ML20114E368

From kanterella
Jump to navigation Jump to search
Amends 51 & 37 to Licenses NPF-87 & NPF-89,respectively, Revising TS to Reflect Approval for Use of New Containment Leakage Rate Testing Program
ML20114E368
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 06/13/1996
From: Polich T
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20114E371 List:
References
RTR-REGGD-01.163, RTR-REGGD-1.163 NUDOCS 9606250222
Download: ML20114E368 (18)
v • d • e


Text

_.

~

4 UNITED STATES g

I NUCLEAR REGULATORY COMMISSION l

E t!

WASHINGTON, D.C. 200SIM1001

\\p

/

TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 j

DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. NPF-87 1.

The Nuclear Regulatory Commission (the Comission) has found that:

i A.

The application for amendment by Texas Utilities Electric Company (TU Electric, the licensee) dated March 12, 1996 (TXX-96008),

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 1:

B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the ;ules 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 license 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. NPF-87 is hereby amended to read as follows:

l 9606250222 960613 PDR ADOCK 05000445 1

P PDR

- 2.

Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 51, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto,-are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of its date of issuance to be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION Timothy J. Polich, Project Man er Project Directorate IV-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 13, 1996

pun q p

k UNITED STATES j

g

,g NUCLEAR REGULATORY COMMISSION

~t WASHINGTON, D.C. 20066-0001

\\**se*/

j i

TEXAS UTILITIES ELECTRIC COMPANY l

COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 2 l

DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. NPF-89 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by Texas Utilities Electric Company (TU Electric, the licensee) dated March 12, 1996 (TXX-96008),

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; l

B.

The facility will operate in conformity with the application, as amended, the provisin".5 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 Comission's regulations; D.

The issuance of this license 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 Commission't 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. NPF-89 is hereby amended to read as follows:

l i

f

. (2) Technical Soecifications and Environmental Protection Plan 2

The Technical Specifications contained in Appendix A, as revised through Amendment No. 37, and the Environmental Protection Plan l

contained in Appendix B, are hereby incorporated into this license.

TU Electric shall operate the facility in accordance with the l

Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance to be implemented within 60 days.

l FOR THE NUCLEAR REGULATORY COMMISSION

  • Y-

\\

/

i l

himothy J. Polich, Project nager Project Directorate IV-1 Division of Reactor Projects III/IV l

Office of Nuclear Reactor Regulation i

Attachment:

Changes to the Technical 1

j Specifications Date of Issuance: June 13, 1996 l

l k

l ATTACHMENT TO LICENSE AMENDMENT NOS. 51 AND 37 FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 DOCKET NOS. 50-445 AND 50-446 l

Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change. The corresponding l

overleaf pages are also provided to maintain document completeness.

REMOVE INSERT 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3

)

3/4 6-4 3/4 6-4 3/4 6-5 3/4 6-5 3/4 6-8 3/4 6-8 8 3/4 6-1 B 3/4 6-1 6-7 6-7 6-7a i

l i

4 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY j

LIMITING CONDITION FOR OPERATION 4

3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within I hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE0VIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

At least once per 31 days by verifying that all penetrations

  • not a.

capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 2.1.1 of the Technical Requirements Manual; and l

b.

By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.

  • Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days. The blind flange on the fuel transfer canal need not be verified closed except after each drainage of the canal.

CDMANCHE PEAK - UNITS 1 AND 2 3/4 6-1 Unit 1 - Amendment No.51 Unit 2 - Amendment No.37

l CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LINITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited in accordance with the Containment Leakage Rate Testing Program (refer to Technical Specification Section 6.8.3g).

APPLICABILITY: M00ES 1, 2, 3, and 4.

ACTION:

With the measured overall integrated containment leakage rate exceeding 1.0 L, within I hour initiate action to be in HOT STANDBY within the next 6 hou,rs and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Restore the overall integrated leakage rate to less than or equal to 0.75 L combined leakage rate for all penetrations subject to Type B an$ and the C tests to less than or equal to 0.60 L, prior to increasing the Reactor, Coolant System l

l temperature above 200*F.

SURVEILLANCE REOUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the test l

schedule and shall be determined in conformance with the criteria specified in the Containment Leakage Rate Testing Program (refer to Technical Specification Section 6.8.3g), except as noted below:

i I

I l

l I

l COMANCHE PEAK - UNITS 1 AND 2 3/4 6-2 Unit 1 - Amendment No. 44,51 Unit 2 - Amendment No. 37

CONTAINMENT SYSTEMS SURVEILLANCE REOUTREMENTS (Continued) a.

Air locks shall be tested and demonstrated OPERABLE by the require-ments of Specification 4.6.1.3; b.

Containment ventilation isolation valves with resilient material l

seals shall be tested and demonstrated OPERABLE by the requirements of Specification 4.6.1.7.2 or 4.6.1.7.3, as applicable; c.

Safety injection valves 8809A, 88098, and 8840 shall be leak tested l with a gas at a pressure not less than P, 48.3 psig, or with water Containment Leakage Rate Testing f,rogram (ervals defined in the at a pressure not less than 1.1 P at int refer to Technical Specification Section 6.8.3g);

d.

Containment spray valves HV-4776, HV-4777, CT-142, and CT-145 shall l

be leak tested with water at a pressure not less than 1.1 P,, at intervals defined in the Containment Leakage Rate Testing Program (refer to Technical Specification Saction 6.8.3g); and e.

The provisions of Specification 4.0.2 are applicable only to b.

l 1

COMANCHE PEAK - UNITS 1 AND 2 3/4 6-3 Unit 1 - Amendment No. 44,51 Unit 2 - Amendment No. 37

f i

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with both doors closed l

except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a.

With one containment air lock door inoperable:

1.

Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed; 2.

Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least l

once per 31 days; 3.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; and 4.

The provisions of Specification 3.0.4 are not applicable.

b.

With the containment air lock inoperable, except as the result of an l

inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

l 1

COMANCHE PEAK - UNITS 1 AND 2 3/4 6-4 Unit 1 - Amendment No. 51 Unit 2 - Amendment No. 37

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a.

By verifying leakage rates in accordance with the Containment Leakage Rate Testing Program (refer to Technical Specification Section 6.8.3g).

b.

At least once per 6 months by verifying that only one door in each air lock can be opened at a time.

COMANCHE PEAK - UNITS 1 AND 2 3/4 6-5 Unit 1 - Amendment No. 51 Unit 2 - Amendment No. 37

CONTAINMENT SYSTEMS INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6.1.4 Primary containment internal indicated pressure shall be maintained between -0.3 psig and 1.3 psig.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.4 The primary containment internal pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

COMANCHE PEAK - UNITS 1 AND 2 3/4 6-6

CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION l

3.6.1.5 Primary containment average air temperature shall not exceed 120*F.

l APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With the containment average air temperature greater than 120*F, reduce the average air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

j,UJ.VEILLANCEREQUIREMENTS U

4.6.i.5 The primary containment average air temperature shall be the adjusted average of two temperatures at or above the following containment locations of which at icast one temperature is from location a. or above and shall be determined a t least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

Location a.

Dome, El. 1000'-6" b.

Floor, El. 860'-0" COMANCHE PEAK - UNITS 1 AND 2 3/4 6-7

~

CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.1.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With the structural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.6.1.

Containment Surfaces. The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined during shutdown by a visual inspection of these surfaces. This inspection shall be performed in accordance with the Containment Leakage Rate Testing Program (refer to Technical. Specification Section 6.8.39) to verify no apparent changes in appearance or other abnormal degradation.

4.6.1.6.2 Reports. Any abnormal degradation of the containment structure detected during the above required inspections shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2 within 15 days.

This report shall include a description of the condition of the concrete, the inspection procedure, the tolerances on cracking, and the corrective actions taken.

COMANCHE PEAK - UNITS 1 AND 2 3/4 6-8 Unit 1 - Amendment No. 51 Unit 2 - Amendment No. 37

3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAllMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the contaimeent atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restric-tion, in conjunction with the leakage rate limitation, will limit the EXCLUSION AREA BOUNDARY radiation doses to within the dose guideline values of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates, as specified in the Containment Leakage Rate Testing Program (refer to Technical Specification Section 6.8.3g),

ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, P. The overall containment measured overall integrated leakage rate is f. As an added conservatism, the leakage rate acceptance criterion is s; 1.0 L urther limited to less than or equal to 0.75 L during performance of the periodic test to account for possible degradati,n of the containment leakage barriers between leakage tests.

o I

For specific system configurations, credit may be taken for a 30-day water i

seal that will be maintained to prevent containment atmosphere leakage through the penetrations to the environment. The following is a list of the containment isolation valves that meet this system configuration and the Maximum Allowed Leakage Rate (MALR) required to maintain the water seal for 30 days.

MALR Valve No.

fec/hr) 1-8809A 77 1-88098 77 2-8809A 75 i

2-8809B 73 1-8840 2577 2-8840 2382 CT-142 4734 CT-145 4734 HV-4776 4734 HV-4777 4734 The surveillance testing for measuring leakage rates, as specified in the Containment Leakage Rate Testing Program (refer to Technical Specification Section 6.8.3g), is consistent with Reg. Guide 1.163, 1995 and the requirements of Option B of 10 CFR 50 Appendix J.

3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.

Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

COMANCHE PEAK - UNITS 1 AND 2 8 3/4 6-1 Unit 1 - Amendment No. H,51 Unit 2 - Amendment No. 37

CONTAINMENT SYSTEMS BASES 3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that:

(1) the con-tainment structure is prevented from. exceeding its design negative pressure dif-ferential of 5 psid with respect to the outside atmosphere, and (2) the contain-ment peak pressure does not exceed the design pressure of 50 psig during a LOCA.

The indicated containment pressure values of -0.3 psig and 1.3 psig corres-pond to analytical limits of -0.5 psig and 1.5 psig, respectively, with allowance for measurement uncertainty.

The maximum peak pressure expected to be obtained from a LOCA event is 48.3 psig, which is less than design pressure and is consistent with the safety analyses. This value includes the limit of 1.5 psig for initial positive containment pressure.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the over-all containment average air temperature does not exceed the initial temperature condition assumed in the safety analysis for a LOCA or steam line break accident.

The average temperature shall be by an adjusted averaging of at least 2 of the measurements made at the listed locations, by fixed or portable instruments with allowance for temperature measurement uncertainty.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 48.3 psig in the event of a LOCA. A visual inspection in conjunction with the Type A leakage tests is sufficient to demonstrate this capability.

3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The 48-inch and 12-inch containment and hydrogen purge supply and exhaust isolation valves are required to be locked closed during plant operations since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident. Maintaining these valves locked closed during plant opera-tion ensures that excessive quantities of radioactive materials will not be released via the Containment Ventilation System. To provide assurance that these containment valves cannot be inadvertently opened, the valves are locked closed in accordance with Standard Review Plan 6.2.4 which includes mechanical devices to seal or lock the valve closed, or prevents power from being supplied to the valve operator.

The use of the Containment Ventilation System during operations is restricted to the 18-inch pressure relief discharge isolatiun valves (with an effective diameter of 3 inches) since, these venting valves are capable of closing during a LOCA or steam line break accident. Therefore, the Exclusion Area dose guideline of 10 CFR 100 would not be exceeded in the event of an accident during containment venting operation.

COMANCHE PEAK - UNITS 1 AND 2 B 3/4 6-2 j

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 9)

Limitations on the annual and quarterly doses to a MEMBER OF l

THE PUBLIC from Iodine-131, Iodine-133, tritium, and all. radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR 50, and 10)

Limitations on the annual dose or dose comitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR 190.

l f.

Containment Leakaae Rate Testina Proaram l

A program shall be established to implement the leakage rate testing of the containment as required by 10CFR50.54(o) and 10CFR50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program, dated September 1995".

l The peak calculated containment internal pressure for the design basis loss of coolant accident, P,, is 48.3 psig.

The maximum allowable containment leakage rate, L, at P, shall_ be 0.10% of containment air weight per day.

1 Leakage rate acceptance criteria are:

1.

Containment leakage rate acceptance criterion is s 1.0 L Duringthefirstunitstartupfollowingtestinginaccord.ance with this program, the leakage rate acceptance criteria are s 0.60 L, for the Type B and Type C tests and s 0.75 L, for Type A tests; 2.

Air lock testing acceptance criteria are:

a)

Overall air lock leakage rate is s 0.05 L, when tested at k P,.

b)

For each door, leakage rate is s 0.01 L, when pressurized to 2 P,.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program, with the exception of the containment ventilation isolation valves, which is specified in Specification 4.6.1.7.2 and 4.6.1.7.3.

The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

COMANCHE PEAK - UNITS 1 AND 2 6-7 Unit 1 - Amendment No. 14,42,50,51 Unit 2 - Amendment No. Ge 36,37 r

l L

ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall bc submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted.

6.9.1.1 Not used.

ANNUAL REPORTS

  • 6.9.1.2 Annual Reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March I of each year. The initial report shall be submitted prior to March I of the year following initial criticality.

Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of station, utility, and other individuals (including contractors), for whom monitoring was performed, receiving an annual deep dose equivalent greater than 100 mrem and the associated collective deep dose equivalent (reported in person-rem) 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 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total deep dose equivalent received from external sources should be assigned to specific major work functions; "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.

COMANCHE PEAK - UNITS 1 AND 2 6-7a Unit 1 - Amendment No. 51 Unit 2 - Amendment No. 37

i ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) b.

The results of specific activity analyses in which the primary m lant exceeded the limits of Specification 3.4.7.

The following l

information shall be included:

(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded analysis for radiciodine perfor)med prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than i

limit.

Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; l

(4) Graph of the I-131 concentration (pCi/ge) and one other radioidine isotope concentration (pC1/ge) as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

ANNUAL RADIOLOGICAL ENVIROOMENTAL OPERATING REPORT

before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM, and (2) Sections IV.B.2, IV.B.3, and IV.S sf Appendix I to 10 CFR 50.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT" 6.9.1.4 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR 50.

MONTFLY OPERMING REPORTS 6.9.1.5 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, l

l l

  • A single submittal may be made for a multiple unit station.
    • A single submittal may be made for a multi-unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

j i

COMANCHE PEAK - UNITS 1 AND 2 6-8 Unit 1 - Amendment No. M,50 l

Unit 2 - Amendment No. M,36 l

-..

Retrieved from "https://kanterella.com/w/index.php?title=ML20114E368&oldid=4289869"