ML20137V474
| ML20137V474 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 01/22/1986 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137V449 | List: |
| References | |
| NUDOCS 8602190582 | |
| Download: ML20137V474 (21) | |
Text
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/ fog UNITED STATES NUCLEAR REGULATORY COMMISSION g
3 .E WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET N0. 50-295 ZION NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.93 License No. DPR-39
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment by Commonwealth Edison Company (the licenseri dated June 28, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate ir. confomity with the application, the provisions of the Act, and the rules and regulations of the .
Comission;
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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 sucn activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable reauirements 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-39 is hereby amended to read as follows:
8602190582 860122 PDR ADOCK 05000295 P PDR
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No. 93 , 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 COMMISSION R
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r On, Steven . Var , Director l PWR Project Directorate #3 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: January 22, 1986 l
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Sa nso ng'o,
' UNITED STATES
, g NUCLEAR REGULATORY COMMISSION
$ t WASHINGTON. D. C. 20555
's,, * . . . 4 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.83 License No. DPR-48
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
.e A. The application for amendment by Commonwealth Edison Company (the licensee) dated June 28, 1985, 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 (1) 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. OPR-48 is hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No. 83 , 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 COMMISSION
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1 n o)7CL.w, ,
Iteven A. Varga, Director w PWR Project Directorate #3 b Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: January 24,1986 e
ATTACHMENT TO LICEhSE AMENDMENTS AMENDMENT NO. 93 FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO. 83 FACILITY OPERATING LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise Appendix A as follows:
Remove Pages Insert Pages iv iv 295W 295W 295X 295X 295Y 295Y 295Z 295Z 295AA 295AA 315 315 295AA1 295AA2 295AA3 295AA4 295AA5 295AA6 295AA7 295AA8 295AA9 .
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SURVLILLANCE tlMlilNG CDN9111DN FOR OPERATION REQUIREMENT PAGE 3.13 Refueling Operations 4.13 243 3.13.1 Core Reactivity 4.13.1 243 3.13.2 Protection from Damaged Spent Fuel 4.13.2 244 3.13.3 Containment Status 4.13.3 245 3.13.4 Radiation Monitoring 4.13.4 246 3.13.5 Refueling Equipment Checkout 4.13.5 246 3.13.6 Refueling Equipment Operab111ty 4.13.6 246 3.13.7 Spent Fuel Pit Cooling Systems 4.13.7 246 3.13.8 Fuel Inspection Program 4.13.8 247 3.13.9 Residual Heat Removal System Operation 247c 3.13.10 Water Level - Reactor Vessel 247d 3.13.11 Water Level - Storage Pool 4.13.9 247a Bases 248 3.14 Plant Radiation Monitoring
- 4.14 250 Bases . 254 3.15 Auxiliary Electrical Power System 4.15 255 Bases 271 3.16 Radiological Environmental Monitoring 4.16 275 Bases 279 3.17.1 Ventilation 4.17.1 281
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3.17.2 Aircraf t Fire Detection 4.17.2 283 Bases 287 i
3.18 Steam Generator Activity 4.18 289 Bases 290 3.19 Failed fuel Monitoring 4.19 292 Bases 293 3.20 Deleted -
3.21 Fire Protection 4.21 2950 Bases 2950 3.22 Shock Suppressors (Snubbers) 4.22 295W 3.22.1 Mechanical Snubbers . 4.22.1 295W
4.22.3 295AA7 Bases 295AA8 3.23 Special Test Exceptions 4.23 295A8 i
- Bases 295AC l
4 TABLE Cf CDNTENTS (Continued) Amendment No.s 93 and 83 tv l 0872t
LIMITING CON 0!TIONS FOR OPERATION SURVE!LLANCE 4EQUIREMENT ,
3.22. Shock Suppressors (Snubbers) 4.22. Shock Suppressors (Snubbers)
- 1. Mechanical Snubbers 1. Mechanical Snubbers A. All safety related mechanical A. Each mechanical snubber shall be snubbers listed in station demonstrated OPERABLE by performance of the procedures shall be OPERABLE. following augmented inservice inspection program.
APPLICABillTY: MODES 1,2,3,4 and i 1. Visual Inspection - Mechanical Snubbers (MODES 5 and 6 for s.'ubbers located
- The visual inspection shall be on systems required OPERA 8tE in . performed in acccrdance with the those MODES.) following schedule. .
No. Inoperable Snubbers Subsequent Visual ACTIDN: per inspection Period Inspection Period *# -
0 18 months 1 25%
With one or more snubbers inoperable, within 1 12 months 1 25%
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 2 6 months 1 25%
snubber (s) to OPERABLE status and perform an 3,4 124 days 1 25%
engineering evaluation per Specification 5,6,7 62 days 1 25%
4.22.1.A.3 on the supported component or 8 or more 31 days 1 25%
declare the supported system inoperable and follow the appropriate AtilDN statement for The snubbers may be categortred into that system. two groups: Those accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the abewe schedule.
- The inspection interval shall not be lengthened more than one step at a time.
- The provisions of Specification 4.0.2 are not applicable.
0853t/0854t -
295W Amendment Nos. 93 and 83
LIMITING CONDITIONS FOR OPERAil0N SURVEILLANCE REQUIREMENT 4.22.1.A.
- 2. Visual Inspection Acceptance Criteria -
Mechanical Snubbers
! Visual inspections shall verify (1) that there are no visible indications of damage or impaired DPERABILITY, (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 OPERABl.E for the purpose of establishing the next visual inspection interval, providing i
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.
- 3. Functional Tests - Mechanical Snubbers 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) 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 4.22.1.A.4, an additional 10% of that type of snubber shall be 0853t/0854t 295X Amendment No.s 93 and 83
LIMITING Co#0!TIONS FOR OPERATION SURVEILLANCE REQUIREMENT 4.22.1.A.3. (Continued) 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:
. a. The first snubber away from each reactor vessel nozzle
- b. Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc.)
- c. Snubbers within 10 feet of the discharge from a safety relief valve Snubbers that are 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 justifiable basis for exemption is presented and/or snubber 11fe destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
Amendment Nos. 93 and 83 0853t/0854t 295Y
- g. .
e, LIMITING CON 0lilDNS FOR OPERATIDN SURVE!LLANCE REQUIREMENT 4
4.22.1.A.3. (Continued)
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.
If any snubber selected for functional testing either fails to lockup or falls 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 j
functionally tested. This testing l requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
For the snubber (s) found inoperable, an l engineering evaluation shall be i
performed on the components which are supported by the snubber (s). The purpose of this engineering evaluation shall be to determine 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.
0853t/0854t 295Z Amendment Nos. 93 and 83
LIMITING CDN01TIONS FOR OPERATION SURVE! LANCE REQUIREMENT .
4.22.1.A. (Continued)
- 4. Functional Test Acceotance Criteria -
Mechanical Snubbers The mechanical snubber functional test shall verify that:
- a. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force. Drag force shall
, not have increased more than 50% since the last functional test.
- b. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
- c. Snubber release rate, where required, is within the specified range in compression or tension. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
Amendment Nos. 93 and 83 0853t/0854t 295AA
= _ . . _._ ,
s LINITING CON 0!T10NS FOR OPERATION SURVE!LLANCE REQUIRENEN; 3.22. Shock Suppressors (Snubbers) (Continued) 4.22. Shock Suppressors (Snubbers)
- 2. Hydraulle Snubbers 2. Hydraulic Snubbers A. All safety related hydraulic A. Each hydraulic snubber shall be demonstrated snubbers listed in station OPERABLE by performance of the following procedures shall be OPERABLE. augmented inservice inspection program.
- 1. Visual Inspections - Hydraulic Snubbers APPLICA8ILITY: MODES 1,2,3,4 and 7 '
All hydraulic snubbers shall be (MODES 5 and 6 for snubbers located visually inspected in accordance with on systems required OPERABLE in '. the following schedule:
those MODES.)
No. Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period *#
ACTION: 0 18 months 1 25%
1.2 12 months 1 25%
With one or more snubbers inoperable, within 3.4 6 months 1 25%
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 5-8 124 days 1 25%
snubber (s) to OPERABLE status and perform an 9-14 62 days 1 25%
engineering evaluation per Specification 15,16 31 days 1 25%
4.22.2.A.3 on the supported component or declare the supported system inoperable and The snubbers may be categorized into follow the appropriate AC11DN statement for -
two groups: Those accessible and those that system. , 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.
- The provisions of Specification 4.0.2 are not applicable.
Amendment Nos. 93 and 83
, 0853t/0854t 295AA1 ,
LINITING CONDITIDNS FOR OPERATION SURVEILLANCE REQUIREMENT , 4.22.2.A. Hydraulic Snubbers (Continued)
- 2. Visual Inspection Acceptance Criteria -
Hydraulic Snubbers Visual inspection shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) l attachments to the foundation or l supporting structure are secure, and (3) in those locations where snubber movement can be manually induced ,
without disconnecting the snubber, that I the snubber has freedom of movement and is not frozen up. Snubbers which ,
appear inoperable as a result of visual . l Inspections may be determined OPERABLE I 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 susceptthle; and (2) the affected snubber'is functionally tested in the as found condition and determined OPERABLE. 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.
Amendment Nos. 93 and 83 0853t/0854t . 295AA2
LINITING CONDITIDMS FOR OPERATIDN SURVEILLANCE REQUIREMENT
. 4.22.2.A. (Continued)
Once each refueling cycle, a representative sample of at least 10 hydraulic snubbers shall be functionally tested for operability incluo'ing verification of proper piston movement, lock up and bleed. For each unit and subsequent unit found
. inoperable, an additional ten snubbers shall be so tested until no more failures are found or all units have been tested.
- The representative sample selected for i
functional t.esting 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
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, following three categories:
- a. The first snubber away from each reactor vessel nozzle.
- b. Snubbers within 5 feet of heavy equipment (valve, pump, turbine, 4 motor, etc.)
- c. Snubbers within 10 feet of the discharge from a safety relief valve.
Amendment Nos. 93 and 83 0853t/0854t 295AA3
LIMITING CDN0!TIONS FOR OPERAT1DN SURVEILLANCE REQUIREMENT 4.22.2.A.3. (Continued)
Snubbers that are especially difficult to remove or in high radiation zones during shutdown shall also be included in the representative sample.*
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 snobber (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.
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 1/ 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 for 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 0853t/0854t 295AA4 Amendment Nos. 93 and 83
i D
t j
LIMITING CON 0!TIONS FOR OPERATION
.t SURVEILLANCE REQUIREMENT 4.22.2.A.3. (Continued)
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by the snubber (s). The purpose of this engineering evaluation shall be to determine if the comprnents 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 j meeting the designed service.
)
- 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.
Testing Once each refueling cycle, a representative sample of at least 1 Large Bore Hydraulic Snubber shall be functionally tested for operab111ty including verification of proper piston movement, lock up and bleed.
Large bore hydraulic snubbers have rated full load capacity of greater than 50,000 lbs.
! 1he representative sample selected for -
functional testing shall be a different steam generator snubber than has been previously functionally tested during this testing cycle.
0853t/0854t 295AA5
o t -
LIMITING CONDIT10NS FOR OPERATION SURVEllLANCEREQUIREMENT 4.22.2.A.4. (Continued)
For snubber (s) found inoperable, an engineering evaluation shall be performed on components which are supported by the snubber (s). The purpose of the engineering evaluation shall be to determine if the components supported by the snubber (s) were i
adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of
, meeting the designed service.
For each unit and subsequent unit found inoperable, an additional two snubbers shall be so tested until no more failures are found or all units have been tested.
- 5. Functional Test Acceptance Criteria -
t Hydraulic Snubber The hydraulic snubber functional test shall verify that:
- a. Activation (restraining action) is achieved within the specified range of
- velocity or acceleration in both i tension and compression,
- b. Snubber bleed, or release rate, where required, is within the specified range in compression or tension. For snubbers specifically required to not displace under continuous load,the ability of the snubber to withstand load without displacement shall be verified.
0853t/0854t 295AAb L
LIMITING CDNDiflDNS FOR OPERATION SURVEILLANCE REQUIREMENT , 4.22. Shock Suppressors (Continued) 4.22. Shock Suppressors (Centinued)
- 3. Snubber Service Life Monitoring 3. Snubber Service Life Monitorina A record of the service life of each mechanical and hydraulic snubber, the date at which 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 6.5.8.16
, Concurrent with the first inservice visual
. inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.
. If the indicated 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.
0853t/0854t 295AA7 Amendment Nos. 93 and 83
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2 I Bases: 3.22 & 4.22
)
! snubbers are designed to prevent unrestrained The inspection frequency is based upon i
pipe motion under dynamic loads as might occur maintaining a constant level of snubber drring an earthquake or, for some snubbers, protection. Thus the required inspection i
ssvere transients, while allowing normal thermal interval varies inversely with the observed motion during startup and shutdown. The snubber failures. The number of inoperable tcssequences of an inoperable snubber is an snubbers found during a required inspection
! increase in the probability of structural damage determines the time interval for the next to piping as a result of a seismic event or, for required inspection. inspections performed some snubbers, other events initiating dynamic before that interval has elapsed may be used as a Icads. It is therefore required that all new reference point to determine the next
! snubbers required to protect the primary coolant inspection. However, the results of such early i system or any other safety system or component be inspections performed before the original j cp2rable during reactor operation.
, required time interval has elapsed (nominal time
! less 25%) may not be used to lengthen the
! Because the snubber protection is required required inspection interval. Any inspection
{ cnly during low probability events, a period of whose results require a shorter inspection i 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements. interval will override the previous schedule.
j in case a shutdown is required, the allowance of 4 h:urs to reach hot shutdown is consistent with To further increase the assurance of snubber 3 standard operating procedures. After a maximum reliability, functional tests should be performed of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> in hot shutdown, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is allowed once each refueling cycle. These tests will to reach cold shutdown conditions. Since plant include stroking of the snubbers to verify proper i startup should not commence with knowingly piston movement, lockup and bleed. Ten snubbers
! defective safety-related equipment, represents an adequate sample for such tests.
! Sp cifications 3.22.1 and 3.22.2 prohibit startup Observed failures on these samples should require j with inoperable snut'bers. testing of additional units. To minimize
! personnel exposures, snubbers installed in high
]
All safety related hydraulic snubbers are radiation zones during reactor shutdown or in visually inspected for overall integrity and especially difficult to remove locations may be cperability. The inspection will include exempted from these functional testing verification of proper orientation, adequate requirements provided a permanent exemption is hydraulic fluid level and proper attachment of obtained f rom the Conunission.
snubber to piping and structures.
0853t/0854t 295AA8 Amendment Nos.'93 and 83 i '
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l
- j 1
4
- Bases
- 3.22 & 4.22 (Continued)
I i Experience at operating factittles has shown Snubbers may be added to safety related that the required surveillance program should systems without prior license aumendment provided assure an acceptable level of snubber performance they are added to station procedures and prsvided that the seal materials are compatible documented in accordance with 10 CIR 50.59.
with the operating environment.
Hydraulic snubbers and mechanical snubbers j Snubbers containing seal material which has may each be treated as a different entity for the
! n t been demonstrated by operating experience, above surveillance programs.
1ab tests or analysis to be compatible with the
{ cp2 rating environment should be inspected more
- The service life of a snubber is evaluated frequently (every month) untti materials via manufacturer input and information through compatibility is confirmed or an appropriate consideration of the snubber service conditions changeout is completed. *
. and associated installation and maintenance
! records (newly installed snubber, seal replaced, ,
! Examination of defective snubbers at reactor spring replaced, in high radiation area, in high fac111 ties and material tests performed at temperature area, etc...). The requirement to soveral laboratories (Reference 1) has shown that monitor the snubber service life is included to cillable gum polyurethene deteriorates rapidly ensure that the snubbers periodically undergo a
- nder the temperature and moisture conditions performance evaluation in view of their age and l present in many snubber locations. Although operating conditions. These records will provide molded polyurethene exhibits greater resistance statistical bases for future consideration of 1
to these conditions, it.also may be unsuitable snubber service life. The requirements for the for application in the higher temperature maintenance of records and the snubber service i Environments. Data are not currently available life review are not intended to affect plant I to precisely define an upper temperature 11mit operation.
l fcr the molded polyurethene. Lab tests and
- ' in-plant experience indicate that seal materials
- are available, primarily ethylene propylene.
1 i
! (1) Report H. R. Erickson, Bergen Paterson to K. R. Goller, NRC, October 7, 1974 1
)
J Amendment Nos. 93 and 83
' 0853t/0854t 295AA9 l
e 6.5 R: cords (Continued)
- 8. Records and/or logs relative to the 10. Records of transient or operational following items shall be recorded in a cycling for those components that have manner convenient for review and shall been designed to operate safely for a be retained for the life of the plant, limited number of transient or operational cycles.
- 1. Substitution or replacement of principal items of equipment 11. Records of individual qualifications, pertaining to nuclear safety, experience, training and retraining.
- 2. Changes made to the plant as it is 12. Inservice inspections of the reactor described in the Safety Analysis coolant system.
Report.
,' 13. Minutes of meetings and results of
- 3. Records of new and spent fuel reviews performed by the off-site and inventory and assembly histories, on-site review functions.
- 4. (Deleted) 14. Records of secondary water sampling and water quality.
- 5. Updated, corrected, and as-butit drawings of the plant.
- 15. Records for Environmental Qualification
, which are covered under the provisions
- 6. Records of plant radiation and of paragraph 6.6.3.d.
contamination surveys.
7.
- 16. Records of the service lives of all Records of of f-site environmental snubbers covered by Specification 3.22 monitoring surveys. Including the date at which the service life commences and associated
- 8. Records of radiation exposure for installation and maintenance records.
all plant personnel, including all contractors and visitors to the plant in accordance with 10 CfR 20.
- 9. Records of radioactivity in liquid and gaseous wastes released to the environment.
0853t/0854t 315 Amendment Nos. 93 and 83
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