ML17277B277

Proposed Tech Specs Reflecting Reporting Requirements of 10CFR50.73

ML17277B277
Person / Time
Site:	Columbia
Issue date:	01/20/1984
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17277B276	List: ML17277B275 ML17277B277
References
NUDOCS 8401300236
Download: ML17277B277 (20)

Text

INDEX DEFINITIONS SECTION DEF INITIONS (Continued) PAGE 1.24 MEMBER(S) OF THE PUBLIC...... ... ....,.............. 1-4 1.25 MINIMUM CRITICAL POWER RATIO.......

1-4 RE 1.26 OFFSITE DOSE CALCULATION MANUAL..

1.27 OPERABLE " OPERABILITY... 1-4 1.28 OPERATIONAL CONDITION " CONDITION. ~ ~ ~ ~ ~ ~ ~ 1-5 1.29 PHYSICS TESTS.......... 1" 5 1.30 PRESSURE BOUNDARY LEAKAGE ~ ~ ~ ~ ~ ~ ~ ~ 1 5

1. 31 PRIMARY CONTAINMENT INTEGRITY 1-5

1. 32 PROCESS CONTROL PROGRAM.. 1" 5 1.33 PURGE - PURGING. 1-6 1.34 RATED THERMAL POWER. 1" 6 1.35 REACTOR PROTECTION SYSTEM RESPONSE TIME 1" 6 8'08uj 4CCN 1-6 1.37 ROD DENSITY 1-6

1. 38 SECONDARY CONTAINMENT INTEGRITY. 1" 6

1. 39 SHUTDOWN MARGIN. 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ 1-7 1.40 SITE BOUNDARY. 1-7

1. 41 SOLID IF ICATION. 1-7 1.42 SOURCE CHECK 1-7 1.43 STAGGERED TEST BASIS 1-7 1.44 THERMAL POWER. 1-7 1.45 TOTAL PEAKING FACTOR.

1-8 1.46 TURBINE BYPASS SYSTEM RESPONSE TIME 1-8 WASHINGTON NUCLEAR " UNIT 2 11 840i300236 840i20 PDR ADOCK 05000397 P . , PDR

IHDEX ADMINISTRATIVE CONTROLS SECTION PAGE CORPORATE NUCLEAR SAFETY REVIEW BOARD (Continued)

CONSULTANTS. 6"ll MEETING FREQUENCY..................................., 6-11 UORUMo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-11 REVI EW o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6"ll AUDITS o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6"12 R ECORDS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-12 ACTIONo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ a ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

6. 7 SAFETY LIMIT VIOLATION......,............,........ 6"13 6.8 PROCEDURES AND PROGRAMS . .. . ... ..................,. 6"14 6.9 REPORTING RE UIREMENTS 6-15 6.9. 1 ROUTINE REPORTS 6" 15 STARTUP REPORT. 6"15 ANNUAL REPORTS 6-16 MONTHLY OPERATING REPORTS. 6-16

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT...,.

6.9.2 SPECIAL REPORTS..................... 6" 19

6. 10 RECORD RETENTION. 6-21 6.11 RADIATION PROTECTION PROGRAM 6-22 6.12 HIGH RADIATION AREA. 6 23

6. 13 PROCESS CONTROL PROGRAM. . ............................ ~ 6"24 6.14 OFFSITE DOSE CALCULATION MANUAL 6-25 6.15 MAJOR CHANGES TO RADIOACTIVE LI UID GASEOUS AND SOLID WASTE TREATMENT SYSTEMS.... 6-25 WASHINGTON NUCLEAR - UNIT 2 Xix

DEFINITIONS PURGE " PURGING 1.33 PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in'such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER 1.34 RATED THERMAL POWER shall be a total reactor core heat transfer rate to

'he reactor coolant of 3323 MWt.

REACTOR PROTECTION SYSTEM RESPONSE TIME

1. 35 REACTOR PROTECTION SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until deenergization of the scram pilot valve solenoids.'he response time may be measured by any series of sequential, overlapping, or total steps such that the entire response time is measured.

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1.37 ROD DENSITY shall be the number of control rod notches inserted as a fraction of the total number oi control rod notches. All rods fully inserted is equivalent to 100K ROD DENSITY.

SECONDARY CONTAINMENT INTEGRITY 1.38 SECONDARY CONTAINMENT INTEGRITY shall exist when:

a. All secondary containment penetrations required to be closed during accident conditions are either:

1. Capable of being closed by an OPERABLE secondary containment automatic isolation system, or

2. Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position.

b. All secondary containment hatches and blowout panels are closed and sealed.

c. The standby gas treatment system is in compliance with the requirements of Specification 3.6.5.3.

WASHINGTON NUCLEAR - UNIT 2 1" 6

ADMINISTRATIVE CONTROLS RESPONSIBILITIES 6.5. 1.6 The POC shall be responsible for:

a0 Review of (1) all proposed procedures required by Specification 6.8 and changes thereto, (2) all proposed programs required by Specifica-tion 6.8 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety;

b. Review of all proposed tests and experiments that affect nuclear safety; C. Review of all proposed changes to the Appendix A Technical Specifications;

d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety;

e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence, to the Director of Power Generation and to the Corporate Nuclear Safety Review Board;

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w Review of unit operations to detect potential hazards to nuclear safety; Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant Manager or the Corporate Nuclear Safety Review Board; Review of the Security Plan and implementing procedures and submittal of recommended changes to the Corporate Nuclear Safety Review Board; and Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Corporate Nuclear Safety Review Board.

k. Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Director of Power Generation and to the Corporate Nuclear Safety Review Board.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.

AUTHORITY 6.5.1.7 The POC shall:

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a. Recommend in writing to the Plant Manager approval or disapproval of items considered under Specification 6.5. 1.6a. through d. prior to their implementation.

WASHINGTON NUCLEAR " UNIT 2 6-9

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ADMINISTRATIVE CONTROLS REVIEW (Continued)

c. Proposed tests or experiments which involve an unreviewed safety ques-tion as defined in 10 CFR 50.59;

d. Proposed changes to Technical Specifications or this Operating License;

e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; S

f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; I'0 Owb.

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QAi All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and

i. Reports and meeting minutes of the POC.

j. Audit reports and summary reports of audits.

AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the CNSRB. These audits shall encompass:

a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months;

b. The performance, training and qualifications of the entire unit staff at least once per 12 months;

c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months;

d. The performance of activities required by the Operational guality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months;

e. The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee gA personnel;

f. The Emergency Plan and implementing procedures at least once per 12 months per 10 CFR 50.54(t).

g. The Security Plan and implementing procedures at least once per 12 months'ASHINGTON NUCLEAR - UNIT 2 6-12

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h. The fire protection equipment and program implementation, at least once per l2 months utilizing either a qualified offsite licensee fire protection engineer(s} or an outside independent fire protection consultant. An outside independent fire protection consultant shall be utilized at least once every third year; and Any other area of unit operation considered appropriate by the CNSRB or the Managing Director.

J ~ The radiological environmental monitoring program and the results thereof at least once per 12 months.

k. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.

m. The performance of activities required by the guality Assurance Program for effluent and environmental monitoring at least once per 12 months.

RECORDS 6.5.2.9 Records of CNSRB activities shall be prepared, approved, and distri-buted as indicated below:

'a ~ Minutes of each CNSRB meeting shall be prepared, approved, and forwarded to the Managing Director 14 days following each meeting.

Reports of reviews encompassed by Specification 6.5.2.7 above, shall be prepared, approved, and forwarded to the Managing Director within 14 days following completion of the review.

C. Audit reports encompassed by Specification 6.5.2.8 shall be forwarded to the Managing Director and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

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Eac PORTABLE OCCURRENCE requiring 24-hour notification to the Commission reviewed by the POC, and the results of this review shall be submit e B and the Director of Power Generation.

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AOMINISTRATI VE CONTROLS 6.9 REPORTING RE UIREMENTS ROUTINE REPORTS 6,9.1 In addition to the applicable reporting requirements of. Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted.

STARTUP REPORT 6.9. 1. 1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.

6.9. 1.2 The startup report shall address each of the tests identified in the

'inal Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions. Any corrective actions that were required to obtain satisfactory opera" tion shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the startup report does not cover all three events (i. e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS" 6.9. 1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

"A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

MASHINGTON NUCLEAR " UNIT 2 6-16

ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) 6.9. 1.5 Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions" (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [describe maintenance], waste processing, and refueling).

The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totalling less than 20K of the individual total dose need not be accounted for. In the aggregate, at least 80K of the total whole-body dose received from external sources should be assigned to specific major work functions; and

b. Documentation of all challenges to main steam line safety/relief valves.

MONTHLY OPERATING REPORTS

6. 9. 1. 6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

R RTABLE OCCURRENCES 6.9. 1.7 EPORTABLE OCCURRENCES of Specifications 6.9. 1.8 and 6.9. 1.9,

, including corre 'tions reported to the NRC. Sup and measures to prevent recurrence, shall be 1 reports may be required to fully describe final resolution of occurrence. In c orrected or supplemental reports, a Licensee Event Report shall be completed and re shall be made to the original report date.

'PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9. 1.8 The of events. listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirm telegraph, mailgram, or facsimile transmission to the Regional Administrator o Regional Office of the NRC or his designee no later than the first working day owing the event, with a written followup report within 14 days. The written follow e ort shall include, as a minimum, a completed copy of a Licensee Event Report form. ormation provided on the Licensee Event Report form shall be supplemented, as nee e by additional narrative material to provide complete explanation of the circu ces surrounding the event.

"This tabulation supplements the requirements of f20.407 of 10 CFR Part 20, WASHINGTON NUCLEAR - UNIT 2 6-17

AOMINISTRATIYE CONTROLS PAO PT NOTIFICATION WITH WRITTEN FOLLOWUP (Continued) a Failure of the'eactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint ecified as the Limiting Safety System Setting in the Technical Sp ifications or failure to complete the required protective func ion.

b. Operati of the unit or affected systems when any parameter or operation subject to a Limiting Condition for Operation is less conservati than the least conservative aspect of the Limiting Condition fo Operation established in the Technical Specifications.

C. Abnormal degrada ion discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.

Reactivity anomalies nvolving disagreement with the predicted value of reactivity balance ader steady-state conditions during power opera-tion greater than or equ+1 to IX delta k/k; a calculated reactivity balance indicating a SHUTO WN MARGIN less conservative than specified in the Technical Specificat'ons; short-term reactivity increases that correspond to a reactor peri of less than 5 seconds or, if subcrit-ical, an unplanned .reactivity 'nser tion of more than 0.5X delta k/k; or occurrence of any unplanned iticality.

Failure or malfunction of one or m re components which prevents or could prevent, by itself, the fulfi lment of the functional require-ments of system(s) used to cope with ccidents analyzed in the Safety Analysis Report.

Personnel error or procedural inadequacy hich prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents alyzed in the .Safety Analysis Repor t.

g. Conditions arising from natural or man-made eve s that, as a direct result of the event, require unit shutdown, opera ion of safety systems, or other protective measures required by chnical Specifications.

Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the Safet Analysis Report or in the bases for the Technical Specifications th t have or could have permitted reactor operation in a manner less cons vative than assumed in the analyses.

WASHINGTON NUCLEAR - UNIT 2 6-18

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ADMINISTRATIVE CONTROLS PROHP NOTIFICATION WITH WRITTEN FOLLOWUP (Continued)

Perfor anc of structures, systems, or components that requires remedial actino corrective measures to prevent operation in a manner less conservative tha sumed in the accident analyses in the Safety Analysis Report or TechnicalMpecifications bases; or discovery during unit life of conditions not specifically considered in the Safety Analysis Report or Technical SpecificCCiqns that require remedial action or corrective measures to prevent %~xistence or development of an unsafe condition.

j. Failure of main steam line safety/relief valves.

T RTY DAY WRITTEN REPORTS 6.9. 1. The types of events listed below shall be the subject of written reports to the ional Administrator of the Regional Office of the NRC within 30 days of occurre e of the event. The written report shall include, as a minimum, a completed co of a Licensee Event Report form. Information provided on the Licensee Event port form shall be supplemented, as needed, by additional nar-rative material t rovide complete explanation of the circumstances surrounding the event.

a. Reactor protec 'on system or engineered safety features instrumenta-tion settings wh h are found to be less conservative than those established by the echnical Specifications but which do not prevent the fulfillment of th -functional requirements of affected systems.

b. Conditions leading to oper ion in a degraded mode permitted by a Limiting Condition for Opera ' or plant shutdown required by a Limiting Condition for Operatio C. Observed inadequacies in the impleme ation of administrative or procedural controls which threaten to use reduction of degree of redundancy provided in reactor protection ystems or engineered safety features systems.

d. Abnormal degradation of systems other than those pecified in Speci-6.9. 1.8c designed to contain radioactive teria1 resulting 'ication from the fission process.

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ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1~ Routine Radiological Environmental Operating Reports covering the operation of 'the unit during the previous calendar year shall be submitted prior .

to May 1 of each year. The'initial report shall be submitted prior to Hay 1 of the year following initial criticality.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a compar-ison with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 3. 12,2.

The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations speci-fied in the table and figures in the QDCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment branch Technical Position, Revision 1, November 1979.

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps" covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3. 12.3; discussion of all deviations from the sampling schedule of Table 3.12-1; and discussion of all analyses in which the LLD required by Table 4, 12-1 was not achievable.

"One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

, WASHINGTON NUCLEAR - UNIT 2 6-20

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ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.~ Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality.

The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,"

Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direc-tion, atmospheric stability, and precipitation (if measured), or in the form of Joint frequency distributions of wind speed, wind direction, and atmospheric stability." This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or. station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5. 1-3) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall. be used for determining the gaseous'pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The Radioactive Effluent Release Report shall also include once a year an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including

'doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1. 109, Rev. 1, October 1977.

• In lieu of submission with the first half year Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that .shall be provided to the NRC upon request.

. WASHINGTON NUCLEAR - UNIT 2 6-21

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ADMINISTRATIVE CONTROLS SEMIANNUAl. RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

e. Type of container (e.g., LSA, Type A, Type 8, Large guantity), and

f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).

The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the'and use census pursuant to Specification 3. 12. 2.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

6. 10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6. 10. 2 The following records shall be retained for at least 5 years:

a. Records and logs of unit operation covering time interval at each power level.

Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety.

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d. Records of surveillance activities, inspections, and calibrations requi r ed by these Techni cal Speci fi cati ons.

MASHINGTON NUCLEAR - UNIT 2 6-22

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