ML17329A235
| ML17329A235 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/05/1991 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:0969U, AEP:NRC:969U, NUDOCS 9111120265 | |
| Download: ML17329A235 (65) | |
Text
ACA ELERATED D ATTRIBUTION DEMONS ATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9111120265 DOC.DATE: 91/11/05 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
(formerly Xndiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
Document Control Branch (Document Control Desk)
SUBJECT:
Forwards revs to Inservice Testing Program which resulted from review of valves not asssigned backflow checkinq safety function. Review performed in response to concerns raised during ESW Safety Sys Functional insp.
DISTRIBUTION CODE:
A047D COPIES RECEIVED LTR ENCL SIZE:
TITLE: OR Submittal:
Xnservice Inspection/Testing/Relief from ASME ode NOTES R
RECIPIENT ID CODE/NAME PD3-1 LA COLBURN,T.
INTERNAL: NRR/DET/ECMB 9H NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR/EIB EXTERNAL EG&G BROWNi B NRC PDR COPIES LTTR ENCL 1
0 2
2 1
1 1
1 1
0 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DET/EMEB 7E OC/LE~MILE 01 EG&G RANSOME i C NSIC COPIES LTTR ENCL 1
1 1
1 1
0 1
1 1
1 1
1 D
D R
D NOTE TO ALL"RIDS" RECIPIENTS:
D D
PLEASE HELP US TO REDUCE WASTE( CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPXES REQUIRED:
LTTR 15 ENCL 12
0 I
f a, t
'7
Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:0969U Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
DPR-58 and DPR-74 License Nos.
50-315 and 50-316 IST PROGRAM REVISION/CHECK VALVE REVERSE FLOW UPS. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555 Attn: T.
E. Murley November 5, 199l
Dear Dr. Murley:
References:
1)
Letter AEP:NRC:0969S, E.
E. Fitzpatrick to T.
E. Murley, "IST Program Revision/Check Valve Reverse Flow," dated April 9, 1991 2)
Letter AEP:NRC:1125H, M. P. Alexich to A. B. Davis, "Inspection Reports 50-315/90201 (DRS) and 50-316/90101 (DRS)," dated December 7,
1990 This letter transmits a revision to the In-service Testing Program for the Donald C.
Cook Nuclear Plant.
These changes result from our review of those valves that were not assigned a backflow checking safety function.
This review was performed in response to concerns raised during the Essential Service Water Safety System Functional Inspection (References 1 and 2).
The review was completed October 23,
- 1991, and additional check valves that have a
closed safety function were identified.
This letter transmits the results of the review.
A list of these additional valves and a summary of the IST valve program changes are contained in Attachment 1.
The revised pages to the IST valve program are contained in Attachment 2.
The additions to the IST program will be made during the first post-outage three-month interval following the 1992 refueling outages for both units.
This time is required to avoid diverting 9111120265 5'11105 gi' PDR ADOCK 05000315 P
l I
8
'tg
Dr. T.
E. Murley AEP:NRC:0969U resources required to plan and perform outage-related activities, and to allow time to revise the applicable procedures.
Additionally, eight check valves (four in each unit) have been identified as candidates for inclusion as valves having a closed safety function.
The closed position of these valves, which are listed in Attachment 1, is, however, difficult to test because of the system configuration and the absence of instrumentation.
For these valves, further evaluation is required.
This evaluation includes investigation of design alternatives and further development of test methodology and acceptance criteria.
Testing methods that are currently being considered for these valves included radiography, ultrasonic examination, and acoustic flow measurement.
The tests or examinations necessary to verify the closed position of these valves will be incorporated into the IST Valve Program prior to the 1993 refueling outages should this be necessary.
All of the valves listed in Attachment 1 are contained in the Check Valve Program developed in response to INPO SOER 86-03 (Check Valve Failure or Degradation).
As part of this program, these valves have been previously screened and reviewed for significant maintenance trends and potential misapplication (type, size, and installation).
The SOER 86-03 activities, in combination with the current IST testing requirements associated with these valves, provide a reasonable mechanism to detect check valve failures and prevent occurrence of a substantial safety hazard until the procedures are revised and closed position testing commences under the IST Valve Program.
This letter has been reviewed by the Plant Nuclear Safety Review Committee.
This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, E.
E. Fitz trick Vice President dfw Attachments
Dr. T.
E. Murley AEP:NRC:0969U cc:
D. H. Williams, Jr.
A. A. Blind - Bridgman J
~
R. Padgett G. Charnoff A. B. Davis
- Region III NFEM Section Chief NRC Resident Inspector
- Bridgman
ATTACHMENT 1 TO AEP'NRC:0969U
SUMMARY
OF IST VALVE PROGRAM CHANGES
Attachment 1 to AEP:NRC:0969U Page 1
The following check valves have been assigned a closed safety function:
1/2-5135A 1/2-CCW-176E*,W*
12-CCW-170 1/2-5144 1/2-CTS-127E,W 1/2-CTS-131E,W 1/2-RH-141 1/2-RH-142 1-5151B 1-DG-127A 1-DG-129A 1-DG-151A*
1-DG-153A 1-5151C 1-5151D 1-DF-108C*
1-DF-109C*
1-DF-114C*
1-DF-115C*
1-DG-127C 1-DG-129C 1-DG-151C 1-DG-153C~
12-5131 1-CS-415-1 1-CS-415-2 2-CS-415-3 2-CS-415-4 2-5151A 2,-DF-108A+
2-DF-109A*
2-DF-114A*
2-DF-115A*
2-5151B 2-DG-128A 2-DG-130A 2 - DG - 15 2A*
2-DG-154A 2-5151D 2-DG-128C 2-DG-130C 2-DG-152C 2-DG-154C
- These valves have either been inspected under the SOER 86-03 Program or will be inspected during 1992.
Attachment 1 to AEP:NRC:0969U Page 2
In adding a closed position safety function, it was necessary to revise a Code Relief and add two program notes.
The following list indicates the notes which have changed, and briefly summarizes the content of the change:
1 2-5144 Notes 3
4 and 5'evised to additionally indicate that the previously approved relief (disassembly and inspection at refueling frequency on a sampling basis) is considered to demonstrate the valve's ability to perform both the active open and active closed safety functions.
1-5151C and 2-5151A Note 3:
Added comment regarding testing of closed position safety function.
1 2-5151B D Note 5:
Added comment regarding testing of closed position safety function.
The following valves require further evaluation:
Flow Dia ram
~Valve Ta 1/2-5129 1/2-5142 1-5151A 1-5151C 2-5151A 2-5151C 1/2-SI-185 1/2-SI-101 1-DL-115A 1-DL-115C 2-DL-116A 2-DL-116C
ATTACHMENT 2 TO AEP:NRC:0969U REVISED IST VALVE PROGRAM
SUMMARY
SHEETS
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
1-5144-28 Revision No:
3B Date:
9-30-91 NOTE 1 CTS-138E
& W Code Relief These check valves are located in the lines which supply water from the RWST to the containment spray pumps.
The valves cannot be full stroke exercised during power operation, cold shutdown or refueling without spraying the containment.
The valves are part stroke exercised during containment spray pump testing on a quarterly basis.
The only practical method available to verify full stroke of these valves is by disassembly.
These valves are not equipped with position indicators.
The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of two) per GL-89-04, Attachment 1, Item 52, once every other refueling frequency.
NOTE 2 CTS-103 E
& W Code Relief These check valves are located in the discharge lines of containment spray pumps to the spray ring headers in the containment.
These valves cannot be full stroke exercised during power operation, cold shutdown or refueling without spraying the containment.
The valves are part stroke exercised during containment spray pump testing on a quarterly basis.
The only practical method available -to verify full stroke of these valves is by disassembly.
The valves are not equipped with position indicators.
The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of two) per GL-89-04, Attachment 1, Item 52, once every other refueling frequency.
page 49 of 81
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
1-5144-28 Revision No:
3B Date:
9-30-91 NOTE 3:
NOTE 4 CTS-131E
& W Code Relief
- These check valves are located in the supply lines to the (upper compartment) containment spray ring headers.
These valves are in the closed position during normal plant operation.
These valves perform an open safety function when containment spray is active (pass flow to the ring headers) and a
subsequent closed safety function (containment isolation) if containment spray is suspended.
The valves are exposed to containment atmosphere on the downstream side and are isolated from fluid pressure in the upstream side by the closed motor operated valves.
The yalves cannot be part or full stroke exercised during power operation, cold shutdown or refueling because flow through these valves would result in spraying the containment.
This could cause problems with wet lagging, corrosion of components inside containment, etc.
The only practical method available to exercise these valves is by disassembly.
The valves are not equipped with position indicators.
The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of two) per GL-89-04, Attachment 1, Item N2, once every other refueling frequency.
Disassembly, manual exercising and visual
- examination assure that the valves are capable of performing both the active open and active closed safety function.
CTs-127E W
code Relief
- These check valves are located in the supply lines to the (lower compartment) containment spray ring headers.
These valves are in the closed position during normal plant operation, These valves perform an open safety function when containment spray is active (pass flow to the ring headers) and a
subsequent closed safety function (containment isolation) if containment spray is suspended.
The valves are exposed to containment atmosphere on the downstream side and are isolated from fluid pressure in the upstream side by the closed motor operated Page 50 of 81
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
1-5144-28 Revision No:
3B Date:
9-30-91 Note 4 (continued).
valves.
The valves cannot be part or full stroke exercised during power operation, cold shutdown or refueling because flow through these valves would result in spraying the containment.
This could cause problems with wet lagging, corrosion of components inside containment, etc.
The only practical method available to exercise these valves is by disassembly.
The valves are not equipped with position indicators.
The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of two) ger GL-89-04, Attachment 1, Item 52, once every other refueling frequency.
Disassembly, manual exercising and visual examination assure that the valves are capable of performing both the active open and active closed safety function.
NOTE 5 RH-141
& -142 Code Relief
- These check valves are located in the supply lines to the (upper compartment) containment spray ring headers from the RHR Heat Exchangers.
These valves are in the closed position during normal plant operation.
These valves perform an open safety function when containment spray is active (pass flow to the ring headers) and a subsequent closed safety function (containment isolation) if containment spray is suspended.
The valves are exposed to containment atmosphere on the downstream side and are isolated from,fluid pressure in the upstream side by the closed motor operated valves.
The valves cannot be part or full stroke exercised during power operation, cold shutdown or refueling because flow through these valves would result in spraying the contyinment.
This could cause problems with wet lagging, corrosion of components inside containment, etc.
The only practical method available to exercise these valves is by disassembly.
The valves are not equipped with position indicators.
The valves will be disassembled, manually full stroke exercised and Page 51 of 81
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM
. RELIEF REQUEST NOTES Flow Diagram No:
1-5144-28 Revision No:
3B Date:
9-30-91 Note 5 (continued) visually examined on a'sampling basis (one of two) per GL-89-04, Attachment 1, Item 42, once every other refueling frequency.
Disassembly, manual exercising and visual examination assure that the valves are capable of performing both the active open and active closed safety function.
NOTE 6 CTS-109 and -110 Cold Shutdown Justification These check valves function as vacuum breakers for spray additive tank.
The check valves are closed during normal plant operation to maintain the tank pressurized.
The valves will be verified closed quarterly during power operation and will be verified open at cold shutdown frequency.
NOTE 7 CTS-127E&W CTS-131E&W RH-141 -142 Code Relief
. These valves are to be seat leakage tested in accordance with the unique testing methods established in the FSAR because of the configuration at D.C.
Cook Plant.
The permissible seat leakage"values of these valves are listed in Attachment "A".
Page 52 of 81
~:
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
1-5151B-28 Revision No:
3B Date:
9-30-91 NOTE 1:
DG-101A
-103A
-127A 129A
-145A
-151A and -153A Comment The required full stroking'f the check valves is satisfied when the diesel generator successfully completes its required testing per Technical Specification 4.8.1.1.2.
NOTE 2:
T-132-1AB Code Relief This valve is located at the discharge of the emergency diesel engine jacket water pump.
This three-way thermostatic valve functions to maintain the correct proportion of water flowing through the diesel engine water cooler and bypassing the diesel engine jacket water cooler to maintain a preset jacket water temperature.
We are requesting exemption from the testing requirements since (1) this valve functions only as a regulating valve and not open/closed valve; (2) this valve is demonstrated operable during diesel generator testing.
Diesel generators are tested per Technical Specification 4.8.1.1.2.
The valve will be verified operable by observing proper temperatures during diesel testing.
NOTE 3
XRV-221 and 222 -Startin Air Code Relief The starting air valves are installed on parallel air supply lines to the emergency diesel generator (EDG).
The valves are not equipped with position indication devices to directly measure valve stroke times.
The valves function to provide starting air which rolls the EDG.
The valves are functionally redundant to each other.
These valves fail "as is," and, therefore, they have no fail safe position.
Successful starting of the EDG in accordance with Technical Specification 4.8.1.1.2 (i.e., slow start at least quarterly and fast start once every 184 days within 10 seconds) will verify the Page 58 of 81
C \\
F
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
1-5151B-28 Revision No:
3B Date:
9-30-91 NOTE 4:
Note 3 (continued) valve performance.
The valve stroke timing will be verified by measuring diesel starting times during fast start testing of EDG.
The valves on a staggered basis will be valved out one at a time to verify the operability of the opposite valve during slow start of EDG at least quarterly.
Position indication will be confirmed during the above testing when only one starting air train is used to start the diesel generators.
XRV-220-Jet A sist Code Relief This valve,'s function is to facilitate the EDG fast start by providing an air boost to the turbo charger to assist in starting the EDG in its Technical Specification 4.8.1.1.2 time limitation of 10 seconds.
The valve is not equipped with position indication devices; therefore, meaningful stroke times are not achievable.
The valves will be full stroke and fail safe tested by verifying EDG starting time once per 184 days in accordance with Technical Specification 4.8.1.1.2.
NOTE 5 DG-127A
-129A
-151A
-153A Comment The closed safety function of these valves will be demonstrated by quarterly exercising/closed verification.
Page 59 of 81
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
1-5151C-26 Revision No:
3B Date:
9-30-91 NOTE 1:
DF-108C
-109C
-114C
-115C DL-113C
-115C
-125C and -131C
-157C Comment The required full stroking of the check valves is satisfied when the diesel generator successfully completes its required testing per Technical Specification 4.8.1.1.2.
NOTE 2:
NOTE 3:
T-114-1CD Code Relief This valve is located at the discharge of the engine driven lube oil pump (diesel-generator).
This three-way thermostatic valve functions to maintain the correct lube oil temperature by maintaining the correct proportion of oil flowing through the lambe oil cooler and bypassing the lube oil cooler to maintain a preset lube oil temperature.
We are requesting exemption from testing requirements since (1) this valve functions only as a regulating valve and not opened/closed valve; (2) this valve is demonstrated operable during diesel generator testing.
Diesel generators are tested per Technical Specification 4.8.1.1.2.
The valves will be verified operable by observing proper temperatures during diesel testing.
DF-108C
-109C
-114C
-115C Comment The closed safety function of these valves will be demonstrated by quarterly exercising/closed verification.
Page 60 of 81
./
I I
p1 l/
P
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
1-5151D-28 Revision No:
3B Date:
9-30-91 NOTE 1:
DG-101C
-103C
-127C
-129C
-145C
-151C and -153C Comment The required full stroking of the check valves is satisfied when the diesel generator successfully completes its required testing per Technical Specification 4.8.1.1.2.
NOTE 2
NOTE 3:
T-132-1CD Code Relief This valve is located at the discharge of the emergency diesel engine jacket water pump.
This three-way thermostatic valve functions to maintain the correct proportion of water flowing through the diesel engine water cooler and bypassing the diesel engine jacket water cooler to maintain a preset jacket water temperature.
We are requesting exemption from the testing requirements since (1) this valve functions only as a regulating valve and not open/closed valve; (2) this valve is demonstrated operable during diesel generator testing.
Diesel generators are tested on a staggered
- basis, every 31 days per Technical Specification 4.8.1.1.2.
The valve will be verified operable by observing proper temperatures during diesel testing.
XRV-226 and -227 -Startin Air Code Relief The starting air valves are installed on parallel air supply lines to the emergency diesel generator (EDG).
The valves are not equipped with position indication devices to directly measure valve stroke times.
The valves function to provide starting air which rolls the EDG.
The valves are functionally redundant to each other.
These valves fail "as is," and, therefore, they have no fail safe position.
Successful starting of the EDG in accordance with Technical Specification 4.Q.1.1.2 (i.e.,
slow start at least quarterly and fast start once every 184 days within 10 seconds) will verify the Page 61 of 81
l' l
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
1-5151D-28 Revision No:
3B Date:
9-30-91 NOTE 4:
NOTE 5 Note 3 (continued) valve performance.
The valve stroke timing will be verified by measuring diesel starting times during fast start testing of EDG.
The valves on a staggered basis will be valved out one at a time to verify the operability of the opposite valve during slow start of EDG at least quarterly.
Position indication will be confirmed during the above testing when only one starting air train is used to start the diesel generators.
XRV-225 -Jet ssist Code Relief This valve's function is to facilitate the EDG fast start by providing an air boost to the
'urbo charger to assist in starting the EDG in its Technical Specification 4.8.1.1.2 time limitation of 10 seconds.
The valve is not equipped with position indication devices; therefore, meaningful stroke times are not achievable.
The valves will be full stroke and fail safe tested by verifying EDG starting time once per 184 days in accordance with Technical Specification 4.8.1.1.2.
DG-127C
-129C
-151C
-153C Comment The closed safety function of these valves will be demonstrated by quarterly exercising/closed verification.
Page 62 of 81
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
12-5131 Unit-1 Revision No:
3B Date:
9-30-91 NOTE 1 CS-427N Cold Shutdown Justification This valve is located in the emergency boration path.
This valve cannot be tested during power operation without inserting large negative reactivity which would result in unit shutdown.
The valve will be full stroke exercised at cold shutdown frequency.
Page 65 of 81
SYSTEM:
COHPOHEHT COOLIHG ~
DOHALO C.
COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE
SUMMARY
SHEET - UNIT 1
FLSI DIAGRAM: 1-5135A-30 VALVE VALVE POSITION ASHE SECTION XI Valve Tag Rev Type Size Actuator Coords Power Safety Operation Function Active/
Test Class Passive Category Required Test Test Relief Performed Frequency Request I-CCll-176-E 3B CK 16.00 SA L/4 0/C 1-CCM-176-ll 38 CK 16.00 SA K/4 0/C 1-CH0.410 3
BF 16.00 MO H/4 0/C 0/C 3
A 0/C 3
A 0
3 CF-1 CF-1 EF-1 EF-5 ET.XXX CF-1 CF-1 EF-1 EF-5 ET-XXX NO NO NO HO HO 1-CH0.411 3
BF 18.00 HO N/5 0
3 A
EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX NO MO NO, NOTE 2 1-CHO-412 1-CH0.413 3
BF 16.00 HO 3
BF 18.00 NO L/3 0
L/5 0
3 A
3 A
EF 1
EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P
NO HO NO, MOTE 2 NO NO NO, NOTE 2 1-CH0.414 3
BF 16.00 NO T-CN0.415 3
BF 16.00 HO I-CHO-416 3
BF 16.00 HO 1-CHO-419 3
BF 14.00 MO 1-CH0.420 3
BF 16.00 NO 1-CHO-429 3
BF 14.00 HO K/3 0
H/5 0
G/5 0
E/5 C
H/4 0/C E/5 C
C 3
A 3
A 3
A 3
A 3
A 3
A EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 FT-XXX EF-1 EF-5 ET-XXX EF-1 EF 5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX NO HO HO, NOTE 2 NO MO HO, NOTE 2 HO NO NO, NOTE 2 NO MO NO HO HO HO HO HO NO
SYSTEN:
COHPOHENT COOLING DOHALD C.
COOK NUCLEAR PLAHT SECOND TEH YEAR INTERVAL VALVE SUHHARY SHEET - UHIT 1
FLOH D IAGRAH: 1-5135A-30 VALVE Valve Tag Rev
. Type Size Actuator Coords VALVE POSITION Po~er Safety Operation Function ASHE SECTION XI Active/
Test Test Test Relief Class passive Category Required perforated Frequency Request 1-CRV-412 3
GL 4.00 A
1-SV-60 3
REL 3.00 SA 1-SV-72 3
REL 1.00 SA 12.CCM-170 38 CK 16.00 SA K/1 0
L/1 C
E/5 C
JI/4 C
3 A
0 3
0 3
A 0/C
3 A
EF-1 EF-5 EF-7 ET-XXX TF-1 TF-1 CF-1 EF-1 EF-5 EF-7 ET-XXX TF-1 TF 1
CF-4 P
HO HO P
HO P
HO R
NO R
NO NO, NOTE 1
SYSTEH:
CONTAINHENT SPRAY
~
DONALD C.
COOK NUCLEAR PLANT SECOND TEN YEAR lNTERVAL VALVE SUHHARY SHEET - UNlT 1 FLON 0lAGRAH: 1-5144-28 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITlON Po)}er Safety Operation Fmction ASHE SECTION Xl Active/
Test Test Test Relief Class Passive Category Required Performed Frequency Request 1-CTS-103-E 3
CK 10.00 SA 1-CTS-103.IJ 3
CK 10.00 SA 1-CTS-109 1-CTS-110 3
CK 2.00 SA 1.CTS-120-'N 3
CK 2.00 SA 1.CTS-127-E 38 CK 6.00 SA J/9 C
L/9 C
H/6' H/6 C
H/8 C
K/8 C
E/5 C
0/C 2
A 2
A 2
A 0
2 A
0 2
0 2
2 A
AC CF-1 SLT-1 C
CF-1 C
CF-1 C
CF-1 C
CF-1 C
CF-1 C
CF-1 CF-3 CF-3 CF-2 CF-2 CF-1 CF-1 CF-2 SLT-2A
- YES, NO'TE 2
- YES, NOTE 2 C
NO, CSJ 6 C
NO, CSJ 6 P
NO P
NO R
- YES, NOTE 4 R
- YES, NOTE 7 1-CTS-127.II 3B CK 6.00 SA 1-CTS-131-E 38 CK 8.00 SA 1-CTS-131-II 3B CK 8.00 SA 1.lH0.202 3
GA 2.50 HO 1-lHO-204 3
GA 2.50 HO 1-lHO-210 3
GA 10.00
) HO 1.1H0.211 3
GA 10.00 HO 1-CTS-138-E 3
CK 12.00 SA 1-CTS-138-M 3
CK 12.00 SA E/4 C
E/2 C
E/2 C
G/9 C
J/9 C
H/7 C
H/7 C
J/8 C
J/8 C
0/C 2
A 0/C 2
0/C 2
0/C 2
A 0/C 2
A 0
2 A
2 A
2 A
2 A
AC AC AC SLT-1 CF-1 SLT-1 CF-1 SLT-1 CF-1 CF-1 CF-1 EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 El'-XXX SLT-2A CF-2 SLT-2A CF-2 SLT-2A CF-2 CF-3 CF-3 EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX R
- YES, NOTE 7 R
- YES, NOTE 4 R
- YES, NOTE 7 R
- YES, NOTE 3 R
- YES, NOTE 7 R
- YES, NOTE 3
- YES, NOTE 1
- YES, NOTE 1
P NO NO P
NO P
NO NO P
NO P
NO NO P
NO P
NO NO P
NO
SYSTEH:
CONTAlNHENT SPRAY DONALD C.
COOK NUCLEAR PLANT SECOND TEN YEAR lNTERVAL VALVE SUHHARY SHEET - UNlT 1
FLOI D IAGRAH: 1-5144-28 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSlTION Po~er Safety Operation
'Function ASHE SECTION Xl Active/
Test Test Test Relief Class Passive Category Required Performed Frequency Request 1-IHO-212 3
GA 2.00 HO 1-lk0.215 3
GA 12.00 HO 1-1H0.220 3
GA 10.00 HO 1.lH0-221 3
GA 10.00 HO 1-IHO-222 3
GA 2.00 HO 1-IHO-225 3
GA 12.00 HO 1-RN-141 3B CK 8.00 SA'-RH-142 3B CK 8.00 SA 1-SV-107 3
REL 1.00 SA H/8 0
G/9 0
L/8 C
L/8 C
L/9 0
J/9 0
E/3 C
E/3 C
N/5 C
0/C 2
A 0/C 2
A 2
A 2
A 0/C 2
0/C 2
A 0/C 2
A 0/C 2
A 2
A AC AC EF.1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF.5 ET-XXX EF-1 EF.S ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX SLT-1 CF-1 CF-1 SLT-1 TF-1 EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX SLT-2A CF-2 CF-2 SLT-2A TF-1 NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO
- YES, NOTE 7
- YES, NOTE 5
- YES, NOTE 5
- YES, NOTE 7 NO
t
SYSTEH:
EHERGEHCY DIESEL GENERATOR 'AB'ONALD C.
COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUHHARY SHEET - UNIT 1 FLOI DIAGRAM: 1-51518 28 VALVE Valve Tag Rev Type Site Actuator Coords VALVE POSITIOH Po~er Safety Operation Function ASHE SECTION XI Active/
Test Test Test Relief Class passive Category Required performed Frequency Request 1-DG-101A 1-DG-103A 1-DG-127A 1-DG-129A 1-DG-139A 1-00.141A 1-DG-145A 1-DG-151A 1-DG-153A 3
CK 1.50 SA 3
CK 1.50 SA 38 CK 1.00 SA 38 CK 1.00 SA 3
CK 0.50 SA 3
CK 0.50 SA 3
CK 2.00 SA 38 CK 2.00 SA 38 CK 4.00 SA 1-XRV-220 3
GA 1.00 A
1-aT-132-1AB 3
3M 6.00 SA 1-SV-120-1AB 3
REL 0.25 SA 1-SV-139-1AB 3
REL 1.00 SA 1-SV-61-1AB 3
REL 1.00 SA
'-SV-78-1A81 3
REL 1.00 SA 1-SV-78-1A82 3
REL 1.00 SA 1-SV.79-1A81 3
REL 0.50 SA 1-SV-79-1AB2 3
REL 0.50 SA H/4 F/3 C/4 C/4 F/1 F/1 A/e ole C/8 E/8 G/2 8/2 A/8 E/3 0/3 E/1 E/1 8/3 0/C 0/C 0/C 0/C 0/C 0/C 0/C 0/C 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
-A 3
A 3
A CF-1 CF-1 CF.1 CF-1 CF-1 CF-I CF-1 CF-1 CF-1 EF-1 TF-1 TF-1 TF-1 TF-1 TF-1 TF-1 TF-1 EF-1 EF-7 ET-XXX CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 NOTE 2 TF-1 TF-1 TF-1 TF-1 TF-1 TF-1 TF-1 EF-1 EF-7 NOTE 4 P
NO, NOTE 1
P NO, NOTE 1
P NO, NOTE 1,5 P
NO, NOTE 1,5 P
NO P
NO P
NO, HOTE 1
P HO, NOTE 1,5 P
NO, NOTE 1,5 P
NO, NOTE 2 R
NO R
HO R
HO R
NO R
HO R
NO R
NO
- YES, NOTE 4 NO, NOTE 4
- YES, NOTE 4 1-XRV-221 3
GL 3.00 A
8/4 C
3 A
EF-1 EF-7 ET-XXX EF-1 NOTE 3 HOTE 3
- YES, NOTE 3
- YES, NOTE 3
- YES, NOTE 3 1-XRV-222 3
GL 3.00 A
8/4 C
3 A
EF.1 EF-7 EF-1 NOTE 3
- YES, NOTE 3
- YES, NOTE 3
/"
J f
SYSTEH:
EHERGENCY DIESEL GENERATOR 'AB'ONALD C.
COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET - UNIT 1
FLOl DIAGRAH: 1-51518-28 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITION Power Safety Operation Function ASHE SECTION XI Active/
Test Test Test Relief Class Passive Category Required Performed Frequency Request 1-XRV-222 3
GL 3.00 A
BP C
0 3
A ET-XXX NOTE 3
- YES, NOTE 3
S'YSTEH:
EMERGENCY DIESEL GEHERATOR 'CD'ONALD C.
COOK NUCLEAR PLANI'ECOND TEH YEAR INTERVAL VALVE
SUMMARY
SHEEt UNIT 1 FLN DIAGRAM: 1-5151C-26 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITIOH Po~er Safety Operation Function ASNE SECTIOH XI Active/
Test Test Test Relief Class Passive Category Required Performed Frequency Request 1-DF.10BC 1-DF-109C 1-DF-114C 1-DF-115C 1-0L.113C 1-DL-115C 1-DL-125C 1-DL-131C 1-DL-157C 3B CK 1.50 SA 3B CK 1 50 SA 3B CK 1 50 SA 3B CK F 50 SA 3
CK 1.50 SA 3
CK 1.50 SA 3
CK 2.50 SA 3
CK 1.00 SA 3
CK 6.00 SA 1-OT-114-1CO 3
3H 6.00 SA J/3 K/3 L/3 H/3 B/9 8/9 E/9 F/9 G/5 H/5 0/C 0/C 0/C 3
3 A
3 3
A 3
A 3
A 3
A 3
A 3
"A 0/C 3
A CF-I CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 EF 1
CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF.1 CF-1 CF-1 NOTE 2 NO, NOTE 1,3 NO, NOTE 1,3 NO, NOTE 1,3 HO, NOTE 1,3 NO, NOTE 1
NO, NOTE 1
NO, NOTE 1
NO, NOTE 1
NO,'NOTE 1
HO, MOTE 2
SYSTEM:
EMERGENCY DIESEL GENERATOR 'CD'ONALD C.
COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE
SUMMARY
SHEET - UNIT 1
FLN DIAGRAII: 1-5151D 28 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITION Poger Safety Operation function ASHE SECTION XI Active/
Test Test Test Relief Class Passive Category Required Performed Frequency Request 1.DG-101C 3
CK 1.50 SA 1-DG-103C 3
CK 1.50 SA 1.DG-127C 3B CK 1.00 SA 1-DG-129C 3B CK 1.00 SA 1-DG-139-CO 3
CK 0.50 SA 1-DG.141-CD 3
1-DG.145C 3
CK 0.50 SA CK 2.00 SA 1 ~ DG-151C 38 CK 7.00 SA 1.DG-153C 38 CK 4.00 SA 1-GT-132-1CD 3
3M 6.00 SA 1.SV-120-1CO 3
REL 0.25 SA 1 SV-139-1CD 3
REL 1.00 SA 1 SV-61-1CD 3
REL 1.00 SA" 1 SV-78-1CD1 3
REL 1.00 SA 1-SV-78-1CD2 3
REL 1.00 SA 1-SV-79.1CD1 3
REL 0.50 SA 1-SV-79-1CD2 3
REL 0.50 SA 1-XRV-225 3
GA 1.00 A
H/4 0
F/3 0
C/3 C
C/3 C
F/1 C
F/1 C
A/9 0
D/9 C
C/9 C
E/8 0
H/2 C
8/2 C
A/8 C
E/3 C
D/3 C
E/1 C
E/1 C
8/3 0/C 0/C 0/C 0/C 0/C 0/C 0/C 0/C 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF 1
CF-1 EF-1 TF-1 TF.1 TF-1 TF-1 EF-1 Ef-7 ET-XXX CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF 1
CF-1 CF-1 NOTE 2 TF-1 TF-1 TF-1 TF-1 TF-1 TF-1 Ef-1 Ef-7 MOTE 4 NO, NOTE 1
NO, NOTE 1
NO, NOTE 1,5 NO, NOTE 1,5 HO NO NO, NOTE 1
NO, NOTE 1,5 NO, NOTE 1,5 HO; NOTE 2 NO NO HO R
HO NO HO HO
- YES, NOTE 4
- YES, NOTE 4
- YES, NOTE 4 1-XRV-226 3
GL 3.00 A
8/4 3
A Ef-1 EF-7 ET-XXX EF-1 HO'IE 3 NOTE 3
- YES, NOTE 3
- YES, NOTE 3
- YES, MOTE 3 1-XRV-227 3
GL 3.00 A
8/4 C
3 A
EF-1 EF-7 EF I NOTE 3
- YES, MOTE 3
- YES, NOTE 3
SYSTEH:
EHERGENCY DIESEL GENERATOR 'CD'ONALD C.
COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET - UNIT 1 FLSI 0 IAGRAH: 1-51510-28 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITION Power Safety Operation Function ASHE SECTION XI Active/
Test Test Test Relief Class Passive Category Required Performed Frequency Request 1-XRV.227 3
GL 3.00 A
B/4 C
3 A
El'-XXX NOTE 3
- YES, NOTE 3
SYSTEM:
CVCS -
BORON MAKE-UP DONALD C.
COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE
SUMMARY
SHEET - UNIT 1
FLON DIAGRAM: 12-5131-19 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITION Pouer Safety Operation Function ASME SECTION XI Active/
Test Test Test Relief Class Passive Category Required Perforaed Frequency Request 1-CS-415-1 1-CS-415-2 1-CS-426-N 1-CS-427-H 1-OMO-410 3B CK 2.00 SA H/6 0/C 3B CK 2.00 SA
'/6 0/C 3
CK 1.00 SA G/6 0/C 3
CK 2.00 SA G/5 C
3 GL 2.00 MO G/5 C
0/C 3
A 0/C 3
3 A
3 A
3 A
CF-1 CF-1 CF-1 CF-1 EF-1 EF-5 ET XXX CF-1 CF.1 CF-1 CF-2 EF-1 EF-5 ET-XXX P
NO NO NO HO, CSJ 1
NO NO HO 1-QRV-411 3
GL 1.00 A
1-QRV 412 3
GL 2.00 A
G/6 0/C F/7 0
3 A
EF-1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET XXX EF-1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P
P P
NO NO NO NO NO NO NO NO
SYSTEN:
CVCS -
BOROH NAKE-UP DOHALD C.
COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE
SUMMARY
SNEET - UHIT 2 FLN DIAGRAN: 12-5131-19 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITION Pover Safety Operation Function ASNE SECTION XI Active/
Test Test Test Relief Class Passive Category Required Performed Frequency Request 2-CS-415-3 2-CS.415-4 2-CS-426-S 2-CS-427-S 2-QHO-420 3B CK 2.00 SA K/6 0/C.
38 CK 2.00 SA L/6 0/C 3
CK 1.00 SA N/6 0/C 3
CK 2.00 SA N/5 C
3 GA 2.00 NO L/5 C
0/C 3
0/C 3
3 A
3 A
3 A
CF-1 CF-1 CF-1 EF-1 EF-5 ET-XXX CF-1 CF-1 CF.2 EF-1 EF-5 ET-XXX CF-1 'F-1 NO NO HO NO, CSJ 1
NO HO NO 2-QRV-421 3
GL 2.00 A
L 2-QRV-422 3
GL 2.00 A
H/6 0/C N/7 0
3 A
3 A
EF-1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX HO NO MO NO MO NO HO NO
p I p
I
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
2-5144-29 Revision No:
3B Date:
9-30-91 NOTE 1:
NOTE 2:
CTS-138E W
Code Relief These check valves are located in the lines which supply water from the RWST to the containment spray pumps.
The valves cannot be full stroke exercised during power operation, cold shutdown or refueling without spraying the containment.
The valves are part stroke exercised during containment spray pump testing on a quarterly basis.
The only practical method available to verify full stroke of these valves is by disassembly.
These valves are not equipped with position indicators.
The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of two) per GL-89-04, Attachment 1, Item N2, once every other refueling frequency.
CTS-103 E
W Code Relief These check valves are located in the discharge lines of containment spray pumps to the spray ring headers in the containment.
These valves cannot be full stroke exercised during power operation, cold shutdown or refueling without spraying the containment.
The valves are part stroke exercised during containment spray pump testing on a quarterly basis.
The only practical method available to verify full stroke of these valves is by disassembly.
The valves are not equipped with position indicators.
The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of two) per GL-89-04, Attachment 1, Item 42, once every other refueling frequency.
Page 49 of 81
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
2-5144-29 Revision No:
3B Date:
9-30-91 NOTE 3:
NOTE 4:
CTS-131E
& W Code Relief
- These check valves are located in the supply lines to the (upper compartment) containment spray ring headers.
These valves are in the closed position during normal plant operation.
These valves perform an open safety function when containment spray is active (pass flow to the ring headers) and a
subsequent closed safety function (containment "isolation) if containment spray is suspended.
The valves are.exposed to containment atmosphere on the downstream side and are isolated from fluid pressure in the upstream side by the closed motor operated valves.
The yalves cannot be part or full stroke exercised during power operation, cold shutdown or refueling because flow through these valves would result in spraying the containment.
This could cause problems with wet lagging, corrosion of components inside containment, etc.
The only practical method available to exercise these valves is by disassembly.
The valves are not equipped with position indicators.
The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of two) per GL-.89-04, Attachment 1, Item N2, once every other refueling frequency.
Disassembly, manual exercising and visual examination assure that the valves are capable of performing both the active open and active closed safety function.
CTS-127E
& W Code Relief
- These check valves are located in the supply lines to the (lower compartment) containment spray ring headers.
These valves are in the closed position during normal plant operation.
These valves perform an open safety function when containment spray is active (pass flow to the ring headers) and a
subsequent closed safety function (containment isolation) if containment spray is suspended.
The valves are exposed to containment atmosphere on the downstream side and are isolated from fluid pressure in the upstream side by the closed motor operated Page 50 of 81
V
'r
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
2-5144-29 Revision No:
3B Date:
9-30-91 NOTE 5 Note 4 (continued) valves.
The valves cannot be part or full stroke exercised during power operation, cold shutdown or refueling because flow through these valves would result in spraying the containment.
This could cause problems with wet lagging, corrosion of components inside containment, etc.
The only practical method available to exercise these valves is by disassembly.
The valves are not equipped with position indicators.
The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of two) ger GL-89-04, Attachment 1, Item 52, once every other refueling frequency.
Disassembly, manual exercising and visual examination assure that the valves are capable of performing both the active open and active closed safety function.
RH-141
& -142 Code Relief
- These check valves are located in the supply lines to the (upper compartment) containment spray ring headers from the RHR Heat Exchangers.
These valves are in the closed position during normal plant operation. 'hese valves perform an open safety function when containment spray is active (pass flow to the ring headers) and a subsequent closed safety function (containment isolation) if containment spray is suspended.
The valves are exposed to containment atmosphere on the downstream side and are isolated from fluid pressure in the upstream side by the closed motor operated valves.
The valves cannot be part or full stroke exercised during power operation, cold shutdown or refueling because flow through these valves would result in spraying the con0qinment.
This could cause problems with wet lagging, corrosion of components inside containment, etc.
The only practical method available to exercise these valves is by disassembly.
The valves are not equipped with position indicators.
The valves will be disassembled, manually full stroke exercised and
\\
Page 51 of 81
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
2-5144-29 Revision No:
3B Date:
9-30-91 NOTE 6-NOTE 7 Note 5 (continued) visually examined on a sampling basis (one of two) per GL-89-04,, Item g2, once every other refueling frequency.
Disassembly, manual exercising and visual examination assure that the valves are capable of performing both the active open and active closed safety function.
CTS-109 and -110 Cold Shutdown Justification These check valves function as vacuum breakers for spray additive tank.
The check valves are closed during normal plant operation to maintain the tank pressurized.
The valves will be verified closed quarterly during power operation and will be verified open at cold shutdown frequency.
CTS-127E&W CTS-131E&W RH-141 -142 Code Relief These valves are to be seat leakage tested in accordance with the unique testing methods established in the FSAR because of the configuration at D.C.
Cook Plant.
The permissible seat leakage values of these valves are listed in Attachment "A".
Page 52 of 81
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
2-5151A-26 Revision No:
3B Date:
9-30-91 NOTE 1:
DF-108A
-109A 14A
-115A DL-114A
-116A
-1 6A
-132A
-158A wE
'atisfied when the diesel generator successfully completes its required testing per Technical Specification 4.8.1.1.2.
NOTE 2:
NOTE 3 T-114-2AB Code Relief This valve is located at the discharge of the engine driven lube oil pump (diesel-generator).
This three-way thermostatic valve functions to maintain the correct lube oil temperature by maintaining the correct proportion of oil flowing through the i@be oil cooler and bypassing the lube oil cooler to maintain a preset lube oil temperature.
We are requesting exemption from testing requirements since (1) this valve functions only as a regulating valve and not opened/closed; (2) this valve is demonstrated operable during diesel generator testing.
Diesel generators are tested basis per Technical Specification 4.8.1.1.2.
The valves will be verified operable by observing, proper temperatures during diesel testing.
DF-108A
-109A
-114A
-115A Comment
- The closed safety function of these valves will be demonstrated by quarterly exercising/closed verification.
Page 57 of 81
l,
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
2-5151B-27 Revision No:
3B Date:
9-30-91 NOTE 1:
DG-102A
-104A
-128A 130A
-146A
-152A and -154A Comment The required full stroking of the check valves is satisfied when the diesel generator successfully completes its required testing per Technical Specification 4.8.1.1.2.
NOTE 2:
NOTE 3:
T-132-2AB Code Relief This valve is located at the discharge of the emergency diesel engine jacket water pump.
This three-way thermostatic valve functions to maintain the correct proportion of water flowing through the diesel engine water cooler and bypassing the diesel engine jacket water cooler to maintain a preset jacket water temperature.
He are requesting exemption from the testing requirements since (1) this valve functions only as a regulating valve and not open/closed valve; (2) this valve is demonstrated operable during diesel generator testing.
Diesel generators are tested per Technical Specification 4.8.1.1.2.
The valve will be verified operable by observing proper temperatures during diesel testing.
XRV-221 and 222 -Startin Air Code Relief The starting air valves are installed on parallel air supply lines to the emergency diesel generator (EDG).
The valves are not equipped with position indication devices to directly measure valve stroke times.
The valves function to provide starting air which rolls the EDG.
The valves are functionally redundant to each other.
These valves fail "as is," and, therefore, they have no fail safe position.
Successful starting of the EDG in accordance with Technical Specification 4.8.1.1.2 (i.e.,
slow start at least quarterly and fast start once every 184 days within 10 seconds) will verify the valve performance.
The, valve stroke timing will be verified by page 58 of 81
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
2-5151B-27 Revision No:
3B Date:
9-30-91 NOTE 4:
NOTE 5:
Note 3 (continued) measuring diesel starting times during fast start testing of EDG.
The valves on a staggered basis will be valved out one at a time to verify the operability of the opposite valve during slow start of EDG at least quarterly.
Position indication will be confirmed during the above testing when only one starting air train is used to start the diesel generators.
XRV-220-Jet Assist Code Relief This valve's function is to facilitate thy EDG fast start by providing an air boost to the turbo charger to assist in starting the EDG in its Technical Specification 4.8.1.1.2 time limitation of 10 seconds.
The valve is not equipped with position indication devices; therefore, meaningful stroke times are not achievable.
The valves will be full stroke and fail safe tested by verifying EDG starting time once per 184 days in accordance with Technical Specification 4 ~ 8 ~ 1.1.2.
DG-128A
-130A
-152A
-154A Comment
- The closed safety function of these valves will be demonstrated by quarterly exercising/closed verification.
Page 59 of 81
.0 C
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
2-5151D-27 Revision No:
3B Date:
9-30-91 NOTE 1 DG-102C
-104C
-128C
-130C
-146C
-152C and -154C Comment The required full stroking of the check valves is satisfied when the diesel generator successfully completes its required testing per Technical Specification 4.8.1.1.2.
NOTE 2:
NOTE 3:
T-132-2CD Code Relief This valve is located at the discharge of the emergency diesel engine jacket water pump.
This three-way thermostatic valve functions to maintain the correct proportion of water flowing through the diesel engine water cooler and bypassing the diesel engine jacket water cooler to maintain a preset jacket water temperature.
We are requesting exemption from the testing requirements since (1) this valve functions only as a regulating valve and not open/closed valve; (2) this valve is demonstrated operable during diesel generator testing.
Diesel generators are tested on a staggered
- basis, every 31 days per Technical Specification 4.8.1.1.2.
The valve will be verified operable by observing proper temperatures during diesel testing.
XRV-226 and -227 -Startin Air Code Relief The starting air valves are installed on parallel air supply lines to the emergency diesel generator (EDG).
The valves are not equipped with position.
indication devices to directly measure valve stroke times.
The valves function to provide starting air which rolls the EDG.
The valves are functionally redundant to each other.
These valves fail "as is," and, therefore, they have no fail safe position.
Successful starting of the EDG in accordance with Technical Specification 4.8,1.1.2 (i.e., slow start at, least quarterly and fast start once every 184 days within 10 seconds) will verify the Page 61 of 81
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
2-5151D-27 Revision No:
3B Date:
9-30-91 NOTE 4:
NOTE 5:
Note 3 (continued) valve performance.
The valve stroke timing will be verified by measuring diesel starting times during fast start testing of EDG.
The valves on a staggered basis will be valved out one at a time to verify the operability of the opposite valve during slow start of EDG at least quarterly.
Position indication will be confirmed during the above testing when only one starting air train is used to start the diesel generators.
XRV-225 -Jet ssist Code Relief This valve's function is to facilitate the EDG fast start by providing an air boost to the turbo charger to assist in starting the EDG in its Technical Specification 4.8.1.1.2 time limitation of 10 seconds.
The valve is not ecpxipped with position indication devices; therefore, meaningful stroke times are not achievable.
The valves will be full stroke and fail safe tested by verifying EDG starting time once per 184 days in accordance with Technical Specification 4.8.1.1.2.
DG-128C
-130C
-152C
-154C Comment
- The closed safety function of these valves will be demonstrated by quarterly exercising/closed verification.
Page 62 of 81
DONALD C.
COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
12-5131-19 Unit-2 Revision No:
3B Date:
9-30-91 NOTE 1:
CS-427S Cold Shutdown Justification This valve is located in the emergency boration path.
This valve cannot be tested during power operation without inserting large negative reactivity which would result in unit shutdown.
The valve will be full stroke exercised at cold shutdown frequency.
Page 65 of 81
SYSTEH:
COHPONENT COOLING DONALD C.
COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET - UNIT 2 FLOU 0 IAGRAH: 2-5135A-30 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITION Power Safety Operation Function ASHE SECTION XI Active/
Test Test Class Passive Category Required Performed Test Frequency Relief Request 2.CCM-176.E 3B CK 16.00 SA 2-CCM-176.LI 3B CK 16.00 SA 2-CH0.410 3
BF 16.00 HO 2-CHO-411 3
BF 18.00 HO L/4 0/C K/4 0/C N/4 0/C H/5 0
0/C 3
A 0/C 3
A 0
3 A
3 A
CF-1 CF-1 EF-1 EF-5 ET-XXX EF-1 EF-5 E'I-XXX CF-1 CF-1 EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX NO NO NO NO NO NO NO NO, NOTE 1
2-CH0.412 3
BF 16.00 HO L/3 0
3 EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX NO NO NO, NOTE 1
2.CH0-413 3
BF 1B.OO HO 2 CHO-414 3
BF 16.00 HO 2-CH0.415 3
BF 16.00 HO 2 CH0.416 3
BF 16.00 HO 2-CH0.419 3
BF 14.00 HO 2-CH0.420 3
BF 16.00
>HO 2 CHO-429 3
BF 14.00 HO L/5 0
K/3 0
H/5 0
G/5 0
E/5 C
H/4 0/C E/5 C
0 3
A 3
A 3
A 3
A 3
A 3
A 3
A EF 1
EF-5 ET-XXX.
EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P
P NO NO NO, NOTE 1
NO NO NO, NOTE 1
NO NO NO, NOTE 1
NO NO NO, NOTE 1
NO NO NO NO NO NO NO NO NO
SYSTEH:
COHPONENT COOLING-DONALD C.
COOK NUCLEAR PLANT SECOND TEN YEAR IN1'ERVAL VALVE SUHHARY SHEET - UNIT 2 FLOM DIAGRAM: 2-5135A-30 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITION Power Safety Operation Fmction ASHE SECTION XI Active/
Test Test Test Relief Class Passive Category Required Performed Frequency Request 2.CRV-412 3
GL 4.00 A
K/1 0
3 A
EF-1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P
NO NO P
NO P
NO 2-SV-60 2-SV-72 3
REL 3.00 SA 3
REL 1.00 SA L/1 C
E/5 C
3 A
3 A
TF-1 TF-1 TF-1 TF-1 R
NO R
NO
SYSTEHt CONTAINHENT SPRAY DONALD C.
COOK KUCLEAR PLAHT SECOND TEN YEAR INTERVAL VALVE SNIHARY SHEET - UNIT 2 FLNI DIAGRAII: 2-5144-29 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITION PoMer Safety Operation Function ASHE SECTION Xl Active/
Test Test Test Relief Class Passive Category Required Performed Frequency Request 2-CTS-103-E 3
CK 10.00 SA 2-CTS-103-M 3
CK 10.00 SA 2-ClS-109 2-CTS.110 3
CK 2.00 SA-2-CTS-I20.II 3
CK 2.00 SA 2-CTS-127-E 38 CK 6.00 SA J/9 C
L/9 C
H/6
-C H/6 C
H/8 C
K/8 C
E/5 C
0/C 2
A 2
A 2
A 2
A 2
A 2
A 2
A AC CF-1 CF-1 CF-1 CF-1
, CF-1 CF-1 SLT-1 CF-1 CF-3 CF-3 CF-2 CF-2 CF-1 CF-1 SLT-2A CF-2 C
- YES, NOTE 2
- YES, NOTE 7
38 CK 8.00 SA E/4 C
E/2 C
E/2 C
0/C 2
A 0/C 2
A 0/C 2
A AC AC AC SLT-1 CF-1 SLT-1 CF-1 SLT-1 CF-1 SLT-2A CF-2 SLT-2A CF-2 SLT-2A CF-2 R
R
- YES, NOTE 7
- YES, NOTE 4 YES, NOlE 7
- YES, NOTE 3
- YES, NOTE 7
- YES, NOTE 3 2-CTS.138.E 3
CK 12.00 SA G/9 C
2-CTS-138-M 3
CK 12.00 SA J/9 C
2-IHO-202 3
GA 2.50 iIO H/7 C
0/C 2
0/C 2
A 0
2 A
CF-1 CF-1 EF-1 EF-5 El-XXX CF-3 CF-3 EF-1 EF-5 ET-XXX
- YES, NOTE 1
YES, NOlE 1
HO NO KO 2-IN-204 3
GA 2.50 HO H/7 C
2 A
EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX KO NO HO 2-IHO-210 3
GA 10.00 MO 2-IHO-211 3
GA 10.00 J/8 C
J/8 C
2 A
2 A
EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX NO NO HO HO KO HO
SYSTEH:
COHTAINHENT SPRAY DONALD C.
COOK NUCLEAR PLANT SECONO TEN YEAR IHTERVAL VALVE SUHHARY SHEET UHIT 2 FLOM 0 IAGRAH: 2-5144-29 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITION Power Safety Operation Function ASHE SECTIOH XI Active/
Test Test Test Relief Class Passive Category Required Performed Frequency Request 2 IHO-212 3
GA 2.00 HO 2-IHO-215 3
GA 12.00 IQ 2-IH0.220 3
GA 10.00 IQ H/8 0
G/9 0
L/8 C
0/C 2
A 0/C 2
2 A
EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF 1
EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P
NO NO P
NO P
NO NO P
NO P
NO NO P
NO 2-IHO-221 2-IHO-222 3
GA 10.00 HO 3
GA 2.00 IQ L/8 C
L/9 0
2 A
0/C 2
A EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF.S ET-XXX EF-1 EF-5 ET-XXX NO NO NO NO NO NO 2-IHO-225 3
GA 12.00 IQ 2-RH.141 38 CK 8.00 SA.
J/9 0
E/3 C
0/C 2
A 0/C 2
A AC EF-1 EF-5 ET-XXX CF-1 SLT-1 EF-1 EF-5 ET-XXX CF-2 SLT-2A NO NO NO
- YES, NOI'E 5
- YES, NOTE 7 2RH142 38 CK 800 SA 2-SV.107 3
REL 1.00 SA E/3 C
H/5 C
.0/C 2
A 2
A AC CF-1 SLT.1 TF-1 CF-2 SLT-2A TF-1
- YES, NOTE 5
- YES, NOTE 7 NO
SYSTEH:
EHERGENCY DIESEL GENERATOR 'AB'ONALD C.
COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET UNIT 2 FLN DIAGRAH: 2-5151A-26 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITION Power Safety Operation Function ASHE SECTION Xl Active/
Test Test Test Relief Class Passive Category Required Performed Frequency Request 2.DF-108A 2.DF-109A 2-DF-114A 2-DF 115A 2-DL-114A 2.DL-116A 2-DL-126A 2-DL-132A 2-DL-158A 3B CK 1.50 SA 3B CK 1.50 SA 3B CK 1.50 SA 3B CK 1.50 SA 3
CK 1.50 SA 3
CK 1.50 3
CK 2.50 SA SA 3
CK 7;00 SA 3
CK 6.00 SA 2 QT.114-2AB 3
3M 6.00 SA L/3 H/3 B/9 B/9 E/9 F/9 G/6 N/5 0/C 0/C 0/C 0/C CF-1 CF.1 CF 1
CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 EF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 NOTE 2 NO, NOTE 1,3 NO, NOTE 1,3 NO, NOTE '1,3 NO, NOTE 1,3 NO, MOTE 1
NO, NOTE 1
NO, NOTE 1
MO, NOTE 1
NO, NOTE 1
NO, NOTE 2
SYSTEN:
EMERGENCY DIESEL GENERATOR 'AB'ONALD C.
COOK NUCLEAR PLANT SECOKD lEN TEAR INTERVAL VALVE SCARY SHEET - UNIT 2 FLOM DIAGRAM: 2-51518-27 VALVE VALVE POS IT IOH ASHE SECTION XI Valve Tag Rev Type Size Actuator Coords PoMer Safety Operation Function Active/
Test Test Test Relief Class Passive Category Required Perforaed Frequency Request 2-DG-102A 2.DG-104A 2-DG-128A 2-DG-130A 2-DG-140A 3
CK 1.50 SA 3
CK 1.50 SA 38 CK 1.00 SA 38 CK 1.00 SA 3
CK 0 50 SA 2-DG-142A 3
CK 0.50 SA 2-DG-146A 2-DG-152A 2-DG-154A 3
CK 2.00 SA 38 CK 4.00 SA 38 CK 4.00 SA 2-OT-132-2AB 3
3H 6.00 SA 2-SV-120-AB 3
REL 0.25'A 2-SV-139-AB 3
REL 1.00 SA 2-SV-61-AB 3
REL 1.00 SA 2-SV-78-A81 3
REL 1.00 SA 2-SV-78-A82 3
REL 1.00 SA 2-SV-79-A81 3
REL 0.50 SA 2-SV-79-AB2 3
REL 0.50 SA H/4 G/4 C/4 C/4 F/1 F/1 A/e ole c/e E/8 G/2 8/2 A/8 E/3 0/3 E/1 E/1 0/C 0/C 0/C 3
A 3
A 3
A 0/C 0/C 0.
0/C 3
A 0/C 3
0/C 3
CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 EF-1 TF-1 TF-1 TF-1 TF-1 TF-1 TF-1 TF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 NOTE 2 TF-1 TF-1 TF-1 TF-1 TF-1 TF-1 TF-1 P
NO, NOTE 1
P KO, NOTE 1
P NO, NOTE 1,5 P
NO, KOTE 1,5 P
NO P
HO P
NO, NOTE 1
P NO, KOTE 1,5 P
NO, NOlE 1,5 P
HO, NOTE 2 R
NO R
NO R
NO R
NO R
KO NO R
NO 2-XRV-220 3
GA 1.00 A
8/3 EF-1 EF-7 ET-XXX EF-1 EF-7 HOlE 4
- YES, NOTE 4
- YES, KOlE 4
- TES, NOTE 4 2-XRV-221 3
GL 3.00 A
2-XRV-222 3
GL 3.00 A
8/4 C
8/4 C
3 A
3 A
EF-1 EF-7 ET-XXX EF-1 EF-7 EF-1 NOTE 3 MOTE 3 EF-1 NOTE 3
- YES, NOTE 3
- YES, NOTE 3
- YES, NOTE 3
- YES, NOTE 3 TEST NOTE 3
SYSTDl: EHERGEHCY 01ESEL GENERATOR 'AB'ONALD C.
COOK NUCLEAR PLANT SECOND TEH YEAR 1NTERVAL VALVE SUNHARY SHEET - UHlT 2 FLOM DlAGRAM: 2-5151B-2T VALVE Valve Tag Rev Type Size Actuator Coords VALVE POS1T10N Poger Safety Operation Fmction ASKE SECTlON Xl Active/
Test Test Test ReLief Class Passive Category Required Perforeed Frequency Request 2-XRV-222 3
GL 3.00 A
8/4 C
3 A
ET-XXX HOTE 3
'YES, NOTE 3
SYSTEH:
EHERGENCY DIESEL GENERATOR 'CD'OHALD C.
COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUHHARY SHEEt - UNIT 2 FLOM DIAGRAH: 2-5151D-27 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITION PoMer Safety Operation Function ASHE SECTION XI Active/
Test Test Test Relief Class Passive Category Required Performed Frequency Request 2-DG-102C 3
CK 1.50 SA 2-DG-104C 3
CK 1 ~ 50 SA 2-DG-128C 38 CK 1.00 SA 2-DG 130C 38 CK 1.00 SA 2DG140C 3
CK 050 SA 2-00-142C 3
CK
= 0.50 SA 2-DG-146C 3
CK 2.00 SA 2-DG.152C 38 CK 4.00 SA 2-DG-154C 38 CK 4.00 SA 2-OT-132-2CD 3
3H 6.00 SA 2-SV-120.CO 3
REL 0.25 SA 2-SV.139.CD 3
REL 1.00 SA H/4 0
F/4 0
C/3 C/3 F/1 F/1 A/9 D/9 C/9 E/8 H/2 8/2 0/C 0/C 0/C 0/C 0/C 3
A 3
A 3
3 3
A 3
A 3
A 0/C 3
A 0/C 3
0/C 3
A CF-1 CF-1 CF-1 CF-1 CF-1 CF.1 CF 1
CF-1 CF-1 EF-1 TF-1 Cf-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 NOTE 1
TF.1 TF-1 HO, NOTE 1
KO, NOtE 1
KO, NOTE 1,5 HO, NOTE 1,5 NO NO HO, NOTE 1
KO, NO'IE 1 ~ 5 NO, NOTE 1,5 MO, NOTE 2 NO NO 2-SV-61-CD 3
REL 1.00 2-SV-78-CD1 3
REL 1.00 SA.
SA A/8 E/3 TF.1 TF-1 HO NO 2-SV-78.C02 3
REL 1.00 SA 2.SV-79.CD1 3
REL 0.50 SA 2-SV-79.CD2 3
REL 0.50 SA D/3 E/1 E/1 TF-1 TF-1 TF-1 NO NO NO 2-XRV-225 3
GA 1 00 A
8/3 Ef.l Ef-7 ET XXX Ef-1 EF-7 NOTE 4
- YES, NOTE 4
- YES, KOTE 4
- YES, KOTE 4 2-XRV-226 3
GL 3.00 A'/4 C
3 A
Ef-1 EF 7 ET XXX Ef-1 NOTE 3 MOTE 3
- YES, MOTE 3
- YES, NOTE 3
- YES, NOTE 3 2-XRV-227 3
GL 3.00 A
8/4 C
3 A
Ef.l Ef 7 Ef-1 NOTE 3
- YES, NOTE 3
- YES, NOTE 3
SYSTEN:
EHERGEHCY DIESEL GEHERATOR 'CD'ONALD C.
COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SOHIARY SHEET - UNIT 2 FLOM DIAGRAM: 2-5151D-27 VALVE Valve Tag Rev Type Size Actuator Coords VALVE POSITION PoMer Safety Operation Fmct ion ASHE SECTION XI Active/
Test Test Test Relief Class Passive Category Required Performed Frequency Request 2-XRV-227 3
GL 3.00 A
8/4 C
3 A
ET-XXX NOTE 3 P
- YES, NOTE 3
4'- ~ ~
~4
~ ~