ML17325A775
| ML17325A775 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/15/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Indiana Michigan Power Co |
| Shared Package | |
| ML17325A776 | List: |
| References | |
| DPR-58-A-116, DPR-74-A-102 NUDOCS 8806220039 | |
| Download: ML17325A775 (13) | |
Text
gp,S RE0y (4
0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 i
INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT, UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
1 16 License No.
DPR-58 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applicatiori for amendment by Indiana t'ichigan Power Company (the licensee) dated July 22, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and thc Commission's rules and regulations set forth in 10 CFR Chapter I; R.
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 vIith 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; arid 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.
8806>200~9 0gg5 PDR
- DOCK 050 PDR P
2 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:
Technical S ecifications The Technical Specifications contained in Appendices A and S, as revised through Amendment No. i 1 6
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY CObNISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 15'988 Project Directorate III-I Division of Reactor Projects - III, IV, V 5 Special Projects
gpss Rf~
4+
J o
DQ
+n
~O
"+*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA YiICHIGAN POttIER COYiPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT, UNIT NO.
2 ANENDIIENT TO FACILITY OPERATING LICENSE Amendment No.
102 License No.
DPR-74 1.
The Nuclear Regulatory COIrII.ission (the Commission) has found that:
A.
D.
The application for amendment by Indiaria Yichigan Power Company (the licensee) dated July 22, 1987, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of'he Commission; 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 ComIission's regulations; 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 amerIdment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2 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:
Technical
~S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 102
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY CONYiISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 15r 1988 8
Daniel R. Huller, Acting Director PAW Project Directorate III-1 Division of Reactor Projects - III, IV, V 8 Special Projects
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT N0.116 FACILITY OPERATING LICENSE NO.
DPR-58 AMENDMENT N0.102 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKETS NOS, 50-315 AND 50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE 3/4 7-28 3/4 7-29 B 3/4 7-5 B 3/4 7-6 3/4 7-20 3/4 7-21 B 3/4 7-5 B 3/4 7-6 UNIT I UNIT 2 INSERT 3/4 7-28 3/4 7-29 B 3/4 7-5 B 3/4 7-6 3/4 7-20 3/4 7-21 B 3/4 7-5 B 3/4 7-6
PLANT SYSTBlS 3 4.7.8 SNUBBERS LIHITING CONOITION FOR OPERATION 3.7.8 All snubbers listed in Table 3.7-4 shall be OPERABLE APPLICABILITY:
NOOES 1, 2, 3 and 4.
(HOOES 5 and 6 for snubbers located on systems required OPERABLE in those HOOES).
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 SpeciPication 4.0.5.**
a.
Visual Insoecticns The first inservice visual inspection of snubbers shall be performed after four montns but within 10 months cf ccmmencing POWER OPERATION and shall Include a1!
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
~
25% from the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance with :he following schedule:
No. Inoperable Snubbers er nspection Period Subsequent Yisual Inspection Period*4 0
1 2
3,4 5,6,7 8 or more 18 month" 12 months 6 months 124 days 62 days 31 days
+ 25' 25~
~ 25~
+
25'5<
+ 25~
The snubbers mav 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.O.2 are not applicable.
- The provisions of Specification 4.0.6 are applicable.
D. C. Cook Unit 1 3/4 7-28 Amendment No'HR i116
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued Visua Ins ection Acce tance Criteria Visual inspections shall verify (I) 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 (I) 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 per 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 inoperable common hydraulic fluid reservoir shall be counted as inoperab',e snubbers.
c.
Functional Tests At least cree per 24 months during shutdown, a representative sample of the total of each type of snubber in use in the plant shall be functinnally tested either ir. 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 shal'l 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:
I.
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 sample."
- Permanent or other exemptions from functional testing for individual 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.
0, C. Cook-Unit I 3/4 7-29 Amendment No. 7H, 116
PLANT SYSTEMS BASES 3/4.7.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room emergency ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistertwith the requirements of General besign Criteria 10 of Appendix "A", 10 CFR 50.
3/4.7.6 ESF VENTILATION SYSTEM The OPERABILITY of the ESF ventilation system ensures that radio-active 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.
3/4. 7. 7 SEALED SOURCE CONTAMINATION The limitations on sealed sour'ce removable contamination ensure that the total body or individual organ irradiation does not exceed allowable limits in the event of ingestion or inhalation of the probable leakage from the source material.
The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
guantities of interest to this specification which are exempt from the leakage testing are consistent with the criteria of 10 CFR Parts
- 30. 11-20 and
- 70. 19.
Leakage from sources excluded from the requirements of this specification is not likely to represent more than one maximum permissible body burden for total body irradiation if the source material is inhaled or ingested.
3/4.7.8 HYDRAULIC SNUBBERS 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.
D.C.
COOK-UNIT 1
B 3/4 7-5 Amendment No115
BASKS Continued The visual inspection frequency is based upon maintaining a constant lcvcl 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 25$ ) may not be used to lengthen the required inspection interval.
Any inspection whose results required a shorter inspection interval wi 11 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 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 snubbers will be functionally tested during plant shutdowns at 24 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.
The number of snubbers to be functionally tested during each surveillance is based on calculations performed to allow extension of the surveillance interval from 18 months to 24 months, and therefore, the number of snubbers functionally tested deviates from the number required by the westinghouse Standard Technical Specifications (NUREG-0452, Revision 4).
D. C.
COOK - UNIT 1 B 3/4 7-6 Amendment No. lgf, 116
PLANT SYSTEHS 3/4.7. 7 SNUBBERS LIMITING CONOITION FOR OPERATION 3.7.7.1 All snubbers listed in Table 3.7-9 shall be OPERABLE.
APPLICABLITY:
NODES I, 2, 3 and 4
(HOOES 5 and 6 for snubbers located on systems required OPERABLE in those NOOES).
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 suppor ted component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SllRVEILLANCE RE UIREHENTS 4.7.7.1 Each snubber shall be demonstrated OPERABLE by performance of the fo11owirg augmented inservice inspection program and the requirements of
-Specification 4.0.5.~>>
Visual Inspection The first inservice visual inspection of snubbers shall be perfor.,ed after four months but within IO months of ccnmencing POWER OPERATION ard shall include all snubbers listed in Table 3.7-9.
If less than two (2) snubbers are found inoperable during the first inservice visual inspec;ion,
- he second inservice vis.al inspection shall be performed 12 months
+ 25".
rom the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance wi;h the follow ng schedule:
No.
Inoper ble Srubbers
~er Insoecti"n Pe. '.'od Subsequent V';sual,>
Insoection Period 0
1 2
3,4 5,6,7 B or more 18 months l2 months 6 months 124 days 62 days 31 days
= 25~
= 25~
= 25~
+ 25L
+ 25~
~ 25~
The. snubbers may be c tegorized into two groups:
Those accessible and those inaccessible "uring reactor operation.
Each group may be inspected independently
'.n accordance with the above schedule.
Th i p>>
f 11.
b 1
g d <<p
- The provisions of Specification 4.0.6 are applicable.
~The provisions of Specification 4.0.2 are not applicable.
D., C. Cook Unit 2 3/4 7-20 Amendment No. (g, 102
PLANT SYSTEMS SURV'EILLANCE REQUIREMENTS Continued b.
Visual Ins ection Acceptance Criteria c ~
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 clear'iy 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 ".nubber 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.
Functional Tests At least once per 24 months during shutdown, a representative sample (14')
of the total of each type of snubber 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 test acceptance criteria of Specification <,7.7,1.d an additional 10-'f 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" 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 Oifficult to Remove" or in "High Radiation lones Ouring Shutdown" shall also be included in the representative sample.+
"Permanent or other exemptions from functional testing for individual 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.
+ The provisions of Specification 4.0.7 are applicable.
0.
C.
COOK - UNIT 2 3/4 7-21 Amendment No.PH 102
The OPERLBILITT of the ESF ventilation system ensures that radioactive materials leaking from the ECCS equipment within the pump r'oom 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 related systems is maintained during and following a seismic or'ther event initiating dynamic loads.
Snubber s 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 requir'ed inspection interval var ies inversely with the observed snubber failures and is determined by the number of inoper able 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 or iginal required time interval has elapsed (nominal time less 25$ ) may not be used to lengthen the required inspection interval.
Any inspection whose results required a shorter inspection interval will over ride 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 ver ified 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, r adiation, 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 pravide assurance of snubber functional reliability, a representative san@le of the installed snubbers will be functionally'ested during plant shutdowns at 24 rmnth intervals.
Observed failures of these sample snubtmrs shall require functional testing of additional units.
D.
C.
COOK UNIT 2 B 3/4 7-5 Amendment No. 97
~ service life of a snubber is evaluated via manufacturer's input and infazmation 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...).
'Ifm requirarent to janitor the snubber service life is included to ensure that &~ snubbers periodically undergo a perfozaance evaluation in view of their age and operating conditions.
'Ihese records will provide statistical bases for future consideration of snubber service life. ~ requireaants for the maintenance of records and the snubber service life review are not intended to affect plant operation.
The number of snubbers,to be functionally tested during each surveillance is based on calculations Performed to allow extension of the surveillance interval from 18 months to 24 months, and therefore, the number of snubbers functionally tested deviates from the number required by the Westinghouse Standard Technical Specifications (NUREG-0452, Revision 4).
1 3/4. 7. 8 SEALED SOURCE CCVFA~iBlATICH The limitations on ranovable contanunation for sources requiring leak testing, including alpha emitters, is based on 10 ~ 70.39(c) limits for plutonium.
This limitation will ensure tlat leakage frcxn byprcduct,
- source, and special nuclear material sources will rot exceed allowable intake values.
3/4.7.9 FIRE SUPPRESSION SY~
The OPERABILITY'f the fire suporession systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurri>g in any portion of the facility where safety related equipnent is located.
The fire suppression system consists of De water system, spray and/or sprinklers, CO2, Halon and fire hose stations.
The collec-tive capability of the fire suppression systems is adequate to nlinimize potential Chnage to safety related equiprent and is a major element in the facility fire protection program.
In the event that portions of the fire suppression systems are inoperable, alUmmte backup fire fighting equipnent is required to be made available in the affected areas until the inoperable equipnant is restored to service.
D, C.
QOGK - UNIT 2 B 3/4 7-6 hmendnant NO.
H1 ~