ML13316B055

Amend 105 to License DPR-13,revising Tech Specs to Be Consistent W/Recent Util Organizational Changes & Recent 10CFR50 NRC Correspondence Requirements

ML13316B055
Person / Time
Site:	San Onofre
Issue date:	08/03/1988
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML13316B054	List: ML13316B052 ML13316B055 ML13316B056
References
DPR-13-A-105, TAC-54700, TAC-54701, TAC-66164 NUDOCS 8808240075
Download: ML13316B055 (24)

Text

p4 ftEGo o1 UNITED STATES 0

NUCLEAR REGULATORY COMMISSION O

WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 105 License No. DPR-13

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Southern California Edison Company and San Diego Gas and Electric Company (the licensee) dated August 27, 1987 complies with the standards and require ments of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's regulations set forth in 10 CFR Chapter 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

PDRADOCKo5OO 6

I P)

-2

2. Accordingly, the license is amended by changes to the Technical Speci fications as indicated in the attachment to this license amendment, and paragraph 3.B. of Provisional Operating License No. DPR-13 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 105, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the T thdical Specifications, except where otherwise stated in specific license conditions.

3. This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.

FOR THE NUCLEAR REGU TORY COMISSION orge

. Knighton irector Project Directora e V Division of Reactor Projects -

III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: August 3, 1988

ATTACHMENT TO LICENSE AMENDMENT NO. 105 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 33s 33s 33v 33v 39o 39o 39p 39p 39r 39r 39s 39s 39t 39t 39w 39w 39x 39x 39dd 39dd 39ee 39ee 39ff 39ff 46e 46e 60k1 60kl 60s 60s 60cc 60cc 6-4 6-4 6-15 6-15 6-19 6-19 6-26 6-26 6-37 6-37

-33s 3.5.8 RADIOACTIVE LIOUID EFFLUENT INSTRUMENTATION APPLICABILITY:

During releases via this pathway.

OEU

Monitor and control radioactive liquid effluent releases.

SPECIFICATION: A. The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.5.8.1 shall be OPERABLE With their alarm/trip setpoints set to ensure that the limits of Specification 3.15.1 are not exceeded.

B. Action

1. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of 3.15.1 are met, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

2. Hith less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.5.8.1. If the inoperable instruments remain inoperable for greater than 30 days, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

3. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases.

The alarm/trip setpoints for these instruments are calculated in accordance with methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

Amendment No. 70 00 1E

33v 3.5.9 RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION APPLICABILITY:

During releases via this pathway.

OBJECTIVE:

Monitor and control radioactive gaseous releases.

SPECIFICATION:

A. The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 3.5.9.1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.16.1 are not exceeded.

B. ACTION

1. Hith a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of 3.16.1 are met, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

2. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.5.9.1. If the inoperable instruments remain inoperable for greater than 30 days, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

3. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

BASIS:

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive material in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments are calculated in accordance with methods in the 0DCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

Amendment No.

19 0 105

39o 3.15.2 LIQUID EFFLUENT DOSE APPLICABILITY:

At all times.

OBJECTIVE:

Maintain the release of radioactive liquid effluents from the site as low as is reasonably achievable.

SPECIFICATION: A. The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (see Figure 5.1-1) shall be limited:

1. During any calendar quarter to 1 1.5 mrem to the total body and to j 5 mrem to any organ, and

2. During any calendar year to 1 3 mrem to the total body and to j 10 mrem to any organ.

B. Action:

1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

2. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

DAMI:

This specification is provided to implement the requirements of Section II.A and IV.A of Appendix I, 10 CFR Part 50.

Specification A implements the guides set forth in Section II.A of Appendix I. Specification B provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable."

Amendment No. 70,00,01, 105

-39p 3.15.3 LIOUID WASTE TREATMENT APPLICABILITY:

At all times.

OBJECTIVE:

Maintain radioactive releases from the site as low as is reasonable achievable by use of the liquid radwaste treatment system.

SPECIFICATION: A. The liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose due to the liquid effluent from San Onofre Unit 1, to UNRESTRICTED AREAS (see Figure 5.1-1) would exceed 0.06 arem to the total body or 0.2 mrem to any organ in a 31 day period.

B. Action:

1. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

a. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems and the reason for inoperability.

b. Action(s) taken to restore the inoperable equipment to OPERABLE status.

c. Summary description of action(s) taken to prevent a recurrence.

2. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

DAMI:

The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonable achievable." This specification implements the requirements of 10 CFR Part 50.36a and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

Amendment No. 70,00,01 105

39r 3.16.2 DOSE. NOBLE GASES APPLICABILITY: At all times.

OBJECTIVE:

Maintain the dose due to noble gases in gaseous effluents as low as is reasonable achievable.

SPECIFICATION:

A. The air dose due to noble gases released in gaseous effluents, from San Onofre Unit I to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

1. During any calendar quarter: 1 5 mrad for gamma radiation and s 10 mrad for beta radiation.

2. During any calendar year:.1 10 mrad for gamma radiation and 1 20 mrad for beta radiation.

B. Action:

1. Hith the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and-the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

2. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

BASIS:

This specification is provided to implement the requirements of Section II.B and IV.A of Appendix I, 10 CFR Part 50.

Specification A implements the guides set forth in Section II.8 of Appendix I. Specification B provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonable achievable."

Amendment No. 70,00,91, 105 T

39s 3.16.3 DOSE. IODINE-131. IODINE-133. TRITIUM AND RADIONUCLIDES IN PARTICJLATE f 9M APPLICABILITY:

At all times.

OBJECTIVE:

Maintain the dose due to radiolodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents as low as is reasonable achievable.

SPECIFICATION: A. The dose to a MEMBER OF THE PUBLIC from 1-131. 1-133, from tritium and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from San Onofre Unit 1 to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

1. During any calendar quarter:.1 7.5 arem to any organ; and

2. During any calendar year: 1 15 mrem to any organ.

B. Action:

1. With the calculated dose from the release of 1-131, 1-133, tritium and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

2. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

AMS:

This specification is provided to implement the requirements of Sections II.C and IV.A of Appendix I, 10 CFR Part 50.

Specification A is the guide set forth in Section II.C of Appendix I. Specification B provides the required operating flexibility and at the same time implements the guides set forth in Section IV.a of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept *as low as is reasonable achievable."

Amendment No. 10,00,91, 105

-39t 3.16.4 GASEOUS RADHASTE TREATMENT APPLICABILITY:

At all times.

OBJECTIVE:

Maintain radioactive gaseous releases from the site as low as is reasonable achievable by use of the GASEOUS RADNASTE and VENTILATION EXHAUST TREATMENT SYSTEMS.

SPECIFICATION:

A. The GASEOUS RADNASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from San Onofre Unit I to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) would exceed 0.2 arad for gamma radiation and 0.4 arad for beta radiation over 31 days. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from San Onofre Unit I to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) would exceed 0.3 mrem to any organ over 31 days.

B.

Action:

1. Hith gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:

a. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems and the reasons for the inoperability.

b. Action(s) taken to restore the inoperable equipment to OPERABLE status.

c. Summary description of action(s) taken to prevent a recurrence.

2. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

BASIS:

The OPERABILITY of the GASEOUS RADHASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensurers that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the Amendment No. 70,00,01, 105

3.17 0

APPLICABILIT:

At all times.

OBJECIVyE:

Maintain the dose due to the release of radioactive materials O V within specified limits.

SPECIFICATION:

A. The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation, from uranium fuel cycle sources shall be limited to j 25 arem to the total body or any organ (except the thyroidwhich shall be limited to j 75.rem).

B. Action:

1. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.15.2.A, 3.16.2.A or 3.16.3.A, calculations should be made to determine whether the above limits of Specification 3.17 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases, to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. The Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190.

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

2. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

lasis: This specification is provided to meet the reporting requirements of 40 CFR 190. In complying vith 40 CFR 190, nuclear fuel cycle facilities over five miles avay are not considered to contribute to the dose assessment.

Amendment No.

0*

105

39x 3.18 RADIOLOGIaL ENVIRONMENTAL MONITORING 3.18.1 MONITORING PROGRAM APPLICABILllY:

At all times.

QBJECTIVE:

Monitor exposure pathways for radiation and radioactive material.

SPECIFICATION: A. The radiological environmental monitoring program shall be conducted as specified in Table 3.18.1.

B.

Action:

1. With the radiological environmental monitoring program not being conducted as specified in Table 3.18.1, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

2. With the level of radioactivity as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Table 3.18.2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter a Special Report pursuant to Specification 6.9.2. When more than one of the radionuclides in Table 3.18.2 are detected in the sampling medium, this report shall be submitted if:

concentration (1)

+ concentration (2)

+...

1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.18.2 are detected and are the result of plant effluents, this report-shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 3.15.2. 3.16.2 and 3.16.3. This report is not required if the measured level of radioactivity was not the result of plant effluents:

however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

3. With fresh leafy vegetable samples or fleshy vegetable samples unavailable from one or more of the sample locations required by Table 3.18.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Amendment No. 70,01, 105

39dd 3.18.2 LAND USE CENSUS APPLICABILITY: At all times.

OBJECTIVE:

Monitor the UNRESTRICTED AREAS surrounding the site for potential changes to the radiological monitoring program as necessary.

SPECIFICATIQM: A. A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden* of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance.of five miles.

B. Action:

1. With the land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.6.3, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the new locations. Identify the new locations in the next Semiannual Radioactive Effluent Release Report.

2. With a land use census identifying a location(s) which yields a calculated dose or dose commitment via the same exposure pathway 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.18.1, prepare and submit to the Commission within 30 days.

pursuant to Specification 6.9.2, a Special Report which identifies the new locations. The new location shall be added to the radiological environmental monitoring program within 30 days. The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment via the same exposure pathway may be deleted from this monitoring program after October 31, of the year in which this land use census was conducted.

• Broad leaf vegetation sampling may be performed at the SITE BOUNDARY in the direction section with the highest D/Q in lieu of the garden census.

Amendment No. 70,01, 105

39ee

3.

The Provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

Bsis:

This specification Is Provided to ensure that changes in the ase of UNRESTRICTED AREASare identified and that modifications to the sonitoring program are made if required by the results of this census.

The best survey information from the door-to-door, serial or consulting with local agricultural authorities shall be used.

This census satisfies the requirements of Section IV.3.3 of osendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 500 square feet provides assurance that significant esosure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to Produce the quantity (25 g/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumotion by a child. To determine this minemue garden size, the Yollowing assuntions were used, (1) that 20 of the garden was used for growing broad leaf vegetation (i.e.. similar to lettuce and cabbage),

and (2) a vegetation yield of 2 kg/quare meter.

3.18.3 INTERLABORATORY COMPARISON PEOGRAM APPLICABILITY:

At all times.

QBJECINE:

To ensure laboratory analysis of radiological environmental monitoring samples is correct and accurate.

SPECIFICATION: A. Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

S. Action:

1. With analyses not being performed as required above.

report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

2. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

BASIS:

The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

Amendment No. ),9;',

105

-39ff 3.19 SOLID RADIOACTIVE WASTE APPLICABILITY:

At all times.

OBJECTIVE:

Ensure meeting the requirements for the SOLIDIFICATION and shipment of solid radwaste.

SPECIFICATION: A. The solid radwaste system shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping burial ground requirements.

B. Action:

1. With the provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site.

2. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

BASIS:

This specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/liquid/

solidification/agent/catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.

Amendment No. 1,00, 105

• H' 46e 9

T (22,000 - F2 )

(F I - F)/TL where F = measured actuator force from the first Hot SIS test during the current surveillance test (lbf)

F = measured actuator force from the second HOT SIS test during the current surveillance test (lbf)

TL

• time (in days) since the last surveillance testing F.

the actuator force from the previous surveillance test (lbf)*

If the calculated value of T does not exceed 92 days.

the next surveillance test must be performed before T days had elapsed.

c.

If the measured actuator force of either KV-851 A or 8 is greater than 22,000 lbf, the valve(s) shall be declared inoperable. The test results shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2 along with proposed corrective actions and NRC approval obtained prior to returning the unit to service.

2.

The first test shall be performed not less than 14 days nor more than 21 days following return to power from the current outage which began September 3, 1981.

• For the first surveillance test, the value of F shall be the average actuator force of HV-851 A&B valves from pre-operation testing (3135 lbf). All subsequent surveillance testing shall assume the F2 value from the previous surveillance test for each valve. If an F2 was not required during the previous surveillance test, the F1 value fOr each valve shall be assumed.

Amendment No. 57,42, 105

60K-1 For the snubber(s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber(s).

The purpose of this engineering evaluation shall be to 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.

D. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:

1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression;

2. Snubber bleed, or release rate, where required, is within the specified range in 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.

E. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:

1. The force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel;

2. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression;

3. 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.

F. Snubber Service Life Monitoring A record of the service life Df each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.

Concurrent with the first in-service visual inspection and at least once per refueling cycle shutdown 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 Amendment No. (t GY, 105

60-S

b. No more than 3 of the tubes inspected exceed the plugging limit, plant operation may resume after performance of the corrective action in Specification F.

4. If, in the inspections performed under Specification B,

a. More than 10% of the total tubes inspected are degraded tubes that were not classified as degraded tubes during the previous inspections or have previously detected imperfections.that have increased more than 10% wall penetration, or

b. More than 3 of the tubes inspected exceed the plugging limit, prior to resumption of plant operation the situation shall be reported in a Special Report to the Commission in accordance with Technical Specification 6.9.2 for approval of the proposed remedial action.

S. The results of inspections performed under specifications A or B for all tubes in service which have defects below the uppermost one inch of tube roll expansion shall be reported to the Commission in a Special Report pursuant to Technical Specification 6.9.2 at least seven days prior to the resumption of plant operation. The report shall include:

a. Identification of applicable tubes, and

b. Location and size of the degradation.

6. If in the inspections performed under Specification C.1. wear rates are observed at AVB intersections which are inconsistent with the 501 plugging criterion, prior to resumption of plant opeat16n the situation shall be reported in a Special Report to the Commission in accordance with Technical Specification 6.9.2 for approval of the proposed remedial action.

7. If in the inspections performed under Specification C.2 progression of the denting process is observed to be recurring, prior to resumption of plant operation the situation shall be reported in a Special Report to the Commission in accordance with Technical Specification 6.9.2 for approval of the proposed remedial action.

Amendment No.

105

60cc 4.19 SOLID RADIOACTIVE WASTE APPLICABILITY:

At all times.

OBJECTIVE:

Ensure meeting the requirements for the SOLIDIFICATION and shipment of solid radvaste.

SPECIFICATION:

The PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of-Wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions).

ACTION:

a.

If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION.

SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.

b.

If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three conse cutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste.

BASIS:

This specification implements the requirements of 10 CFR Part 5O.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH. wastelliquid/solidifica tion agent/catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.

Amendment No. 10,105

1) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight (shift turnover and meal time are not included when calculating hours worked).

2) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period (shift turnover and meal time are not included when calculating hours worked).

3) A break (the time an individual leaves the work location to the time an individual returns to the work location) of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods (shift turnover time is not included when calculating the break.; meal time is not included when calculating the break, unless it represents an administrative entry on the timesheet and not extra hours spent at the work location).

4) Except during extended shutdown periods, overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Station Manager, or by the Responsible Station Division Manager, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Station Manager or his designee to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

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b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d. Proposed changes in 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.

f. Significant operating abnormalities or deviation from normal and expected performance of unit equipment that affect nuclear safety.

g. All REPORTABLE EVENTS.

h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems or components that could affect nuclear safety.

i. Reports and meeting minutes of the Onsite Review Committee.

AUDIT 6.5.3.5 Audits of unit activities shall be performed under the cognizance of the NSG. These audits shall encompass:

a. The conformance of unit operation to the 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 the 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 the activities required by the Quality Assurance Program to meet the criteria of Appendix "B",

10 CFR 50, at least once per 24 months.

e. Any other area of unit operation considered appropriate by the Nuclear Safety Group or the Vice President and Site Manager, Nuclear Generation Site.

SAN ONOFRE - UNIT 1 6-15 Amendment No. 00,01,105

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures* shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

i. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15, Revision 1, February 1979.

J. "Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls and Quality Assurance," June 14, 1977, as specified in Section 6 of the Fire Protection Safety Evaluation Report dated July 19, 1979.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be approved by the Vice President and Site Manager, Nuclear Generation Site; or by (1) the Station Manager; or by (2) the Responsible Station Division Manager; or by (3)

Congnizant Managers reporting directly to them as previously designated by the Vice President and Site Manager, Nuclear Generation Site, prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.

b. The change is approved by two members of the site/station management staff exercising responsibility in the specific area and unit or units addressed by the change, and at least one of whom holds a Senior Reactor Operator's License on the unit affected.

Procedures and administrative policies shall meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18.7-1976, Admisistrative Controls for Nuclear Power Plants.

SAN ONOFRE - UNIT 1 6-19 Amendment No.6,79, 105

MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to pressurizer safety and relief valves, shall be submitted to the Nuclear Regulatory Commission on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Nuclear Regulatory Commission within the time period specified for each report.

SAN ONOFRE - UNIT 1 6-26 Amendment No. 0 97,94,105

A 12-foot ID reinforced concrete conduit is connected horizontally to the shoreward side of the discharge structure. This conduit is buried beneath the ocean bottom, with a minimum of 4 feet of sand cover over its top and 4 feet of rock surrounding the discharge structure. All sand and rock cover was placed so as to approximate the local ocean bottom profile.

The water travels through the discharge conduit with a design velocity of 6.9 feet per second and exits with a vertical velocity of about 2.5 feet per second. The vertical orientation creates a single orifice jet diffuser which entrains surrounding cooler water and assists in rapid diminution of the discharge temperature.

About seven minutes is required for water to travel from the condensers to the end of the discharge.

c. Land Management The facility occupies about 16 acres of the 84 acre site.

No use of herbicides is practiced to manage vegetation along the transmission line except in isolated cases to meet property owners' requests or permit stipulations from public agencies. Standard erosion control measures are used to minimize erosion at the facility, at tower sites, and along access roads.

REPORTS 6.16.2 The following reports shall be submitted pursuant to Specification 6.9.2.

a. A report shall be made to the NRC prior to implementation of a change in plant design, in plant operation, or in procedures described in Section 6.16.1 if the change would have a significant adverse effect on the environment or involves an environmental matter or question not previously reviewed and evaluated by the NRC. The report shall include a description and evaluation of the change and a supporting benefit-cost analysis.

b. Unusual or Important Environmental Events Any occurrence of an unusual or important event that indicates or could result in significant environmental impact causally related to station operation shall be recorded and promptly reported to the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> followed by a written report within 30 days.

No routine monitoring programs are required to implement this condition.

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