ML17325A049
| ML17325A049 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/07/1987 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17325A050 | List: |
| References | |
| NUDOCS 8704150167 | |
| Download: ML17325A049 (30) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. >o4 License No.
DPR-58 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated August 19, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the,Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common "
defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-58 is hereby amended to read as follows:
8704150167 870407 1-PDR ADOCK 05000315 P
(2)
Technical S ecifications 1 The Technical Specifications contained in Appendices A and B, as revised through Amendment No.104, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The Technical Specification changes are effective within 45 days of receipt of this amendment.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications I
Date of Issuance "P~~~
Dave L. Wigginton, Project Manager PWR Project Directorate 84 Division of PWR Licensing-A
- SEE PREVIOUS CONCURRENCE PHRS PWR-A DWigginton/rad 03/
/87 OG - ethesda U 7 03/3)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No, 9>
License No.
DPR-74 1.
The Nuclear Regulatory Comission (the ComIIission) has found that:
A.
The application for amendment by Indiana,and Michigan Electric Company (the licensee) dated August 19, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the'Act) and the Commission"s rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that, the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-74 is hereby amended to read as follows:
~
(2)
Technical,S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.9~, are hereby incorporated in the license.
The licensee shall operate. the facility in accordance with the Technical
'Specifications.
I
'3.
'The Technical Specification changes are effective within 45 days of
'eceipt of this amendment.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
AP<<>
73
>987 Dave L. Wigginton, Project Manager PWR Project Directorate 84 Division of PWR Licensing-A PWRg4/DPWR-A DWigginton/rad 03 87 PiWlg PWR A,.e'lFOB/DPWR A MUuh n
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 104FACILITY OPERATING LICENSE NO. DPR-58 AMENDMENT NO, 91 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NOS. 50-315 AND 50-316 Revise Appendix A as follows:
Remove Pa es Unit 1
3/4 7-28 3/4 7-29 3/4 7-30 3/4 7-36 3/4 7-38 B 3/4 7-6 Unit 2 3/4 7-20 3/4 7-21 3/4 7-27 3/4 7-28 3/4 7-29 3/4 7-32 B3/4 7-5 B3/4 7-6 Insert Pa es 3/4 7-28 3/4 7-29 3/4 7-30 3/4 7-30 3/4 7-38 B3/4 7-6 3/4 7-20 3/4 7-21 3/4 7-27 3/4 7-28 3/4 7-29 3/4 7-32 B3/4 7-5 B3/4 7-6
PLANT SYSTEMS
~34.7.8 4
EEEEE LIMITING CONDITION FOR OPERATION 3.7.8 All snubbers listed in Table 3.7-4 shall be OPERABLE" APPLICABILITY:
MODES 1, 2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.8.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement. for that system.
SURVEILLANCE RE UIREMENTS 4.7.8 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.*"
a.
Visual Ins ections The first inservice visual inspection of srubbers shall be per,ormed-after four months but within 10 months of commencing POMER OPERATION and shall include all snubbers listed in Table 3.7-4.
If less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months '5K from the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance with the following scheduie:
No. Inoperable Snubbers er ins ection Period 0
1 2
3,4 5,6,7 8 or more 18 month".
a 25 12 months
+ 25 6 months
+ 25 124 days z 25 62 days
+ 25 31 days
+ 25 The snubbers may be categorized into two groups:
Those accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedUle.
- The inspection interval shall not be lengthened more than one step at a time.
PThe provisions of Specification 4.0.2 are not applicable.
- The provisions of Specification 4.0.6 are applicable.
D. C. Cook Unit l 3/4 7-28 A
nd nt No. 104
I 0
K I
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued b.
Vssua Ins ection Acce tance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is func-tionally tested in the as found condition and determined OPERABLE
'er Specification 4.7.8.d.
- However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.
All snubbers connected to an
'noperable'ommon hydraulic fluid reservoir shall be counted as inoperable snubbers.
c.
Functional Tests At least once per 18 months during shutdown, a representative sample (10%) of the total of each type of snubber in use in the plant shalj be functionally tested either in place or in a bench test.
For each snubber that does not meet the functional. test acceptance criteria of Specification 4.7.8.d an additional 10% of that type of Snubber shall be functionally tested.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.
At least 25K of the snub-bers in the representative sample-shall include snubbers from the following three categories:
1.
The first snubber away from each reactor vessel nozzle 2.
Snubbers within 5 feet of heavy equipment (valve,
- pump, turbine, motor, etc.)
3.
Snubbers within 10 feet of the discharge from a safety relief valve Snubbers identified in Table 3.7-4 as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative samp'ie.*
- Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a ju&ifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at eith'er the completion of their fabrication or at a subsequent date.
D, C. Cook-Unit 1
3/4 7-29 Amendment No.
>04
D I
A,>
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued) d.
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.
If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested.
Test results of these snubbers may not be included for the re-sampling.
4 If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested.
This testing requirement shall be independent of the requirements stated above the snubbers not meeting the functional test acceptance criteria.
For the snubber(s) found inoperable, an engineering evaluation shall be performed on the components which are supported by. the snubber(s).
The purpose of this engineering evaluation shall be to determire if the components supported by the snubber(s) were adversely affected by the inoperability of the snubber(s) in order to ensure that the supported component remains capable of meeting the designed service.
H draulic Snubbers Functional Test Acce tance Criteria e.
The hydraulic snubber functional test shall verify that:
l.
Activation (restrainirg action) is achievec'ithin the specified range of velocity or acceleration in both. tension and compression.
2.
Snubber bleed, or release
- rate, where required, is within the
'specified range in compress.ion or tension.
For snubbers speci-fically required to not displace under continuous
- load, the ability of the snubber to withstand load without displacement shall be verified.
Snubber Service Life Monitorin A record of the service life of each snubber, the date at which the
~ designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.
Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Table 3.7-4 shall be reviewed to verify that the indicated service life has not been exceeded or will not 4e exceeded prior to the next scheduled snubber service life review.
If the indi-cated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review.
This-reevaluation, replacement or reconditioning shall be indicated in the records.
D.
C. Cook-Unit I 3/4 7-30 Amendment No.
>o4
n TABLE 3.7-4 SAFETY RELATED HYDRAULIC SNUBBERS*
8 SNUBBER NO.
g 44 45 HANGER MARK NO.
1-HSS-4 1-HSS-5 1-HSS-6 1-HSS-7 SYSTEM SNUBBER INSTALLED ON.
LOCATION AND ELEVATION Hain Steam Az 165 Elev.
635'etween Stm.
Gen.
No.
2 and No.
3 Main Steam Az 191'lev.
635'etween Stm.
Gen.
No.2 and No.3 Main Steam Az" 184'lev.
639'-1 1/4" Between Stm.
Gen.
No.
2 and No.
3 Main Steam Az 349 Elev.
635'ehind Stm.
Gen.
No. 1 and No.4 ACCESSIBLE OR HIGH RADIATION INACCESSIBLE ZONE NO NO NO NO ESPECIALLY DIFFICULT TO REMOVE NO NO NO NO 46 1-HSS-8 I
Hain Steam Az 356'lev.
639'-1 1/4 " Between Stm.
Gen.
No.
1 and No.
4 NO 47 49 50'1 1-GCCW-S278 1-GCCM-S309 1-GCCW-S837 1-GCCM-S838 1-GCCW-S839 Component Cooling Water Elev. 609'n CCW Pump Area Component Cooling Water Elev. 597'-1 5/8" In Passageway Near Sampling Room Aux. Bldg.
Component Cooling Mater Elev. 621'-0" In CCW Pump Area Component Cooling Water Elev. 621'-0" In CCW Pump Area I,
s
~ I Component Cooling Water Elev. 621'-0" In CCM Pump Area
'O
'NO NO NO NO NO YES NO NO NO
4 L
n TABLE 3.7-4 SAFETY RELATED HYDRAULIC SNUBBERS*
n SNUBBER NO.
I 62 I
63 HANGER HARK NO.
1-GRH-S47 1-GRH-S48 SYSTEM SNUBBER INSTALLED ON.
LOCATION AND ELEVATION Residual Heat Removal Elev. 581'n 1-W RHR Pump Room Residual Heat Removal Elev. 580'-6" In 1-W RHR Pump Room ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT INACCESSIBLE ZONE TO REMOVE NO NO 64 65 66 g
68 rt 0
o 69 70 1-GDG-S13 1-GDG-S14 1-GSI-S103 1-GSI-S128 1-GSI-S575
~ /
I 1-GSI-S657 1-GSI-S707 1-AB Emerg. Diesel Exhaust Elev. 596'-7 3/8" 1-AB Emerg. Diesel Exhaust Elev. 603'-6" Safety Injection Elev. 573'n 1-E RHR Pump Room Safety Injection Elev. 573'n 1-W RHR Pump Room Safety Injection Elev. 598'-9 3/8" Az 66'n Annulus Safety Injection Az 185'lev.
610'-0" In Annulus Safety Injection Az 228'lev.
608'-4 7/8" Behind RC Pump No.
3
'NO NO NO NO NO NO NO NO YES YES NO
s
~
~
BASES Continued 3/4.7.8 HYDRAULIC SNUBBERS The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems,.
Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.
Inspections performed before that interval has elapsed may be used as a
new reference point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 255) may not be used to lengthen the required inspection interval.
Any inspection whose results required a shorter, inspection interval will override the previous schedule.
a When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable.
Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same epvironmental conditions such as temperature, radiation, and vibration.
When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in-order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber.
The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a
significant effect or degradation on the supported component or system.
To provide assurance of snubber functional reliability, a representative sample of the installed snubber s will be functionally tested during plant shutdowns at 18 month intervals.
Observed failures of these sample snubbers shall require functional testing of additional units.
The service life of a snubber is evaluated via manufacturer's input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal
- replaced, spring replaced, in high radiation area, in high temperature
- area, etc...).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
D.
C.
COOK - UNIT 1 Amendment No.
1o4 B 3/4 7-6 All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.
'Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
z
- P J
4
PLANT SYSTEMS 3/4,7.7 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.7.1 All snubbers listed in Table 3.7-9 shall be OPERABLE.
APPL!CABl.ITY:
MODES 1, 2, 3 and 4
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those NODES).
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.7. 1.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
'SURVEILLANCE REQUIREMENTS 4.7.7. 1 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.'+*
a.
Visual Ins ection The first inservice visual inspection o;
~ snubbers shall be performed after four months but wirhin 10 months of commencing POWER OPERATION and shall include all snubbers listed in Table 3.7-9.
If less than two (2) snubbers are fourd inoperable durino the first inseyvice visual inspection, the second inservice vi.sual inspection shall be performed 12 months
+ 25~ from the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
No. Inoperable Snubbers er !ns ection Period 0
1 2
3,4 5,6,7 8 or more Subsequent Visual+¹ Ins ection Period 18 months x 25 12 months
+ 25 6 months
+ 25 124 days
+ 25 62 days s 25 31 days
+ 25 The snubbers may be categorized into two groups:
Those accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
1<<1
- ~The provisions of Specification 4.0.6 are applicable.
¹The provisions of Specification 4.0.2 are not applicable.
D. C. Cook Unit 2 3/4 7-20 Amendment No.
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS Continued b.
Visual Ins ection Acce tance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providi'ng that (1) the cause of the rejection is clearly established and remedied for that particular snubber and,for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition,and determined OPERABLE per Specification 4.7.7. l.d as applicable.
- However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.
All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.
c.
Functional Tests At least once per 18 months during shutdown, a representative sample
( 10%%d) of the total of each type of ".nubber in use in the plant shall be functionally tested either in place or in a bench test.
For each snubber that does not meet the functional :est acceptance criteria of Specification 4.7.7. 1.d an additional 10~ of that type of snubber shall be functionally tested.
The representative sample selected for functional testing shall. include the various configurations, operating environments and the range-of-size and capacity of snubbers.
At least 25%%d of the snubbers in the representative sample shall include snubbers from the following three categories:
1.
2.
3.
The first snubber away from each reactor vessel nozzle Snubbers within 5 feet of heavy equipment (valve,
- pump, turbine, motor, etc.)
Snubbers within 10 feet of the discharge from a safety relief valve Snubbers identified in Table 3.7-9 as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample.*
- Permanent or other exemptions from functional testing for individbal snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
D.
C.
COOK - UNIT 2 3/4 7-21 Amendment No. 9~
C
TAI3I.I'. 3. 7-9 SAFI:.TY REI.ATFI) IIVI)RAUI.I0 SNUIII3ERS*
P SNUBBER NO.
On 36 o
37 38 39 IIANGER HARK NO.
2-FW-S9 2-FW-S10 (L) 2-FW-S10 (U) 2-FW-Sll SYSTEM SNUBBER INSTAU.EI)
ON LOCATION AND EI.EVATION Feedwater hz 194 Elev. 629'-9" near Stm.
Gen.
No.
3 Feedwater Az 334 Elev. 634'-0" near Stm.
Gen.
No.
4 Feedwater hz 334 Elev. 636'-7" near Stm.
Gen.
No.
4
~"
Feedwater Az 330 Elev. 634'-9" near Stm.
Gen.
No.
4 ACCESS IBLI'. OR lNACCCSSIIILE IIIGH RADIATION ZONE NO NO NO NO ESPECIALLY DIFFICULT TO REMOVE NO NO NO NO 40 2-FW-S12 Feedwater Az 343o Elev. 629'-9" near Stm.
Gen.
No.
4 NO NO 41 2-GBD-S563(I.)
Stm.
Gen.
Blow</own Az 279'lev.
607'-ll" In Anhulus NO NO 42 o
43 48'-GBD-S563 (U) 2-GBD-S569 (L),
Stm.
Gen.
Blowdown Az 275 Elev. 608'-6" In Annulus Stm.
Gen.
Blowdown Az 275o Elev. 607'-ll" In Annulus A
NO NO NO NO o
44 45 2-GBD-S569(U) 2-GBD-S568 Stm.
Gen.
Blowdown Az 275 Elev. 608'-6" In Annulus Stm.
Gen.
Blowdown hz 264 Elev. 608'-1" In Annulus'
~ ~
NO NO NO NO
I
TABI.I'. 3. 7-9 SAFFTY REI.ATED HYDRAULIC SNUBBERS*
~
SNUBBER HANGER a
o NO.
HARK NO.
SYSTEH SNUBBER INSTAI.I.ED ON LOCATION AND ELEVATION ACCESSIBI.E OR INACCESSIBI.E IIIGII RADIATION ZONE ESPECIALLY DIFFICULT TO REMOVE n
C)O 46 2-GRH-S6 Residual Heat Removal Elev. 581'-6" RHR Pump Room 2E NO NO 47 48 49 50 51 52 53 54 2-GRH-S7 2-GRH-S24 2-GRH-S25 2-GCCW-S274 2-GCCW-S308 2-GCCM-S317 2-GCCM-S320 2-GCCW-S519 Residual Heat Removal Elev. 581'-3" RHR Pump Room 2E Residual Heat Removal Elev. 581'-0" RHR Pump Room 2W Residual Heat Removal Elev. 580'-6" RHR Pump Room 2M Component Cooling Water Elev. 621'-0" CCW Pump Area Component Cooling Water Elev. 610'- 1/2" CCW Pump brea Component Cooling Water Elev. 621'-0" CCM Pump brea Component Cooling Wat'er Elev. 610'-6" CCW Pump Area Component Cooling Water hz 132 Elev. 623'-4" RC Pump Area h
NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO 55 2-GCCW-S521
~I f
56
'-GCCW-S550 Component Cooling Water Az 132 Elev. 624'-9" RC Pump Area Component Cooling Water Az 308o Elev. 619'-3" RC Pump Area NO NO NO NO
t f
I Il1 hf
TABLE 3.7-9 SAFETY RELATED IIYDRAULIC SNUBBERS*
A OO SNUBBER NO.
57 58 59 60 HANGER HARK NO.
2-GCCW-S838 2-GCCW-S839 2-GCCW-S840 2-GCCW-S843 SYSTEM SNUBBER INSTALLED ON LOCATION AND ELFVATION Component Cooling Water Elev. 621'-0" CCW Pump Area Component Cooling Water Elev. 621'-0" CCW Pump Area Component Cooling Water Elev. 620'-0" CCW Pump Area Component Cooling Water Elev. 620'-5" CCW I'ump Area ACCESSIBLE OR INACCESSIBLE NIGll RADIATION ZONE NO
~
NO NO NO ESPECIALLY DIFFICULT TO REHOVE NO NO NO NO 61 62 63 2-GCCW-S306 2-GCS-S634 2-GCS-S637 Component Cooling Water Elev. 596'-2 3/8" CCW Pump Area Chem&Vol. Control Az 299o Elev. 613'-1" Inside crane wall by No.
4 RC Pump Chem&Vol. Control Az 72 Elev. 608'-10" In.Annulus NO NO NO NO NO NO 64 2-GCS-S729 Chem&Vol. Control Az 234 Elev. 617'-0" RC Pump Area NO NO 65 2-MSS-1 66 2-HSS-2 Main Steam Az So Elev. 639'-1 1/4" Between Stm.
Gen.
No.
1 and 4
Main Steam Az 17 Elev. 635'-0" Between Stm.
Gen.
No.
1 and 4
NO NO NO NO
TABLE 3.7-9 SAFETY REL'ATED 'tIYDRAULIC SNUBBERS SNUBBER HANGER NO.
MARK NO.
I g
85 2~-S116 (E)
M 86 2~-S116(W)
SYSTIM SNUBBER INSTALLED ON IDCATION AND HZVATION DÃZAINMWZSPRAY ELEV. 579'-6"2W CZS Pump Roan Suction Pipe COVZAINM1WZ SPRAY ELEV. 579'-6" 2W CIS Pump Roan Suction Pipe ACCESSIBIS OR INACCESSIBLE IIIQI RADIATION ZONE ESPECIALLY DIFFICULT
'10 R25KM" 87 N/A STEAM GREIGE'IOR NO.
1 ELEV.
665'8 N/A SZFJR GENEIQIQR NO.
1 ELEV. 665' 89 90 91 92 93
~ I N/A N/A N/A N/A N/A STEAM GENERA'IOR NO.
1 ELEV.
665'TEAM GENEI%'IOR NO.
1 ELEV.
665'TEAM GlMUR'IQR NO. 2 ELEV.
665'TEAM GENITOR NO. 2 ELEV.
665'TEAM GKEINIOR NO. 2 ELEV.
665'4 N/A STFJH GEREIR'IOR M7.
ztzv. 665'
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95 N/A STEAM GENER%'I0R NO-3 ELEV. 665'
The OPERABILITY of the ESF ventilation system ensures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment.
The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses.
All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety r elated systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.
Znspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 255) may not be used to lengthen the required inspection interval.
Any inspection whose results required a shorter inspection interval will override the previous schedule.
When the cause of the reJection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically;.
susceptible, and verified by inservice functional testing, that snubber. may be exempted from being counted as inoperable.
Generically susceptible
'snubbers are those which are of a specific make or model and have the same design features directly related to reJection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions, such as temperature, radiation, and vibration.
When a snubber is found inoperable,
'an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related comp'onent or system has been adversely affected by the inoperability of the snubber.
The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
D.
C ~
COOK - UNIT 2 B 3/4 7-5 Amendment No.
91
C" E
p 4
I
PLANT SYSTEMS To provide assurance of snubber functional reliability, a representative sample of the installed snubbexs will be functionally tested during plant shutdowns at 18 granth intervals.
Observed failures of these sample snubbers shall require functional testing of additional units.
The service life of a snubber is evaluated via manufacturer's input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc...).
The requirement to rranitor the snubber service life is included to ensure that the snubbers periodically undergo a perfonnance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
The requirements for the maintehance of records and the snubber service life review are not intended to affect plant operation.
3/4.7. 8 SEALED SOUKZ CONrANINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
This limitation will ensure tlat leakage from byproduct,
- source, and special nuclear material sources willnot exceed allowable intake values.
3/4.7.9 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occuring in any portion of the facility where safety related equiprent is located, The fire suppression system consists of the water system, spray and/or sprinklers, CO
, Palon and fire hose stations.
The collec-tive capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.
In the event that portions of the fire suppression systems axe inoperable, alternate backup fixe fighting equiprent is reouired to be made available in the affected areas until the inoperable equipnent is restored to service.
D. C.
COOK - UNIT 2 B 3/4 7-6 Amenchnent NO.