differential pressure while both pumps in each division are-j operating.
The acceptance criteria described in Relief Request.PR-6 will be applied to the RHR' service water pumps.
ALTERNATE TESTING:
Flow rate will be set to.a reference value'and dif ferential pressure will be measured'while both pumps in each division are operating.
The following acceptance criteria will be applied:
Alert Ranum Ema_uired Action Acceptable Range Low Values High Values Low" Values High Values 0.96 to 1.02 Pr 0.94.to 1.02 to 0.94 Pr 1.03 Pr 0.96 Pr 1.03 Pr j
l^
i 4
4
.,m,<-
..,.,--..v
.----g..-
,.r-we,,.
.,-,,,~,.,,..-c,,i.,,.r-.,_--e.,.-v.-,-e,m-.-m.,,g-4%--....y.-e,.,
w Mr._B.
J. Youngblood September 20, 1985 RC-LG-85-0004 Page 5 of 17 Relief Recuent No. PR-1 EEEE: RHR Pumps
' PUMP NO.:
E11020002A, E11020002B, E1102C002C, and E11020002D CLASS:
2 FUNCTION:
Provide low pressure coolant injection SECTION II REOUIREMENTS:
Vibration amplitude displacement shall be measured quarterly during inservice testing (Table IWP-3100-1 and IWP-3400 (a) ).
BASIS FOR RELIEF:
During preoperational testing, the vibration velocity measurements for the RHR pumps were high
(.19 to.27 ips) relative to the vibration velocity ranges given in Relief Request PR-1.
Three of the four pumps fell into the alert range.
The preoperational vibration velocity measurements were part.of a series of vibration tests which included vi.b ra t ion amplitude.
The results of the tests ind ic a t e that the pumps are operating acceptably at the higher
~
vibration velocities.
Consequently, a new set of vibration velocity.anges were developed with the assistance of the vendor which recommended the measurement of overall velocity (filter out), overall amplitude (filter out) and running speed amplitude (filter in).
All three quantities will be measured at the pump bearing and compared to the ranges given below.
ALTERNATE TESTING:
Pump vibration overall velocity, overall amplitude and running speed amplitude measurements will be taken.- The evaluation of the readings will be as follows:
i r
. ~-.-.,- _
i e
Mr. B. J. Youngblood-September 20,-1985 I:C-LG-85-0004 ftta t
RELIEF REQUEST PR-8 CONT'D.
e Overall Velocity Acceptable Range: less than 2.0 Vr Alert Range: greater.than or equal to 2.0 Vr and less than or equal to 4.0 Vr Required Action Range: greater than 4.0 Vr Where Vr = reference vibration velocity in/sec.
Also, no vibration velocity can exceed a value of 1.0 in/sec.
Overall Amplitude The ranges given in Table IWP-3100-2 will be applied.
Running Speed Amplitude The ranges _given.in Table IWP-3100-2 will be applied.
Mr.
B.
J. Youngblood September 20.-1985 RC-LC-85-0004 Page 7 of 17' Relief Reauant No. VR-45 SYSTEM:
Core Spray COMPONENT:
E21-F038A (V8-2044)
E21-F038C (V8-2045)
E21 -F03 8B (V8-2041)
E21-F038D (V8-2040)
CATEGORY:
C FUNCTION:
These valves are designed to close to prevent backflow through core spray pumps that fail'to start, thus preventing loss of core spray inventory.
The valves must also open during pump startup to meet minimum flow requirements of the pumps.
TEST REQUIREMENTS:
Exercise check valve every three months (CT-1).
BASIS FOR RELIEF:- As described in Relief Request PR-6, both core spray pumps in each division must be operating during surveillance testing.
Therefore, detection of flow through the minimum flow line will only show that one out of-two valves is open.
Also, the ability to verify that the check valves close upon reversal of flow is lost during two pump testing.
In' lieu of the Code required exercise test, valve operability will be demonstrated by disassembling the valve and verifying that the-valve disk swings freely from and to the seat.
ALTERNATE TESTING:
Valve disassembly and inspection will occursat every refueling outage until sufficient data can be accumulated to adequately monitor valve degradation.
The maximum inspection intervals will be determined based on an evaluation of that data.
Mr.
B.,J.
Youngblood September 20, 1985 RC-LG-85-0004 Page 8 of 17 Relief Reauent No. VR-46 SYSTEM:
Systems Penetrating Primary Containment COMPONENT:
Valves subject to ASME Section II, Category A Containment Isolation Air Leakage Tests (AT-1 and AT-9).
See Table VR-46 for list of valves.
CATEGORY:
A and A/C FUNCTION:
The subject valves perform a containment isolation function as defined in 10CFR50, Appendix A, criteria 55 and 56.
TEST REOUIREMENT:
Measure valve seat leakage and compare the measured leakage to a specific maximum leakage for each valve (IWV-3426).
BASIS FOR RELIEF:
Due to system configuration, the valves listed in Table VR-46 cannot be individually leak tested.
Table VR-46 gives the primary containment penetration corresponding to the containment isolation valves, the containment isolation valves tested together, the valve diameters and the maximum allowable leakage based on the leakage of 0.173 SCFH sum'of the valve diameters times a per inch of valve diameter.
The 0.173 SCFH per diameter inch is determined by dividing 0.6 La (178 SCFH) by the sum of the air tested containment isolation valve diameters (1029 in.).
Technical Specification paragraph 3.6.1.2.a defines La.
ALTERNATE TESTING:
The containment isolation valves listed in Table VR-46 will be leak tested according to the valve groups given in Table VR-46.
The test leakage will be compared to'the maximum leakage assigned to each group.
The test Icakage will also be trended ac c o rd ing to the requirements of IWV-3427.
If the test leakage exceeds the criteria given in IWV-3427, valves in the affected group will be subject to the corrective actions of IWV-3427 on a valve by valve basis.
The valve most likely to be the lenker will be repaired first and the group retested.
If the test leakage is within the criteria, no further testing will be performed.
E ff Request & __VR-46 Mr. B. J. Youngblood September 20, 1985 Table VR-46 RC-LG-85-0004
(
fa Maximum Leakage Rates o 17 for CIV Groups Valve Maxicua Penetration Valve Size Leaka;e
_Ruober Lboher IIt0_
_ISCEIL X-7A B21-F022A (V17-2003) 26 B21-F028A (V17-2007) 26 B21-F434 (V5-2294) 1 25*
X-7B B21-F022B (V17-2001) 26 B21-F028B (V17-2005) 26 B21-F434 (V5-2294) 1 25*
X-7C B21-F022C (V17-2002) 26
~
B21-F028C (V17-2006) 26 B21-F434 (V5-2294) 1 25*
X-7D B21-F022D (V17-2004) 26 B21-F028D (V17-2008) 26 B21-F434 (V5-2294) 1 25*
(
X-9A B21-F076A (V12-2002) 20 E41-F006 (V8-2194) 14 5.88 X-9B B21-F0763 (V12-2001) 20 E51-F013 (VS-2228) 6 G33-F120 (V8-4615) 4 5.19 X-11 E41-F003 (V17-2021) 10 E41-F600 (V17-2088) 1 1.90 X-12 E11-F009 (V8-2091) 20 E11-F603 (V8-3407) 20 E11-F408 (V8-3874) 0.75 7.05 X-13A E11-F050B (V8-2164) 24 l
E11-F610B (V13-7688) 1 4.33 X-13B E22-F050A (V8-2163) 24 E11-F610A (V13-7687) 1 4.33 X-15 T48-F603A (V4-2144) 4 T48-F605A (V4-2154) 4 1.38 X-22 T49-F601 (V4-2080) 1.5 T49-F465 (V4-2079) 1.5 i
T49-F007 (V4-2172) 1.5 0.78
- All four main steam lines shall have a total leakage less than 100 SCFH when tested at 25.0 PSIG. Per Technical Specification 3.6.1.2.c.
t
Relief _Be. quest _No. VR-46 Mr. B. J. Youngblood Table VR-46 (Continued)
September 20, 1985 RC-LG-85-0004-Maximum Leakage Rates for CIV Groups i
Page 10 of 17 Valve
!!axiatra
. Penetration Valve Size Leakage
_ Nunbar-1] umber 1110 _
_JS.Cf1L X-25 T46-F602 (VR3-3024) 24 T46-F402 (VR3-3023) 24 T46-F411 (VR3-3026) 6 9.34 X-26 T48-F601 (VR3-3011) 24 T48-F407 (VR3-3012) 24 T48-F408 (V4-2060) 10 10.03 X-27a T50-F401B (V5-2159) 1 X-27c T50-F403B (V5-2161) 1 X-27d T50-F404B (V5-2162) 1 X-27e T50-F405B (V5-2163) 1 X-27f T50-F406B (VS-2164) 1 0.86 X-2Tb T50-F402B (V5-2160) 1 P34-F404A (V13-7374) 0.75 0.30 I
T50-F4023 (V5-2160) 1 X-27b P34-F403A (V13-7364) 0.75 0.30 X-31B T48-F453 (VR3-2823) 1 T48-F454 (VR3-2824) 1 T48-F455 (VR3-2824) 1 0.52 X-36 T49-F602 (V4-2188) 1.5 T49-F468 (V4-2187) 1.5 T49-F016 (V8-4140) 1.5 0.78 X-37 C11-F010 (V8-2073) 1 X-38 C11-F011 (V8-2086) 2 0.52 X-37 C11-F180~ (V8-3876) 1 X-38 C11-F181 (V8-3877) 2 0.52 X-44 T48-F6033 (V4-2143) 4 T48-F605B (V4-2153) 4 1.38 X-48a T50-F401A (V5-2151) 1 X-48b T50-F402A (V5-2152) 1 X-4Bc T50-F403A (V5-2153) 1 X-48d T50-F404A (VS-2154) 1 X-48e T50-F405A (V5-2155) 1 0.S5
(
' Mr. B. J. Youngblood Efliff lequestJp, VR-46 September 20, 1985 RC-LG-85-0004 Table VR-46 (Concluded)
-( -
Page 11 of 17 Maxitum Leakage Rates for CIV Groups i
Valve Maxicua Penetration Valve Size Leakage
._Jmter EuDbfr (IN).
-(SCFH_
X-48f T50-F406A (V5-2156) 1 P34-F403B (V13-7365)
.75 0.30 X-48f T50-F406A (V5-2156) 1 P34-F404B (V13-7375)
.75 0.30 X-205A T23-F450B (V21-2014) 20 T23-F410 (V21-2016) 20 6.92 X-205B T23-F450A (V21-2013) 20 T23-F409 (V21-2015) 20 6.92 X-205C T48-F404 (VR3-3013) 20 T48-F405 (VR3-3014) 20 T48-F409 (V4-2061) 6 7.96
(.
X-205D T46-F400 (VR3-3015) 20 T46-F401 (VR3-3016) 20 T46-F412 (VR3-3019) 6 T4S-F410 (V4-2063) 6 9.00 X-205D T48-F456 (VR3-2826) 1 T48-F457 (VR3-2827) 1 T48-F458 (VR3-2828) 1 0.51 X-211A E11-F024B (V8-2136) 18 E11-F027B (V8-2158) 6 E11-F028B (V8-2156) 18 7.26 X-211B E11-F024A (V8-2135) 18 E11-F027A (V8-2157) 6 E11-F028A (V8-2155).
18 7.26 X-215-T48-F602A (V4-2142) 4 T48-F606A (V4-2156) 4 1.38 X-218 T48-F601A (V4-2140) 8 T48-F604A (V4-2148) 8 2.77 X-218 T48-F601B (V4-2139) 8
(
T48-F604B (V4-2149) 8 2.77 X-219 T48-F6023 (V4-2141) 4 T48-F606B (V4-2155) 4 1.38
Mr.
B.
J.LYoungbloed.
September 20, 1985 RC-LG-85-0004 Page 12 of 17 Relief Raouant No. VR-47 SYSTEM:
Systems Penetrating Primary Containment C OMP ONENT :
Valves subject to ASME Section II, Category A, Containment-Isolation Water Leakage Tests (AT-2).
See Table VR-47 for list of valves.
CATEGORY:
A FUNCTION:
The subject valves perform a containment isolation function as defined in 10 CFR 50, Appendix A, Criterion 57.
TEST REOUIREMENT:
Measure valve seat leakage and compare the measured leakage to a specific maximum leakage ~for each valve (IWV-3426).
BASIS FOR RELIEF:
Due to system configuration, the containment isolation valves (CIVs) listed in Table VR-47 cannot be individually leak-tested.
Tab le VR-47 gives the primary' containment penetration corresponding to the'
-containment isolation valves, the valve diameters and the maximum allowable leakage based on the leakage limits given in Technical Specification paragraph 3.6.1.2.e.
According to the technical specification, the leakage shall be. limited to one gym times the number of valves per penetration, not to exceed three gpm per penetration.
For the penetrations in Table VR-47, the maximum penetration limit is three gym (11355 ml/ min).
This limit is divided by the sum of the valve diameters for the penetration, and multiplied by the sum of the valves tested in a penetration group to produce the maximum leakage for that group.
i ALTERNATE TESTING:
The containment isolation valves listed in Table VR-47 will be leak tested according to the valve groups given in Table VR-47.
The test leakage will be
' compared'to the maximum leakage assigned to each group.
The test leakage will also be trended accor'ing to the d
requirements of IWV-3427.
If the test leakage exceeds the criteria given in IWV-3427, valves in the affected group will be subject to the corrective ac* ions of IWV-3427 on a valve by valve basis.
The valve most likely to be the leaker will be repaired first and the group retested.
If the test is within the criteria, no further testing will be performed.
'Mr. B. J. Youngblood Helief_Heauast_lb_YZ-E September 20, 1985 RC-LG-85-0004 Table VR-47
(
Page 13 of 17 liaximum Leakage Rates for CIV Groups
]
Maximum 11axicium Leakage Leakage All CIVs Valve Tested Tested Penetration Assigned to Size SID9Ie Together J iber EcDatrailsn_
UlD_ (ml/ min) g3 g X-227A E21-F0328 (V22-2004) 1 379 E21-F0313 (V8-2032) 3 1135 G51-F606 (V8-3850) 4 1514 G51-F607 (V8-3848) 4 1514 E41-F012 (V8-2196) 4 1514 E21-F011B (V22-2119) 2 E21-F0128 (V22-2017) 2 E21-F015B (V8-2034) 10 5299
- X-2273 E51-F019 (V8-2230) 2 1136 E21-F031A (V8-2031) 3 1703 E21-F032A (V22-2019) 1 569 E21-F011A (V22-2120) 2
(
E21-F012A (V22-2016) 2 7948
- E21-F015A (V8-2033) 10
- These valves tested together.
A 0
Mr.'B.
J. Youngb lood September 20, 1985 RC-LC-85-0004 Page 14 of 17 Ralle f Ranumat No. VR-48 S11 TEM:
Emergency Equipment Cooling Water COMPONENT:
P44-F051 (V8-2431)
P44-F1165 (V8-2332)
P44-F116A (V8-2432)
P44-F165 (V8-2428)
CATECORY:
C FUNCTION:
These valves are designed to close to prevent backflow in the Emergency' Equipment Cooling Water System.
TEST REOUIREMENT:
Exercise check valve every three months to the open position (CT-1).
BASIS FOR RELIEF:
The current system configuration does not allow for direct or indirect verification that the check valve disk moves from its seat to the open position upon initiation of flow.-
In lieu of the Code required exercise test, valve operability will be demonstrated by disassembling the valve and verifying that the valve disk swings freely from and to the seat.
ALTERNATE TESTING:
Valve disassembly and inspection will occur at every refueling outage until sufficient data can be accumulated to adequately monitor valve degradation.
The maximum inspection intervals will be determined based on an evaluation of that data.
I Mr.
B.
J. Youngblood September ~20, 1985 RC-LG-85-0004 Page 15 of 17 Relief Reaumat No. VR-49 SYSTEM:
Residual Heat Removal System COMPONENT:
E11-F00 9 ( V8-20 91), E11-F608 (V8-3407)
CATECORY:
A i
FUNCTION:
The subject valves isolate low pressure piping 3
l from the adjacent high pressure. piping.
TEST REOUIREMENT:
Measure valve seat leakage and compare the measured leakage to a specific maximum leakage for each valve (IWV-3426).
4 BASIS FOR RELIEF:
Due to system configuration, the above
. pressure isolation valves cannot be individually leak tested.
Both valves must be tested within the same test volume with pressure being applied in the accident direction for both valves.
According to Technical Specification paragraph 3.4.3.2.d.
the 1eakage shall be limited to.one gym (3785 ml/ min) at a reactor coolant pressure of 1040 1 10 psig from any reactor coolant' system pressure isolation valve.
ALTERNATE TESTING:
Pressure isolation valves E11-F009 and E11-F608 will be leak tested together.. The test leakage will be compared to a maximum leakage of one gpm (3785-ml/ min).
The test leakage will also be trended according to the requirements of IWV-3427.
}
If the test leakage exceeds the criteria:given.in IWV-3427, both valves will be subject to the corrective actions of IWV-3427.
The valve most likely to be the leaker will be i
repaired first and both valves retested.
If the test leakage is within one gpm, no further testing will be performed.
1 4
b 7
i i
i
~., -., --
Mr.
B.
J.
Youngb lo od September 20, 1985 RC-LG-85-0004 Page 16 of 17 Relief Request VR-50 SYSTEM:
High Pressure Coolant Injection COMPONENT:
E41-F003 (V17-2021)
E41-F006 (V8-2194)
E41-F600 (V17-2088)
CATECORY:
A FUNCTION:
The subject valves perform a bypass leakage isolation function.
TEST REOUIREMENT:
Measure valve seat leakage and compare the measured leakage for each valve (IWV-3426).
BASIS FOR RELIEF:
Due to system configuration, the above listed valves cannot be individually leak tested.
Bypass leakage valves E41-F003 and E41-F600 must be tested together, and bypass leakage valve E41-F006 must be tested with the non-bypass leakage valve B21-F076A.
Maximum allowable leakages have been assigned to the two i
groups of valves, based on the requirement that the summed leakage from all bypass leakage paths is less than 0.04 La.
(See the Fermi 2 Safety Evaluation Report, NUREG-0798, Supplement 2, pg. 6-1.)
ALTERNATE TESTING:
Bypass leakage valves E41-F003 and E41-F600 and bypass leakage valve E41-F006 and containment isolation valve B21-F076A will be leak tested as groups.
The test leakage will be compared to the maximum leakage assigned to each of the two groups.
.The leakage will also be trended according to the requirements of IWV-3427.
If the test leakage exceeds the criteria given in IWV-3427, valves in the affected group will be subject to the corrective actions of IWV-3427 on a valve by valve basis.
The valve most likely to be the lenker will be repaired first and the group retested.
If the test leakage is within the criteria, no further testing will be performed.
r v
'Mr.
B.
J.
Youngblood September 20, 1985 RC-LG-85-0004 Attachment Page 17 o f 17 l
Relief Requent VR-51 SYSTEM:
Diesel Generator COMPONENTS:
R30-FA04A R30-FA04B R30-FA04C R3 0 -FA04D R30-FA05A R30-FA05B R30-FA05C R30-FA05D CATEGORY:
B FUNCTION:
Normally closed valves which must open to supply air to the Air Start System of the Diesel Generator.
TEST REOUIREMENTS:
Per IWV-3413(b) exercise testing, verified by stroke time measurements, will be performed to confirm full stroke capability of each valve.
The stroke direction tested and timed will be based on the direction the valve disk must travel to fulfill its safety function.
The test frequency required is once every 92 days during power operation.
BASIS FOR RELIEF:
It is impractical to apply the requirements of IWV-3413(b) to valves with very short stroke times (i.e. 2 seconds).
Solenoid operated valves typically have full stroke times under one second.
For these short stroke time valves, variances of 50 percent or more can occur in the measured times for-reasons that are in no way related to valve performance; for example, operator reaction times.' In this specific case verifying that the' valve's stroke time satisfies system operating requirements is sufficient to evaluate valve performance.
To satisfy the test frequency requirement would require-additional diesel starts which would be detrimental to overall diesel operation and reliability.
ALTERNATE TESTING:
For the subject valves, a successful start of the diesel generator within the required Fermi 2 Technical Specification requirement of achieving speed and voltage level (Ref. Tech. Spec. Faragraph 4.8.1.1.2.a.4) within ten (10) seconds, shall be sufficient to demonstrate that the 3-way solenoid valves have opened in the required time.
The test frequency shall be once every 6 months.
i