Text

Proposed Revs to Tech Spec 4.8.1.1.2.C to Determine Operability of Diesel Generator Should Diesel Fuel Oil Fail to Meet Test for Insolubles & Proposed Revs to Section 6 Re Organizational Changes
	ML20081B573
Person / Time
Site:	San Onofre
Issue date:	03/07/1984
From:	; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML13305A539	List: ML13305A537; ML20081B564; ML20081B573; ML20081B579; ML20081B591;
References
	TAC-54698, TAC-54699, TAC-54700, TAC-54701, TAC-61516, TAC-61517, NUDOCS 8403090230
	Download: ML20081B573 (115)
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ELECTRICAL POWER SYSTEM SURVEILLANCE REQUIREMENTS (Continued) b.

Demonstratad OPERABLE at least once per 18 months during shutoown by l

transferring (manually and automatically) unit power supply from the normal circuit to the alternate circuit.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a.

In accordance with the frequency specified in Table 4.8-1 on a STAGGERED TEST BASIS by:

1.

Verifying the fuel level in the day fuel tank, 2.

Verifying the fuel level in the fuel storage tank, 3.

Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank, 4.

Verifying the diesel starts from ambient condition and accelerates to at least 900 rps in less than or equal to 10 seconds. The generator voltage and frequency shall be 4360 2 436 volts and 60 2 1.2 Hz within 10 seconds after the start signal. The diesel generator shall be started for this -

test by using the manual start signal.

5.

Verifying the generator is synchronized, loaded to greater than

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or equal to 4700 kw in less than or equal to 77 seconds, and operates with a load greater than or equal to 4700 kw for at least an additional 60 minutes, and 6.

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

b.

At least once per 31 days and after each operation of the diesel where the period of operation was greater than or equal to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months by checking for and removing accumulated water from the day tank.

c.

At least once per 92 days and from new fuel oil prior to addition to the storage tanks by verifying that a sample obtained in accordance witn ASTM-0270-1975 has a water and sedhnt content of less than or equal to.05 volume percent and a kinematic viscosity 040*C of greater than or equal to 1.9 but less than or equal ts 4.1 when tested in accordance with ASTM-0975-77, and an impurity level of less than 2 og of insolubles per 100 al. when tested in accordance with ASTM-02274-70.

d.

At least once per 18 months during shutdown by:

1.

Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of stanoby service.

2.

Verifying the generator capability to reject a load of greater than or equal to 655.7 kw while maintaining voltage at 4360 : 436 volts and frequency at 60 ; 6.0 Hz.

SAN ONOFRE-UNIT 2 3/4 8-3 8403090230 840307 DR ADOCK 05000361 PDR

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SURVEILLANCE REQUIREMENTS (Continued) b.

Demonstrated OPERABLE at least once per 18 months during shutdown by transferring (manually and automatically) unit power supply from the normal circuit to the alternate circuit.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a.

In accordance with the frequency specified in Table 4.8-1 on a STAGGERED TEST BASIS by:

1.

Verifying the fuel level in the day fuel tank, 2.

Verifying the fuel level in the fuel storage tank, 3.

Verifying the fuel transfe pump can be started and transfers fuel from the storage system to the day tank, 4.

Verifying the diesel starts from ambient condition and accelerates to at least 900 rpm in less than or equal to 10 seconds. The generator va3tage; and frequency shall be 4360 1 436 volts and 60 1 1.2 Mr within 10 seconds after the start signal. The diesel generator shall be started for this test by using the manual start signal.

5.

Verifying the generator is synchronized, loaded to greater than or equal to 4700 kw in less than or equal to 77 seconds, and operates with a load greater than or equal to 4700 kw for at least an additional 60 minutes, and

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6.

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

b.

At least once per 31 days and after each operation of the diesel where the period of operation was greater than or equal to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months by checking for and removing accumulated water from the day tank.

c.

At least once per 92 days and from new fuel oil prior to addition to the storage tanks by verifying that a sample obtained in accordance with ASTM-0270-1915 has a water and sediment content of less than or equal to.05 volume percent and kinematic viscosity 0400C of greater than or equal to 1.9 but less than or equal to 4.1 when tested in accordance with ASTM-0975-77, and an impurity level of less than 2 mg of insolubles per 100 ml. when tested in accorda.nce with ASTM-02274-70. A diesel tenerator is not considered inoperable on the basis of fuel oil failure to meet the 2 mg of insolubles per 100 m1 limit provided that within 14 days, fuel quality can be demonstrated to be within this limit.

d.

At least once per 18 months during shutdown by:

1.

Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's reconnendations for this class of standby service.

2..

Verifying the generator capability to reject a load of greater than or equal to 655.7 kw while maintaining voltage at 4360 1 436 volts and frequency at 60 1 6.0 Hr.

SAN ON0FRE-UNIT 2 3/4 8-3

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ELECTRICAL POWER SYSTEM SURVEILLANCE REQUIRENENT5 (Continued) b.

Demonstrated OPERA 8tE at least once per 18 months during shutdown by transferring (manually and automatically) unit power supply from the normal circuit to the alternate circuit.

l 4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a.

In accordance with the frequency specified in Table 4.8-1 on a 1

STAGGERED TEST BASIS by:

1.

Verifying the fuel level in the day fuel tank, 2.

Verifying the fuel level in the fuel storage tank, 3.

Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank, 4.

Verifying the diesel starts from ambient condition and accelerates to at least 900 rps in less than or equal to 10 seconds. The generator voltage and frequency shall be 4360 2 436 volts and 60 t 1.2 Hz within 10 seconds after the start signal. The diesel generator shall be started for this test by using the manual start signal.

5.

Verifying the generator is synchronized, loaded to greater than t

or equal to 4700 kw in less than or equal to 77 seconds, and operates with a load greater than or equal to 4700 kw for at least an additional 60 minutes, and 6.

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

b.

At least once per 31 days and after each operation of the diesel where the period of operation was greater than or equal to I hour by checking for and removing accumulated water from the day tank.

At least once per 92 days and from new fuel oil prior to addition to c.

the storage tanks by verifying that a sample obtained in accordance with ASTM-D270-1975 has a water and sediment content o'f less than or i

equal to.05 volume percent and a kinematic viscosity 940*C of greater than or equal to 1.9 but less than or equal to 4.1 when tasted in accordance with ASTM-D975-77, and an impurity level of less than 2 og of insolubles per 100 al. when tested in accordance with ASTM-D2274-70.

f d.

At least once per 18 months during shutdown by:

1.

Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.

2.

Verifying the generator capability to reject a load of greater

l.

than or equal to 655.7 kw while maintaining voltage at 4360 1 436 volts and frequency at 60 3 6.0 Hz.

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SAN ON0FRE-UNIT 3 3/4 8-3

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ELECTRICAL POWER SYSTEM SURVEILLANCE REQUIREMENTS (Continued) b.

Demonstrated OPERA 8tE at least once per 18 months during shutdown by transferring (manually and automatically) unit power supply from the normal circuit to the alternate circuit.

4. 8.1.1. 2 Each diesel generator shall be demonstrated OPERABLE:

a.

In accordance with the frequency specified in Table 4.8-1 aon a STAGGERED TEST SASIS by:

1.

Verifying the fuel level in the day fuel tank, 2.

Verifying the fuel level in the fuel storage tank, 3.

Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank, 4.

Verifying the diesel starts from ambient condition and accelerates to at least 900 rps in less than or equal to 10 seconds. The generator voltage, and frequency shall be 4360 1 436 volts and 60 1 1.2 Hz within 10 secondr after the start signal. The diesel generator shall be started for this test by using the manual start signal.

5..

Verifying the generator is synchronized, loaded to greater than or equa'l to 4700 kw in less than or equsi to 77 seconds, and operates with a load greater than or equal to 4700 kw for at least an additional 60 minutes, and 6.

Verifying the diesel generator is aligred to provide standby power to the associated emergency busses, b.

At least once per 31 day's and after each operation of the diesel where the period of operation was greater than or equal to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months by checking for and removing accumulated water from the day tank.

c.

'At least once per 92 days and from new fuel oil prior to addition to the storage tanks by verifying that a sample obtained in accordance with ASTM-0270-1975 has a water and sediment content of less than or equal to.05 volume percent and kinematic viscosity 9400C of greater than or equal to 1.9 but less than or equal to 4.1 when tested in accordance with ASTM-b975-77, and an impurity level of less than 2 mg of insolubles per 100 ml. when tested in accordance with ASTM-02274-70. A diesel generator is not considered

' inoperable on the basis of fuel oil failure to meet the 2 mg of insolubles per 100 m1 limit provided that within 14 days, fuel quality can be demonstrated to be within this limit.

d.

At'least once per 18 months during shutdown by:

1.

Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.

2.

Verifying the generator capability to reject a load of greater than or equal to 655.7 kw while maintaining voltage at 4360 1 436 volts and frequency at 60 1 6.0 Hz.

SAN ON0FRE-UNIT 3 3/4 8-3

1 DESCRIPTION OF PROPOSED CIW GES NPF-10-83 AND NPF-15-83 AND S P ETY ANALYSIS This is a request to revise conpany and site organization illustrated in Figures 6.2-1 and 6.2-2 of the Technical Specifications of Facility Operating Licenses NPF-10 and NPF-15, and modify the text of Section 6.0 -

Administrative Controls to reflect these changes as well as make other minor revisions and clarifications to incorporate NRC guidance on new reporting requirements.

Existing Te&nical Specifications Unit 2 See Attachment A Unit 3 See Atta& ment B Proposed Technical. Specifications Unit 2 & Unit 3 See Attachment C Description In general, these changes revise section 6 - Administrative Controls of San Onofre Nuclear Generating Station Units 2 and 3 Operating License Appendix A Technical Specifications to reflect changes in organization structure which will consolidate and increase executive level attention and oversight of all nuclear activities.

In additicn to revising the structure of the organization and associated review and approval responsibilities, incorporation of new NRC reporting requirements and minor clarification of Section 6 requirements are also included.

A sunnary of each change 'is provided as follows:

TE3NICAL

. SPECIFICATION SECTION CIW CE SUMtRRY 1.26 Definition of REPORIABLE OCCURRENCE revised per Generic Letter 83-43.

6.1.2 shift Supervisor revised to Shift Superintendent and Manager, Nuclear Operations revised to Vice President and Site Manager, Nuclear Generation Site.

6.2.2.e Shift Supervisor revised to Shift Superintendent.

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Fig. 6.2-1 & 6.2-2 Revised to reflect the new organization structure, able 6.2-1 Revised to reflect the existence of a common control room'and recognition of shift Superintendent and Control Room Supervisor as titles of responsible individuals.

Fig. 6.2-3 Revised Shift Supervisors office to Shift Superintendents office and added the Operaticns g

Support Office to the Control Room Area.

6.2.4 Shift Supervisor revised to Shift Superintendent 6.5.1.6.b

' Revised per Generic Letter 83-43

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6.5.1.7.b Revised Manager, Nuclear Operations to Vice President and Site Manager, Nuclear Generation Site.

6.5.2.4 Revised review responsibility of 6.5.2.1 through 6.5.2.3 activities.

6.5.2.5 Revised wording of review responsibility for proposed tests and experiments.

'6.5.2.6 Revised review and approval authority of the Station Security Plan and its iglementing procedures and added reference to 10 CFR review requirement 6.5.2.7 Revised review and approval authority of the Station Emergency Plan and its iglementing procedures and added ref rence to 10 CFR review requirement

. 6.5.2.8 Revised Manager, Nuclear Operations to Vice President and Site Manager, Nuclear Generation Site.

6.5.2.9 Revised review and approval authority of the PCP, radwaste treatment pystem changes and the ODCM.

6.5.2.10:

Deleted requirement for publishing reports of review

~ activities since each review is individually documented for the record.

6.5.3.4.g Revised per Generic Letter 83-43 6.5.3.5.e Revised Manager, Nuclear Operations to Vice President and Site Manager, Nuclear Generation Site.

6.5.3.6 Revised Manager, Nuclear Engineering and Safety to Manager, Nuclear Safety.

t 6.6 Revised per Generic Letter 83-43 6.7.1.a Revised Manager, Nuclear Operations to Vice 6.7.1.c President and Site Manager, Nuclear Generation Site and revised NSG Chairman to NSG Supervisor.

6.8.2 & 6.8.3 Revised program and procedure review and approval authority consistent with new organization.

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~3-1 6.9 Revised per Generic Letter 83-43.

6.9.1.7 Revised to reflect actual practice.

6.9.1.8 Revised to allow additional time for preparation of 6.9.1.9 Radioactive Effluent Release Report to ensure l

accuracy and cowleteness. Redundancy to ODCM has been removed.

6.9.1.10 Clarified safety valve challenges to be reported, added diesel generator failures and corrected reference to review and acceptance of major changes to radioactive waste treatment system.

6.9.1.11 (Old) 6.9.1.12 (Old)

Deleted per Generic Letter 83-43 6.9.1.13 (Old) 6.9.1.14 (Old)

Renumbered to 6.9.1.11 6.9.1.12 (New)

Added per IUREG-0737, Item II.K.3.17 6.9.2 Clarified Special Reporting requirements 6.10.1.c Revised per Generic Letter 83-43 6.13.2.1 Corrected reference to PCP change acceptance 6.13.2.1.c consistent with current review and approval process.

6.13.2.2 6.14.2.1.c Corrected reference to ODCM change acceptance 6.14.2.2 consistent with current review and approval process.

6.15.1.1 Corrected reference to Major Radwaste Treatment 6.15.1.1.h' System change acceptance consistent with, current G.15.1.2 review and approval process.

In addition, as a result of the revisions to NRC reporting requirements outlined in Generic Mtter 83-43, the fo11cwing specific Limiting Condition for Operation Action Statements are to be revised for consistency with the above changes.

SECTION 3/4 PAGE NO.

I40 NO.

U2 U3 DESCRIPTION 3.3.3.8 3-63 3-64 Deleted reference to 6.9.1.13.b in Action (c) 3.3.3.9 3-68 3-69 Deleted reference to 6.9.1.13.b in Action (c) 3.4.7 4-24 4-25 Reportable Occurrence changed to SPECIAL REPORT in 30 days pursuant to 6.9.2.

SECTION 3/4 PAGE NO.

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U2 U3 DESCRIPTION 3.8.1.1 8-06 8-06 Corrected reference to diesel generator failure reporting requirement.

3.11.1.2 11-5 N/A Deleted reference to 6.9.1.13.b in Action (b).

3.12.1 12-1 12-1 Replaced reference to 6.9.1.13 with reference to 6.9.2.

Safety Analysis 2 e proposed changes discussed above shall be deemed to constitute a significant hazard consideration if there is a positive finding in any of the following areas.

1.

Will operation of the facility in accordance with these proposed danges involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No 2 ese proposed changes are administrative in nature and do not affect any physical aspect of the plant. Functions performed by the organization will be essentially the same before and after these changes.

2.

Will operation of the facility in accordance with these proposed

&anges create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: tb 2e proposed changes are administrative in nature and do not affect any physical aspect of the plant. Functions performed by the organizations will be essentially the sa:ae before and after the proposed changes.

3.

Will operation of the facility in accordance with these proposed changes involve a significant reduction in a margin of safety?

Response: No h e proposed changes are administrative in nature and do not affect any physical aspect of the plant. Functions performed by the organizations will be essentially the same before and after the proposed danges.

D

5-l Safety and Significant Hazards Determination Based on the above discussion, Proposed Changes NPF-10-83 and IPF-15-83 do not involve a significant hazards consideration in that they do not:

(1) involve a significant increase in the probability or consegaences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident fror any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. In addition, it is concluded that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by.the proposed change; and (2) this action will not result in a condition which significantly alters the impact of the station on the environment as described in the NRC Final Environmental Statement.

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ATIAODGNP A EXISTING TBOMICAL SPECIFICATIONS W ONTRE NUCLEAR GENERATING STATION - UNIT 2 4

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I ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Statira Manager shall be responsible for overall unit operation sad shall delegate in writing the succession to this responsibility during his absence.

6.1. 2 The Shift Supervisor (or during his absence from the Control Room Area,

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a designated individual) shall be responsible for the Control Room command function. A management directive to this effect, signed by the Vice-President of Nuclear Operations shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization fo'r unit management and technical support shall be as shown in Figure 6.2-1.

UNIT STAFF 6.2.2 The Unit organization shall be as shown in Figure 6.2-2 and:

a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown irt Table 5.2-1.

b.

At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room area identified as such on Table 6.2-1.

A health physics technician # shall be on site when fuel is in the c.

reactor.

d.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

A site Fire Bgigade of at least 5 members shall be maintained onsite e.

at all times.

The Fire Brigade shall not include the Shift Super-visor and the 2 other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

ThehealthphysicstechnicianandFireBrigadecompositionmaybelessbanthe minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence provided immediate action is taken to fill the required positions, t

SAN ONOFRE-flNIT 2 6-1 Amendment No. 4 JULi6ISE2

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CHAIRMAN OF THE BOARD I'

SENIOR V8CE PREEMENT I

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l VICE PR DENT vlCE PREstDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PREllDENT INUCLEAR ENGINEERING ISYSTEM (ENGINEERING &

(ADVANCED (FUEL SUPPLYi

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8 LY)

AND OPE RATIONSI DEVELOPMENT)

CONSTRUCTICNI ENGINEERING) 1 MANAGEROF MANAGER OF MANAGER OF MANAGER OF NUCLEAR ENGINEERING.

NUCLEAR ENvlRONMENTAL ENGINEERING SAFETY & LICENSING OPERATIONS AF F AIRS DESIGN DIRECTOR OF M ANMeE R.

TRAINING RESEARCH AND

- QUALITY MANAGER DEVELOPMENT ASSURANCh MANAGER PROJECT MANAGER MANAGER.

Uk NVCLEAR LICEk21tiG ENGINEE ING &

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SAN ONOFRE-UNIT 2 6-3 Amendenent No. 4 JUL 16 ILE:

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Table 6.2-1 MINIMUM SHIFT CREW COMPOSITION POSITION NUM ER OF INDIVIDUALS REQUIRED TO' FILL POSITION MODES 1, 2, 3 4 4 MODES 5 & 6 55 1

1 SRO 1

None RO 2

1 A0 2

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None Shift Supervisor with a Senior Reactor Operators License on l

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Individual with a senior Reactor Operators License on Unit 2 SRO Individual with a Reactor Operators License on Unit 2 RO Auxiliary Operator AD Shift Technica? Advisor STA Except for the Shift Supervisor, the Shift Crew Cosposition say be one less l

than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in ot4er to accommodate unexpected absence of on-duty shift crew i

l members provided immediate action is taken to restore the Shift Crew Composi-tion to within the minimum requirements of Table 6.2-1.

This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the Shift Supervisor from the Control Room Area shown in l

Figure 6.2-3 while the unit is in MODE 1, 2, 3.or 4, an individual (other than l

the Shift Technical Advisor) with a valid SRO license shall be designated to l

assume the Cor. trol Room command function. During any absence of the Shift l

Supervisor from the Control Room Area shown in Figure 6.2-3 while the unit is I

in MODE 5 or 6, en individual with a valid SRO or R0 license shall be designated to assume the Control Room command function.

3 5AN ONOFRE-UNIT 2 6-4 JUL 16 082

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ADMINISTRATIVE CONTROLS I

I 6.2.3 INDEPENDENT SAFETY ENGINEERI':G GROUP (ISEG)

FUNCTION 6.2.3.1 The ISEG shall functior, to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources of plant design and operating experience inforsation which may indics,te areas for improving plant safety.

COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five dedicated full-time Each shall have a Bachelor's Degree in Engineering or Physical engineers.

Science or equivalent and at least two years professional level experience in his field. Off-duty q'ualified Shift Technical Advisors may be used to fulfill this requirement.

RESPONSIBILITIES The ISEG shall be responsible for maintaining surveillance of plant' 6.2.3.3 activities to provide independent verification

that these activities are performed correctly and that human errors are reduced as much as practical, AUTHORITY The ISEG shall make detailed recommendations for revised procedures, 6.2.3.4 equipment modifications, maintenance activities, operations activities or other means of improving plant safety to the Supervisor, Nuclear Safety Group.

RECORDS 6.2.3.5 Records of activities performed by the ISEG shall be prepared, maintained, and forwarded each calendar month to the NSG Supervisor.

6.2.4 SHIFT TECHNICAL ADVISOR The Shift Technical Advisor shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.

The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a ' scientific or engineering discipline with specific training in plant design and in the response and analysis of the plant for transients and accidents.

6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum-qualifications of ANSI N18.1-1971 for comparable positions, except for the Health Physics Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

, Not responsible for sign-off function.

SAN ONiiRE* UNIT 2 6-5 Amendent No. 15

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l ADMINISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for.the unit staff shall be maintained under the direction of the Manager, Nuclear Training and shall meet or exceed the requirements and recommendations of Sections 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental-requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience identified by the ISEG.

6.5 REVIEW AND AUDIT 6.5.1 ONSITE REVIEW COM ITTEE (OSRC)

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FUNCTION 6.5.1.1 The Onsite Review Committee shall function to advise the Station Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Onsite Review Committee shall be composed of the:

Chairman:

Station Manager

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Member:

Deputy Station Manager Member:

Manager, Operations Member:

Manager, Technical Member:

Plant Superintendent SONGS Unit 2 & 3 Member:

Supervisor of I&C Member:

Manager, Health Physics l

Member:

Supervisor of Chemistry Member:

Manager, Maintenaace l

Member:

Supervising Engineer (NSSS, NSSS Support, Computer, or STA)

Member:

SanDiegoGas&ggectric' Representative.

Senior Engineer ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the 0SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in OSRC activities at any one time.

(1385 degree in Engineering or Physical Science plus at least four years professional level experience in his field. At least one of the four years experience shall be nuclear power plant experier.ce.

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SAN ONOFRE-UNIT 2 6-6 Amendment No. 4 h.:. b C

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ADMINISTRATIVE CONTROLS a

MEETING FRIOUENCY N,,

s 6.5.1.4 The 05RC shall meet at least once per calendar month and as convened by the 05RC Chaimen or his designated., alternate.

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6.5.1.5 The minimum quorum of the 05RC necessary for the perfomance of the 03RC responsibility and authority provisions of these Technical Specifications sl shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES t

6.5.1.6 The Onsite Review Committee shall be responsible for:

a.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluetion and recommendations to pesvent recurrence to the Nuclear Safety Group (NSG).

b.-

Review of events requiring 24-hour written notification to the Ccesission.

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c.

Review of unit epe?ations to detect potential nuclear safety hazards.

d.

Performer:a.of special reviews,. investigations or analyses and reports trereo') as requested by the Station Manager or the NSG.

Review an'd 'docsmentation of judgment concerning prolonged operation in e.

bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last 05RC meeting.

s f.

Review and approval of using and entering values of CPC addressable constants outside the allowable range of Tacle 2.2-2.

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%r 1 -7 SAN ON0FRE-UNIT 2 6

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ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The Onsite Review Cosmittee (DSRC) shall:

I Render determinations in writing with regard to whether or not itees a.

considered under 6.5.1.6(a) above constitute unreviewed safety questions.

b.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Manager of Nuclear Operations and NSG of disagreement between the 05RC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS I

6.5.1.8 The Onsite Review Committee shall maintain written minutes of each 05RC meeting that, at a minimum, document the results of all 05RC activitien b

performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the Nuclear Safety Group.

6.5.2 TECHNICAL REVIEW AND CONTROL ACTIVITIES

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6.5.2.1 The Station Manager shall assure that each procedure and program.

required by Specification 6.8 and other procedures which affect nuclear safety, g

and changes thereto, is prepared by a qualified individual / organization. Each such procedure, and changes thereto, shall be reviewed by an individual / group r

other than the individual /groupswhich prepared the procedure, or changes thereto, 7

but who may be from the same organization as the individual / group which prepared

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the procedure, or changes thereto.

f 6.5.2.2 Proposed changes to the Appendix "A" Technical Specifications shall be prepared by a qualified indiv'idual/ organization. The preparation of each proposee Technical Specifications change shall be reviewed by an individual /

group other than the individual / group which prepared the proposed change, but m

who may be from the same organization as the individual / group which prepared g._

the proposed change.' Proposed changes to the Technical Specifications shall be approved by the Station Manager.

g 6.5.2.3 Proposed modifications to unit nuclear safety-related structures, i

systems and components shall t* designed by a qualified individual /

h organization. Each such modification shall be reviewed by ar. individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modifi-cation. Proposed modifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by the Station Manager; or by the Manager, Technical as previously designated by the Station Manager.

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Amendment No. 4

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SAN ON0FRE-UNIT 2 6-8 JUL16 b.

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ADMINISTRATIVE CONTROLS ACTIVIT ES (Continued) 6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5.2.2 and 6.5.2.3 shall be members of the station supervisory staff, previously designated by the Station Manager to perfors such reviews.

Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary. If deemed necessary, such review shall be performed.by the appropriate designated review personnel.

6.5.2.5-Proposed tests and experiments which affect station nuclear safety s

and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager, the Manager Technical, the Manager, Operations, the Manager, Maintenance, the Deputy Station Manager or the Manager, Health Physics as previously designated by the Station Manager.

6.5.2.6 Thestationsecuritypr$ gram,andimplementingprocedures,shallbe reviewed at least once per 12 months. Recommended changes shall be approved by the Station Mnager and transmitted to the Manager of Nuclear Operations and tr the NSG.

6.5.2.7, The station emergency plan, and implementing procedures, shall be reviewed at least once per 12 months. Recosunended changes shall be approved

'by the Station Manager and transmitted to the Manager of Nuclear Operations and to the N5G.

~6.S.2.8 The f.tation Manage

s%11 assure the performance of a review by a qualified indiviaval/organitation of every unplanned onsite r:1 case of 'adio-active material te the environs-including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Manager of Nuclear Operations and to the NSG.

6.5.2.9. The Statirsn Manager; shall assure the performance of a review by a qualifien. individual / organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOIE CALCULATIW MANUAL. and rc1 waste treacaent systems.

6.5.2.10 Peports documenting each of the activities performed under Specifications 6.5.2.1 through 6.5.2.9 shall be maintained. Copies shall be provided to the Manager of Nuclear Operations and the Nuclear Safety i

Group.

6.5.3 NUCLEAR SAFETY GROUP (NSG)

FUNCTION

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6.5.3.1 The Nuclear Safety GrouiJ shall function to provide independent review and audit of designatad activities in the areas of:

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SAN ONOFRE-UNIT 2 6-9 Amendment No. 4

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ADMINISTRATIVE CONTROLS FUNCTION (Continued) 7 a.

nuclear power plant operations b.

nuc1sar engineering chemistry and radioc'hemistry c.

a d.

metallurgy.

k a

e.

instrumentation and control 9

f.

radiological safety g.

mechanical and electrical engineering g

h.

quality assurance practices j

COMPOSITION 6.5.3.2 NSG shall consist of'a Supervisor and at least three staff specialists.

The Supervisor shall have a Bachelor's Degree in Engineering or Physical Science and a minimum of six years of professional level managerial experience in the power *fiele. Each staff specialist shall have a Bachelor's Degree in Engineer-ing or Physical Science and a minimum of five years.of professional levc1 experience in the field of his specialty.

The NSG shall use specialists from other technical organizations to augment its expertise in the disciplines of 6.5.2.1.

Such specialists shall meet the san,e qualification requirements as the NSG members.

4 CONSULTANT $

6.5.3.3 Consultants shall be utilized as determined by the NSG Supervisor te provide expert advice to the NSG.

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E REVIEW 6.5.3.4 The NSG shall review:

j a.

The safety evaluations for 1) changes to procedures required by g

Specification 6.8, equipment or systems and 2) tests or experiments m

completed under the provi_sion of Section 50.59, 10 CFR, to verify that j

such actions did not cor,$titute in unreviewed safety question.

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Proposed changes to procedures, equipment or systems which involve-q an unreviewed safety :;uestion as defined in Section 50.53, 10 CFR. 3 c.

Proposed tests or experiments which involve an unreviewed safety T5 question as defined in Section 50.59, 10 CFR. 1 5

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henknt No. 4 SAN ONOFRE-UNIT 2 6-10 Jill 16 82 3

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ADMitc57RATIVE CotiTROLS

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l d.

Proposed changes to Technical Specifications or this Operating l

License.

l Violations of codes, regulations, orders, Technical Specifications, e,

license requirements, or of internal procedures or instructions having nuclear safety significance.

I f.

Significant c;erating abnormalities or deviations from' normal and expected performance of unit equipment that affect nuclear safety.

g.

Events requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months written notification to the Commission.

h.

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

Reports and meetings mirtutes of the Onsite Review Committee.

AUDITS 6.5.3.5 Audits of unit activities shall be performed under the ccgnizanca of the N5G. These audits shall encompass:

The conformance of unit operation tb provisions contained with'en the a.

Technical Specificatiens and applicable license conditions at least once per 12 months.

b.

The performance, training and qualifications of tie entire unit staff at least cnce per.12 months.

The results of actions taken to correct deficienciis occurring in c.

unit equipment, structures, systems or method of operation that affect nuclear safety at leart once per 6 months.

d.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",

10 CFR 50, at least once per 24 months.

i Any other area of unit operaticn considered appropriate by the e.

Nuclear Safety Group or Manager of Nuclear Operations.

l f.

The Fire Protaction Program and implementing procedures at least j

i once per 24 months.

i An independent fire protection and loss prevention inspection and

'j g.

audit shall be performed annually utilizing either qualified'offsite licensee personnel or an outs,ide fire protection firm.

i h.

An inspection and audit of the fire protection and loss preventien pregram shall be performed by an outside qualified fire c:nsultant i

at intervals no greater than 3 years.

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MAY 1 6 W AMEtGtEriT t0. 16 SA'i ONCFRE-Uti!T 2 6.n

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't g4INISTRATIVECONTROLS I

AUTi40RITY

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The NSG shall report to and advise the Manager, Nuclear Engineering 6.5.3.6 and Safety on those areas of responsibility specified in Sections 6.5.3.4 and 6.5.3.5.

RECORDS Records of NSG activities shall be prepared and maintained! Report

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6.5.3.7 of reviews and audits shall be distributed monthly to the Station Manager and to the management positions responsible for the areas audited.

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SAN CNOFRE-UNIT 2 6-12 AMEN '4E"i NO.15

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ADMINISTRATIVE CONTROLS 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The followig actions shall be taken for REPORTABLE OCCL'RRENCES:

a.

The Commission shall be notified and/or a twport submitted pursuant to the requirements of Specification 6.9.

b.

Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Commission sna11 be reviewed by the 05RC end suositted to the NSG and the Manager of Nuclear Operations.

6.7 5AFETY LIMIT V10LAT10N 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephona as soon as possible and in all cases within one hour. The Manager of Nuclear Operations and the NSG Chairman shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

- A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the 05RC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

c.

The Safety Limit Violation Report shall be submitted to the Commission, the Manager of Nuclear Operations and the NSG within 14 days of the violation.

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

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

a.

The applicable procedures reconnended 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.

SAN ON0FRE-UNIT 2 6-13 9 i ' 13 0

ADMINISTRATIVE CONTROLS

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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 Rev.1, February 1979.

j.

Modification of Core Protection Calculator (CPC) Addressable Constants.

NOTE: Modification to the CPC addressable constants based on information obtained through the Plant Computer - CPC data link shall not be made without prior approval of the Onsite Review Committee.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be approved by the Station Manager; or by (1) the Manager, Operations (2) the Manager, Technical (3) the Manager, Maintenance, (4) the Deputy Station Manager, or (5) the Manager, Health Physics as previously designated by the Station Manager; 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.

s b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

The change is documented, reviewed and approved by the Station c.

Manager; or by (1) the Deputy Station Manager, (2) the Manager, Operations, (3) the Manager, Maintenance, (4) the Manager, Technical, or (5) the Manager, Health Physics as previously designated by the Station Manager; within 14 days of implementation.

6.8.4 The following programs shall be established, implemented, and maintained:

a.

Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the high pres,sure safety injection recirculation, the shutdown cooling system, the ' reactor coolant sampling system (post-accident sampling piping only), the containment spray system, the radioactive waste gas system (post-acci, dent sampling return piping only) and the liquid radwaste system (post-accident sampling l

return piping only). The program shall include the following:

l (1) Preventive maintenance and periodic visual inspection requiremer.ts, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

"See Specification 6.13.1 MAY 16 583 SAN ONOFRE-UNIT 2 6-14 AMENDMENT NO. 16

A_n'Ul;!STRATXVE CONTROLS

,b.

Ir.-Plant Radiation Vor.itorino

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A program which will ensure the capa::ility to accur:.tely determine the airborne iodine concentratier, in vital at:-as under accident conditions. This program shall include the following:

(i) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for caintenance of sampling and analysis equipment.

c.

Secondary Water Chemistry A program for monitoring cf secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

(i) Identification of a sampling schedule for the critical variables and control points for these variables, (ii) Identification of the procedures used to measure the values of the critical variables, (iii) Identification of process sampling points, including monitoring the discharge of the condensate pumps for evidence of c3ndenser in-leakage, (iv) Procedures for the recording and mana;e=ent of data, (v) Procedures defining corrective actions for all off-control point chemistry conditions, and (vi). A precedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

. d.

Post-Accident Samplino A program

which will ensure the capability to obtain and analyze reactor cociant, radioactive iodines and particulates in plant gaseous effluents, and c'6ntainment atmosphera samples under accident conditions. The program

shall include the training of personnel, the procedures for sampling and analysis and the provisions for maintenanc,e of sampling and analysis equ,ipment.

6. 9 REPORTIt!G REQUIREMElGS ROUTIliE REPORTS AfiD REPORTABLE OCCURREliCES 6.9.1 In addition to the applicable reporting requira:ents of Title 10, Code of Federal Regulations, the following reports shall be submitted to the I;RC Regional Administrator unless otherwise ncted.

't:ot required to be implemented until Septeraer 1, 1923.

SA!i 0:;0rRE-U::IT 2 6-15 AMEh3GNT NO.17 APR 2 91983

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ADMINISTRATIVE CONTROLS 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 ine ease 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 plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a compari-son of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

t 6.9.1.3 Startup reports shall be s.nsitted within (l') 90 days following JA commencement of commercial power operation, or (3) 9 months following initial F,/.h completion of the startup test program, (2) 90 days following resumption or

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criticality, whichever is earliest. If the Startup Report does not cover all

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three events (i.e., initial criticality, completion of startup test program, 7

and resumption or commencement of commercial operation) supplementary reports l' p#,#

shall be submitted at least every three months until all tnree events have

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L,. v been completed.

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ANNUAL REPORTS

6.9.1.4 Annual reports covering the activities of the un't 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.

6.9.1.5 Reporte required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 arem/yr and their associated manrem exposure according to work and job functions,** e.g., reactor operations and surveillance, inservice inspection, reutine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments

.to various duty functions may be estimated based on dosimeter, TLD, or film badge measurements. Small exposures totalli less t ercent of the individual total dose need not be accounted fo.

In aggre at least 80 percent of the total whole body dose rec 'ved from ektet O gour should be assigned to specific major work functi s.g.

$!(Das !

, A single submittal may be made for a multiple unit station. The

,should combine those sections that are common to all units at the statio.

This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.

SAN ONOFRE-UNIT 2 6-16 FEE 17 m

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ADMINISTRATIVE CONTROLS L

l-ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

6.9.1.6' 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 May 1 of the year following initial criticality.

6.9.1.7 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 comparison with preoperational studies, operational controls (as appropriate), and 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.

If harmful effects or evidence of irreversible damage are detected by the monitoring,* the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples teken during the report period.

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

c The reports shall also include the following: a summary description of the r

radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3.

SEMIANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT

6.9.1.8 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 cri icality.

ISSugo btal j'o,n.

The s A single submittal may be made for a multiple uni s should combine those sections that are common to ft"g.at the station; however, for units with separate radwaste systems, the ttalsha}l specify the releases of radioactive material from each unit.

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SAN ON0FRE-UNIT 2 6-17 FES

7 !932

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ADMINISTRATIVE CONTROLS 6.9.1.9 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste rel. eased 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 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 of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous affluents 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 (Figures 5.1-3 and 5.1-4) 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 meteoro-logical conditions concurrent with the time of release of radioactive materials in gaseous effluents (as detemined 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 OFFSITE DOSE CALCULATION MANUAL (ODCM).

The radioactive effluent release report to be submitted 60 days after January 1 of each year shall also include 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 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operatien. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.

The radioactive affluents release shall include the f information for each type of solid waste shipped offsite during the port pe a.

Container volume,

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b.

Total curie quantity (specify whether de Und.by measureme'nt or estimate),

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c.

Principal radionuclides (specify whether determined easurene,nt.

6 :stist.te),

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Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

Type of container (e.g., LSA, Type A, Type B, Large Quantity), and e.

f.

Solidification agent (e.g., cement, urea formaldehyde).

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SAN ONOFRE-UNIT 2 6-18 FEB 7 SS2

AOMINISTRATIVE CONTROLS ene radioa:tive effluent release reperts shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents en a quarterly basis.

The radioactive affluent release reperts shall in:1ude any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the safety valves, 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 cf each month fc11owing the calendar month covered by the report.

Any changes to the DFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly 0parating Report within 90 days in which the change (s) was made effective.

In addition, a report of any major changes to the radicactive waste treate.ent systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the Onsite Review Committee.

REPORTABLE OCCURRENCES 6.9.1.11 The REPOR7ABLE OCCURRENCE 5 of Specifications 6.9.1.12 and 6.9.1.13 '

below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental rep ~ orts may be required to fully describe final resolution of occurrence.

In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

PROMPT NOTIFICATICN WITH WRITTEN FOLLOWUP 6.9.1.12 The types of events listed below shall be reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the NRC Regicnal Administrater, or his designate no later thare the first woridng day following the event, with a written followup report within '

14 days. The written follow:;p report shh11 include, as a minimum, a ccepleted copy of a licensee event report form. Information provided on the. licensee event report fora shall be supplemented, as needed, by additional ~ narrative material to provide complete explanation of the circumstances surrounding the event.

Failure of the resctor protection system or other systems subject to a.

lidting safety system settings to initiate the re uired erotective fun: tion by the tire a c.onitored parameter reaches the setpoint specified as the limiting safety system setting in th9 technical specifications or failure to complete the required pr;tective functica.

MAY i 61983 SA'l GNDFRE-UNIT 2 6-19 NiE U ME.;T NO. If

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AD'4INISTRATIVE CONTROL 5

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Operation of the unit or affected systems when any parameter or b.

operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the Limiting Cendition for Operation established in the Technical Specifications.

Abnormal degradation discovered in fuel cladding, reactor coolant c.

pressure boundary, or primary containment.

Reac'tivity anomalies involving disagreement with the predicted value d.

of reactivity balance under steady state conditions during power operation greater than or equal to 1% Ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN 1ess conservative than specified in the Technical Specifications; short-term reactivity increases that correspond to a reactor pericd of less than 5 seconds or, if suberitical, an unplanned reactivity insertion of more than 0.5% Ak/k; or occurrence of any unplanned criticality.

Failure or malfunction of one or more components which prevents or could prevent, by)itself, the fulfillment of the functional require e.

ments of system (s used to cope with accidents analyzed in the SAR.

Personnel error or procedural inadequacy which prevents or could f.

prevent, by itself, the fulfillment,of the functional requirements of systems required to cope with accidents analyzed in the SAR.

Conditions arising from natural or man-made events that, as a direct result of the event require unit shutdown, operation of safety systams, g.

or other protective measures required by Technical Specifications.

Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the. s.afety analysis h.

report or in the bases for the Technical Specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses,

' Performance of structures, systems, or ccaponents that requires i.

remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or Technical Specifications bases; or l

discovery during unit life of conditions not specifically considered in the safety analysis report or Technical Specifications that require remedial action or corrective measures to prevent the existance or development of an unsafe cohdition.

Offsite releases of radioactive materials in liquid and gaseous efflu-ents that exceed the limits of Specifications 3.11.1.1 or 3.11.2.1.

l j.

i Exceeding the limits in Specification 3.11.1.4 or 3.11.2.F for the Tht <ritten l

k.

storage of radioactive materials in the listed tanks. follow-up vities planned and/or taken to reduce the contents to wit.un the specified limits.

Failure of one or more pressurizer safety valves. 19( i 6 M 1 AMEU?.ENT N3. 16 1.

6-20 SAN ONOFRE-UNIT 2 l

~ -.

L.

(

ADMINISTRATIVE CONTROLS THIRTY DAY WRITTEN REPORTS 6.9.1.13 The types of events listed below shall be the subject of written reports to the NRC Regional Adeinistrator within thirty days of occurreme of

,the event. The written report shall include, as a sinism, a cospleted copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative asterial to provide complete explanation of the circumstances surrounding the event,.

a.

Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those estab-lished by the Technical Specifications but which do not prevent the fulfillment of the functional requirements of affected systans.

h.

Conditions leading to operation in a degraded mode permitted by a Limiting Condition for Operation or plant shutdown required by a Limiting Condition for Operation.

c.

Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

d.

Abnormal degradation of systems other than those specified in 6.9.1.12.c above designed to contain radioactive material resulting from the fission process.

HAZARDOUS CARGO TRAFFIC REPORT 6.9.1'~14 Hazardous cargo traffic on Interstate 5 (1-5) and the AT&SF railway shall be monitored and the results submitted to the NRC Regional Aasinistrator once every three years.

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

6.10 RECORD RETENTION 2n addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retsined for at least the minimum period indicated.

SAN ONOFRE-UNIT 2 6-21 q

,' j-i

(

ADMINISTRATIVE CONTROLS 6.10.1 The following verords shall be retained for at least five years:

a.

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

b.

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

I c.

All REPORTABLE OCCURRENCES submitted to the Commission.

d.

Records of surveillance activities; inspections and calibrations required by these Technical Specifications.

e.

Records of changes made to the procedures required by Specification 6.8.1.

f.

Records of radioactive shipments.

g.

Records of sealed source and fission detector leak tests and results.

h.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Unit Operating License:

a.

Records and drawing changes reflecting unit design modificatiens made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories, c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

e.

Records of transient or operational cycles for these unit components identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

Records of training and qualification for current eembers of N g.

unit staff.

(

SPl DNOFRE-UNIT 2 6-22 fil ; ' '.5 '.

k ADMINISTRATIVE CONTROLS h.

Records of in-service inspections perfomed pdrsuant to these Technical Specifications.

1.

Records of Quality Assurance activities required by the QA Manual.

j.

Records of reviews performed for changes made to procedu ms or equipment or myiews of tests and experisents pursuant to 10 CFR 50.59.

t.

Records of meetings of the 05RC and the NSG.

1.

Records of the service lives of all snebers listed in Tables 3.7-4a and 3.7-4b including the data at which the service 1.ife commences and associated installation and maintenance records.

a.

Records of secondary water sampling and water gus11ty.

6.11 RADIATION PROTECTION PROGRAM' Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, mainttined and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or "alam signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mram/hr but less than 1000 stes/hr shall be barricaded and conspicuously posted as a hign radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Exposure Pemit (REP)*. Any individual or group of individuals pemitted to

~

enter such areas shall be provided with or accompanied by one or more of the j

I following:

t a.

A radiation monitoring device which continuously indicates the

-radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device any be made after the dose rata level in the area has been established and personnel have been made knowledgeable of them.

" Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the REP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise l

following approved plant radiation protection procedures for entry into high radiation areas.

SAN ONOFRE-UNIT 2 6-23

e ADMINISTRATIVE CDNTROLS c.

' An individual qualified in radiation protection procedures who is equipped with a radiation dose rata monitoring device who is responsible for providing positive control over the activities within the area and shall perfore periodic radiation surveillance at

- the frequency specified by the facility Health Physicist in,the Radiation Exposure Permit.

6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 orea shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or health physics supervision.

l Doors shall remain locked except during periods of access by personnel under an i

approved REP which shall specify the dose rate levels in the issediate work area and the maximum allowable stay time for individuals in that a'rea.

For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 ares ** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be rop W nff, conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the REP, direct or remote

-(such as use of closed circuit TV cameras) continuous surveillance may be'made by p6rsonnel qualified in radiation protection procedures to provide positive exposurs control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commissior, prior to implementation.#

6.13.2 Licensee initiated changes to the PCP:

1.

Shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:

a.

Sufficiently detailed infomation to totally support the rationale for the change without benefit of additional or supplemental information; b.

A determination that the change cid not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and l

I c.

Documentation of the fact that the change has been reviewed and l-found acceptable by the OSRC.

l l

2.

Shall become effective upon review and acceptance by the OSRC.

i

"* Measurement made at 18" from source of radioactivity.

The PCP shall be submitted and approved prior to shipment of " wet" solid 7

j

\\,

, radioactive waste.

l SAN ONOFRE-UNIT 2 6-24 Amendment No. 4 JUI 1 8 '"'

I I

A!!CNISTRATIVE CONTROLS I.

6.14 0::5ITE 005E CALCULATICN MANUAL (00CM) 6.14.1 The CDCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the ODCM:

1.

Shall be submitted to the Commission in the Monthly Operating Report within 90 days of the date the change (s) was made effective. This submittal shall contain:

Sufficiently detailed information to totally support the a.

rationale for the change without benefit of additional or supplemental information.

Information submitted should consist of a pm.kage of those pages of the ODCM to be changed with each c

page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);

b.

A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and Documentation of the fact that.the change has been reviewed and c.

found acceptable by the OSRC.

2.

-Shall become effective upon review and acceptance by the OSRC.

6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and solic) 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid):

1.

'Shall be reported to the Commission in the Monthly Operating Report for the period in which the evaluation was reviewed by the OSRC.

The discussion of each change shall contain:

A summary of the evaluation that led to the determination that a.

the change could be made in accordance with 10 CFR 50.59; b'.

Sufficient detailed information to totally support the reason for the enange without benefit of additional or supplemental information; A detailed description of the equipment, components and c.

processes involved and the interfaces with other plant systems; d.

An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous affluents and/or quantity of solid waste that differ from those previously s

predicted in the license application and acentments thereto; SAN ONOFRE-UNIT 2 6-25 AME:QMENT NO.15 MAY i 61983 1

/

I ADMINISTRATIVE CONTROLS a.

An evaluation of the change which shows the expected maxima exposures to individual in the unrestricted area and to the general population that differ free those previously altimated in the license application and amendments thereto; f.

A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; g.

An estimate of the exposure to plant operating personnel as a result of the change; and h.

Doc eentation of the fact that the change was reviewed and found acceptable;by the OSRC.

2.

Shall becosh effective upon review and.acceptars= 1,y the OSRC.

SAN ONOFRE-UNIT 2 6-26

2. !

..n..

e INSTRUS.ENTAT]DN RAD 10ACT3VE L10VID EFFLUENT 'MDti! TOR]NG INSTRUMENTAT]ON LIS'IT3tG C0f01T10ti FOR ODERATI0ti 3.3.3.8 The radioactive lieutd effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERASLE with their alarm / trip setpoints set to ensure that the lireits of Specification 3.11.1.1 are not exceeden. The alarm /

trip setpoints of these channels shall be determined in accordance with the DFFSITE DOSE CALCULAT3DN MANUAL (DDCM).

APPLICABILITY: At all times."

ACTION:

a.

With a radioactive liquid effluent s;onitoring instrumentation channel alarm / trip setpoint less cor.servative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel c,r declave the channel inoperable.

b.

With less than the minimuss number of radioactive liquid efficent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Additionally, if the inoperable instruments are not returned to OPERABLE status within 30 days, explain in the next Semi-annual Radioactive Effluent Release Report why the inoperability was not. corrected in a timely manner.

c.

The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13b are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAL]BRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

4.3.3.8.2 At least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at least one circulating water pump shall be determined to be operating and providing dilution to the discharge structure whenever dilution is required to meet the site radioactive affluent con:entration limits of Specification 3.11.1.1.

"See Special Test Exception 3.10.5.

SAR ONOFRE-UNIT 2 3/4 3-E3

e 1NST RW.!NT AT]ON

..(

Rs.01DA T!VE GASEOUS EFFLUENT MONITORING INSTRUM.IbATION l

LIMIi1NO C04DIT20N FOR ODERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alara/ trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in a:cordance with the CDCM.

A*PLICAPI LITY: As shown in Table 3.3-13*

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alare/ trip setpcint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous affluents monitored by the affected channel or declare the channel inoperable, b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Additionally, if the inoperable instruments are not

(<'

returned to OPERABLE status within 30 days', explain the next Semi-annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3. 0.3, 3.0.4, and 6.9.1.13b are not amplicable.

SUT.VE1LLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous affluent monitoring instrumentation channel shall be demonstrated OPERABLE by performanes of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frecuencies shown in Table 4.3-9.

5ee Speciel Test Exception 3.10.5 5AN ONDFRE-UNIT 2 3/4 3-6B 1

.c.

5 F.! C 0:t C03LaNT SYSTEM A**10ts:

(Continued)

MCDE5 1, 2,.), 4 and 5:

d.

With the specific activity of the primary coolant greater than 1.0 microcurie / gram DOSE EQUIVALENT I-131 cr greater than 100/I microcuries/ gram, perform the sam: ling and analysis recuire-ments of item t a) of Table 4.4-4 until the specific activity cf the primary coolar. is restored to within its limits. A REPORTABLE OCCURRENCE shall be prepared and submitted to the Commission pursuant sc Specification 6.9.1.

This report shall contain the results of the specific activity analyses together with the follo.cing information:

1.

Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, 2.

Fuel burnup by core region, 3.

Clean-up flow history starting 48 hcurs prior to the first sample in which the limit was exceeded, 4

Histery of de gassing operation, if any, starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in t.hich the limit was exceeded, and 5.

The time duration when the specific activity of the primary coolant exceeded 1.0 microcurie / gram D05E EQUIVA'ENT 1-131.

SURVEILLANCE REQUIREMENTS 4.4.7 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

A SAN ONOFRE-UNIT 2 3/4 4-24 1

s ELECTRICAL POWER SYSTE*.5

~

SURVEILLANOJ REOUIREMENTS (Continued)

13. Verifying that the automatic load sequence timer is OPERABLE l

with the interval between each load block within + 10% of its

~

l design interval.

14.

Verifying that lockout relay K23 prevents diesel generator starting when the diesel generator is actuated.

e.

At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting the diesel generators simultaneously, during shutdown, and verifying that the diesel generators accelerate to at least 900 rpe in less than or equal to 10 seconds.

f.

At least once per 10 years by:

1.

Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution or the equivalent, and 2.

Performing a pressure test of those portions of the diesel fuel sti system designed to Section III, subsection C of the ASME Code at a test pressure equal to 110 per' cent of the system design pressure.

4.8.1.1.3 Reports - All diesel generator failures, valid or non-valid, shall be reported 1Le tne Cosnission pursuant to Specification 6.9.1.

Reports of diesel generator failures shall include the information recommenced in Regule-tory Position C.3.b of Regulatory Guide 1.108, Revision 1 August 1977. If the number of failures in the last 100 valid tests (on a per nuclear unit basis) is greater than or aquel to 7 the report shall be supplemented to include the additional information reconnended -in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1. August 1977.

SAN ONDFRE-UNIT 2 3/4 8-6 ~

-\\

)

'(

RAD 10ACT3VE EFFLUENTS EPIl LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site (see Figure 5.1-4) shall be limited:

a.

During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 arem to any organ, and b.

During any calendar year to less than or equal to 3 aren to the total body and to less than or equal to 10 mree to any organ.

APPLICABILYTY: At all' times.

ACTION:

s.

With the calculated dose from the releast of radiosctive materials in liquid effluents exceeding any of the above limits, in lieu of py other report required by Specification 6.9.1, prepare and subrit

~to the Coanission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the' limit (s) and defines the corrective actions taken to reduce the releases and tne proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.1.2 b.

The provisions of specifications 3.0.3'3.5.4and6.9.1.13barenot applicable.

SURVEILLANCE REQUIREMENTS l

4.11.1.2 Dose Calculations. Cumulative dese contributions from liquid effluents shall ne setemined in accordance with the ODCM at least once per 31 days.

I m-SAN ONDFRE-UNIT 2 3/4 11-5

c, 3/4.12 Rf0f0LOGICALENVIRDWMENTALMONITORI03 3/4.12.1 MDNITORIN3 PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 Theradiologicalenvironmentalmonitoringprogramshallbeconducted as specified in Table 3.12-1.

APPLICASILITY: At all times.

ACTION:

d.

With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Coe-sission, 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.

b.

With the level of radioactivity in an environmental sampling mediur.

exceedhg the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days froe the end of the affecteo calendar quarter a Report pursuant to Specification 6.9.1.13.

When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1), concentration (2) +..11.0 limit level (1) limit level (2) when radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not required if the measured leve1*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.

c.

With fresh leafy vegetable samples or fleshy vegetable samples unavail-able free one or more of the sample locations required by Table 3.12-1, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Coenission within 30 days, pursuant to Specific-ation 6.9.2, a Special Report which identifies the cause of the unavail-abil'.ty of samples and identifies locations fer obtaining replacement samples. The locations from which samples were unavailable may then be deleted from those required by Table 3.12-1, provided the locations free which the replacement samples were obtained are added to the environmental monitoring program as replaces >ent locations.

d.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SAN DN3FRI-UNIT 2 3/4 32-1 UE,'.

6

.e-k.

=

ATrJGMENT B EXISTING TECHNICAL SPECIFICATIONS SAN ONOFRE NUCLEAR GENERATING STATION - UNIT 3 O

e O

e

---___1---_ = - _ - _ _ _ - -

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1. 2 The Shift Supervisor (or during his absence from the Control Room Area, a designated individual) shall be responsible for the Control Room command function. A management directive to this effect, signed by the Vice-President of Nuclear Operations shall be reissued to all station personnel on an annual basis.

'6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown in Figure 6.2-1.

UNIT STAFF 6.2.2 The Unit organization shall be as shown in ligure 6.2-2 and:

a.

Each on duty shift shall be composed of at least the minimum shift.

crew composition shown in Table 6.2-1.

b.

At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor.

In addition, while the unit is in MODE 1, 2, 3 or 4. 'at least one licensed Senior Reactoi Operator shall be in the Control Room area identified as such on Table 6.2-1.

A health physics technician # shall be on site when fuel is in the c.

reactor.

d.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operatcr or Senior Reactor Operator Limited to Fuel Handling who has ro other concurrent responsibilities during this operation.

A site Fire Bgigade of at least 5 members shall be maintained onsite e.

at all times.

The Fire Brigade shall not include the Shift Super-visor and the 2 other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

The health physics technician and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.

HOV 15 %

SAN ONOFRE-UNIT 3 6-1

i. s 4

,'7 s

+

t a

I AOMINISTPATIVE CONTROLS UNIT STAFF (Continutd) \\

,,e f.

Administrative procedures shall be developed and implemented to t

limit the working hours of unit staff who perform safety-related functions; e.g..tsenior reactor operators, reactor operators, v

health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall. be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating.

However, in the event that unforeseen proolens require substantial amounts of overtime to be used, or during eAtended periods of shut-down for refueling, major maintenance or major pint modifications, on a temporary basis, the following guidelines shall be followed:

1)

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months e

e straight, excluding shift turnover time.

2)

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding

/

shift turnover time.

3).

A break of at least eight hours should be allowed between work g

periods, including shift turnover time.,

4)

Except during extended shutdown periods, the use of overtime

. s,

Should be considered on an individual basis and not for the entire staff on a shift.

0 Any deviation from the above guidelines shall be authorized by the Station Manager,- his deputy, the Manager, Operations or higher levels of management, in accordance with 3 stab 11shed procedures and with documentation of the basis for grsating the deviation. Controls s

R shall be included in the procedures such that individual overtine 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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SAN ONOFRE-UNIT 3 6-2

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VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESiOENT 8^

VICE PRE $80ENT 98UCLEAR ENGINEERING IPOWER SUPPLY)

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MANAGER, RESEARCH AND OUALITY TRAIN 1980 DEVELOPMENT ASSURANCE MANAGER C

e MAN A"sE R, NUCLE AR PROJECT MANAGER

't MANAGER ENGINEE SAN ONOFRE UNITS 2 & 3 SYSTEMS R & D NUCLEAR LICEhSING I

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CONP10URATION STATION MATSRIAL AND STATIM CONTROL AND EMERGENCY AOMtmisTRATIVE 88

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1. AT TieAE OF APMINTMENT TO THE POSITION. SENIOR REACTOR OPERATOR UCENSE REQUtRED.

7. SENIOR StEACTOR UCENSE REQUIRED.

1 CONTROL AND ASSISTANT CONTPOL OPERATORS ARE hot.DERS OF REACTOR OPERATOR UCENSES.

1

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4. teeCLUDES FIRE PROTECTION.

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Figure 6.2-2 e

E Unit organization San Ono're Nuclear Generating Station - Unit 3 g

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h SAN ONOFRE-UNIT 3 6-4 E

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+

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Table 6.2-1 MINIMUM SHIFT CREW COMPOSITION la

^

WITH UNIT 2 IN MODE 5 OR 6 OR DE-FUELED POSITION NUMBER OF INDIVIOUALS REQUIRED TO FILL POSITION MODES.1, 2, 3 & 4 MODES 5 & 6 a

a 55 l

g SR0 1

None M

2 1*

40 2

2 STA 1

None WITH UNIT 2 IN MODES 1, 2, 3 OR 4 POSITION NUMBER 9F INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 8

I l'a 1

SS SRO l

None D

R0 2

1 D

2 A0 2

1 a

STA l

None

,af Individual may fill the sas;e position on Unit 2 bf One of the two required individuals may fill the same position on Unit 2.

Shift Supervisor with a Senior Reactor Operators License on SS Units 2 and 3 Individual with a Senior Reactor Operators License on Units 2 are 3 SRO Individual with a Reactor Operators License on Units 2 anc 3 R0 Auxiliary Operator A0 Shift Technical Advisor STA

. Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew usebers provided ignediate action is takan to restore the Shift Crew Composi-tion to within the minteum requirements of Table 6.2-1.

This provision does not permit any shift crew position to be unmanned upon shift cha.nge due to an oncoming shift crewman being late or absent.

During any absence of the Shift Supervisor free the Control Room Area shown in Figure 6.2-3 while the unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Technica1' Advisor) with a valid SRO license shall be designated to assume the Control Room command function. During any absence of the Shift Supervisor from the Control Room Area shown in Figure 6.2-3 while the unit is in T CE 5 or 6, an individual with a valid SR0 or R0 license shall be designated to assume the Control Room command function, yBy 16 E SAN ONOFRE-UNIT 3 6-5 it.

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ADMINISTRATIVE CONTROLS 6.2.3~ INDEPENDENT'$AFETY ENGINEERING GROUP'(ISEG)

" FUNCTION 6.2.3.1. The ISEG sha13: function to examine; plant. operating characteristics, NRC. issuances,: industry advisories,- Licensee. Event-Reports and other. sources of plant design and operating experience-information which may. indicate areas for improving plant safety.

COMPOSITION

..;4.7.3.2 The ISEG shalhte composed.of:st least five: dedicated full-time

-- engineers.- Each shall have.a Bachelor!s> Degree-in Engineering or Physical

-Science or equivalent.and at least two yearseprofessional level experience in his: field. :Off-duty qualifiet Shift-Technical. Advisors:may be used to fulfill this requirement.

'RESPONF.IBILITIEE

.6.2.3.3 The ISEG shall be responsible for. maintaining survei.11ance of. plant activities to provide independent verification

that these activities are

performed correctly. and that human errors are: reduced.as much as. practical.

s AUTHORITY

6.2.3.4 :Th-e ISEG shall make detailad ncommendations for revised procedures, r, :squipment modifications, maintenance activities,: operations activities or

other. means af.. improving. plant safety to. the-Superviser,e Nuclear. Safety. Group.

RECORDS

.. E 2.3.5 - Socords: of. activities' performed by. the ISEG shal.1-be. prepared, 4 - maintained,'and. forwarded ascerxmiendar month to the' MSG-Supervisor.

6.2-E SHIFT-TECHNICAU ADVISOR

^ + ;The: Shift-Technicali Advisor shall provide-technicatinupport to:the: Shift

.:4.-Supervisorin.the areas of: thermal: hydraulics,. reactor engineering and plant

. arnlysis with regart to the safe aperatiotr of.the unit.. The. Shift Technical o ' > Advisor shall have: a: Sacheler.5 -Degree,or equivalent in a scientific or

'-- iengineering discipline with specific-training in; plant-design anddn the m response. and analysis of. the. plant for; transients:and accidents.

6.3' UNIT STAFF QUALIFICATIONS

..8.3.1 Each member of.the unit staff shall muet.cr. exceed the minimum

.1 qualifications of ANSI.M18.1-19'/1 for. comparable'. positions;: except; for the

' Health Physics' Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8 September 1975.

gy 15 52 Not responsible for sign-aff. function.

'5AN ON0FRE-UNIT 3 6-7 e

t ADMINISTRATIVE CONTROLS 6.4 TRAINING

~

6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager, Nuclear Training end shall meet or exceed the requirements and recommonaations of Sections 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements specified in Section A and C. of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience identified by the ISEG.

6.5 REVIEW AND AUDIT 6.5.1 ONSITE REVIEW COMMITTEE (0SRC)

FUNCTION 6.5.1.1 The Onsite Review Committee shall function to advise the Station Manager on c.11 matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Onsite Review Committee shall be composea of the:

Chairman:

Station fanager Member:

Deputy Station Manager Member Manager, Operations Member:

Manager, Technical Member:

Plant Superintendent SONGS Units 2 and 3 Member:

Supervisor of I&C Member:

Manager, Health Physics Member:

Supervisor of Chemistry Memoer:

Manager, Maintenance Member:

Supervising Engineer (NSSS, NSSS Support.

Computer, or STA)

Member:

'SanDiegoGas&gectricRepresentative, Senior Engineer ALTERNATES 6.5.1.3 All alternate meshers shall be appointed in writing by the OSRC Chairmen to serve on a temporary basis; however, no more than two alternates shall participate as voting members in OSRC activities at any one time.

(1}BS degree in Engineering or Physical Science plus at least four years pro-fassional level experience in his field. At least one of the four years experience shall be nucitar power plant experience.

my i51982 SAN ONOFRE-UNIT 3 6-8

ADMINISTRATIVE CONTROLS IEETING FREQUENCY 6.5.1.4 The 05RC shall meet at least once per calendar month and as convened by the 05RC Chairman or his designated alternate.

OUORUM 6.5.1.5 TPs minimum quorum of the O'5RC necessary for the performance of the OSRC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES

6. 5.1. 6 The Onsite Review Committee shall be responsible for:

a.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Nuclear Safety Group (NSG).

b.

Review of events requiring 24-hour written notification to the Commission.

c.

Review of unit operations to detect potential nuclear safety hazards.

d.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Station Manager or the NSG.

e.

Review and documentation of judgeent concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last OSRC meeting.

f.

Review and approval of using and entering values of CPC addressable constants outside the allowable range of Table 2.2-2.

AUTHORITY 6.5.1.7 The Onsite Review Committee (05RC) shall:

a.

Render determinations in writing with regard to whether or not items considered under 6.5.1.6(a) above constitute unreviewed safety questions.

b.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Manager of Nuclear Operations and NSG of disagreement between the 05RC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

C 1 5 1982 SAN ONOFRE-UNIT 3 6-9

~

ADMINISTRATIVE CONTROLS RECORDS 6.5.1.8 The Onsite Review Committee shall maintain written minutes of each OSRC seating that, at a minimum, docue nt the results of all OSRC activities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the Nuclear Safety Group.

6.5.2 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.2.1 The Station Manager shall assure that each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified. individual / organization.

Each such procedure, and changes thereto, shall be reviewed by an individual / group other than the individual / group which prepared the procedure, or changes thereto, but who say be from the same organization as the individual / group which prepared the procedure, or changes thereto.

6.5.2.2 Proposed changes to the Appendix "A" Technical Specifications shall be prepared by a qualified individual / organization. The preparation of each proposed Technical Specifications change shall be reviewed by an individual /

group other than the individual / group which prepared the proposed change, but who say be from the same organization as the individual / group which prepared the proposed change. Proposed changes to the Technical Specifications shall be approved by the Station Manager.

6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a qualified individual /

organization. Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modifi-cation. Proposed modifications to nuclear safaty-related structures, systems and components shall be approved prior to implementation by the Station Manager; or' by the Manager, Technical. as previously designated by the Station Manager.

6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5/2.2 and 6.5.2.3 shall be members of the station supervisory staff, previously designated by the Station Manager to perform such reviews.

Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary. If deemed necessary, such review shall be performed by the appropriate designated review personnel.

6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager, tr.e Manager, Technical, the Manager, Opera-tions, the Manager, Maintenance, the Deputy Station Manager or the Manager, Health Physics as previously desipnated by the Station Manager.

6.5.2.6 The station security program, and implenienting procedures, shall be reviewed at least once per 12 months. Recommended changes shall be approved by the Station Manager and transmitted to the Manager of Nuclear Operations and to the NSG.

NOV 1.5M SAN ONOFRE-UNIT 3 6-10 ui.

u

ADMINISTRATIVE CONTROLS ACTIVITIES (Continued) 6.5.2.7 The station emergency plan, and implementing procedures, shall be reviewed at least once per 12 months. Recommended changes shall be approved by the Station Manager and transmitted to the Manager of Nuclear Operations and to the NSG.

6.5.2.8 The Statien Manager shall assure the performance of a review by a-qualified individual / organization of every unplanned onsite release of radio-active material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the entrective action to prevent recurrence to the Manager of Nuclear Operations and to the NSG.

6.5.2.9 The Station Manager shall assure the performance of a review by a qualified individual / organization of changes to the PROCESS CONTROL FROGRAM, OFFSITE 005E CALCULATION MANUAL, and radweste treatment systems.

6.5.2.10 Reports documenting each of the activities performed under

~

Specifications 6.5.2.1 through 6.5.2.9 shall be maintained. Copies shall 3

be provided to the Manager of Nuclear Operations and the Nuclear Safety Group.

6.5.3 NUCLEAR SAFETY GROUP (NSG)

FUNCTION 6.5.3.1 The Nuclear Safety Group shall function to provide independent review and audit of designated activities in the areas of:

a.

nuclear power plant operations b.

nuclear engineering c.

chemistry and radiochemistry d.

metallurgy e.

instroentation and control f.

radiological safety g.

mechanical and electrical engineering h.

quality assurance practicus Il0V 151922

-SAN ON0FRE-UNIT 3 6-11 c.

l ADMINISTRATIVE CONTROLS I

CONN 0SITION

6. 5. 3. 2 N54 shall consist of a Supervisor and at least three staff specialists.

The Supervisor shall have a Bachelor's Degree in Engineering,or Physical Science and a minimum of 6 years of professional level managerial experience in the power field. Each staff specialist shall have a Bachelor's Degree in Engineer-ing or Physical Science and a minimum of 5 years of professional level experience in the field of his specialty.

The N54 shall use specialists from other technical organizations to augment its expertise in the disciplines of 6.5.2.1.

Such specialists shall meet the same qualification requirements as the NSG members.

CONSULTANTS 6.5.3.3 Consultants shall be utilized as determined by the NSG Supervisor to provide expert advice to the NSG.

REVIEW 6.5.3.4 The NSG shall review:

The safety evaluations for 1) changes to procedures required by a.

Specification 6.8, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify s

that such actions did not constitute an unreviewed safety question.

b.

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

Proposed tests or experiments which involve an unreviewed safety c.

question as defined in Section 50.59, 10 CFR.

d.

Proposed changes. to Technical Specifications or this Operating License.

Violations of codes, regulations, orders, Technical Specifications, e.

license requirements, or of internal procedures or instructions having nuclear safety significance.

f.

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

g.

Events requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months written notification to the Commission.

h.

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

1.

Reports and meetings minutes of the Onsite Review Committee.

I'0V 151982

)

SAN ON0FRE-UNIT 3 6-12

ADMINISTRATIVE CONTROLS AUDITS 6.5.3.5 Audits of unit activities shall be performed under the cognizance of the NSG. These audits shall ancompass:

a.

The conformance of unit operation to provisions contained withir. 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 Quality Assurance Program to meet the criteria of Appendix "8", 10 CFR 50, at least once per 24 months.

e.

Any other area of unit operation considered appropriate by the Nuclear Safety Group or Manager of Nuclear Operations, f.

The Fire Protection Program and implementing procedures at least once per 24 months.

g.

An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified off-site licensee personnel or an outside fire protection fire.

h.

An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified. fire consultant at intervals no greater than 3 years.

AUTHORITY 6.5.3.6 The NSG shall report to and advise the Manager Nuclear Engineering and Safety on those areas of responsibility specified in Sections 6.5.3.4 arhi 6.5.3.5.

RECORDS 6.5.3.7 Records of NSG activities shall be prepared and maintained. Report of reviews and audits shall be distributed monthly to the Station Manager and to the management positions responsible for the areas audited.

MOV 15 BB2 SAN ONOFRE-UNIT 3 6-13

--_ -- j

ADMINISTRATIVE CONTROLS 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTA8LE OCCURRENCES:

The Commission shall be'not'ified and/or a report submitted pursuant a.

to the requirements of Specification 6.9.

b.

Each REPORTA8LE OCCURRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Commission shall be reviewed by the 05RC and submitted to the NSG and the Manager of Nuclear Operations.

6.7 $AFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Manager of Nuclear Operations and the NSG Chainman shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the 05RC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

c.

The Safety Limit Violation Report shall be submitted to the

.Commissien, the Manager of Nuclear Operations and the NSG within l

14 days of the violation.

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAM 5 6.8.1 Written procedures shall be established, implemented and maintained covering the activiti s referenced below:

a.

The applit.able procedures recommanded in Appendix *A" of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Re*uet...g operations.

c.

56

-v:e and test activities of safety related equipment.

d.

Set in implementation.

e.

Emergency Pian implementation.

f.

Fire Protection Program impismentation.'

g, s N-SAN ONOFRE-UNIT 3 6-14

l ADMINISTRATIVE CONTROLS g.

PROCESS CONTROL PROGRAM implementation."

h.

OFFSITE DOSE CALCULATION MANUAL implementation.

1.

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

j.

Modification of Core Protection Calculator (CPC) Addressable Constants.

NOTE: Modification to the CPC addressable constants based on information obtained through the Plant Computar - CPC data link shall not be made without prior approval of the Onsite Review Committee.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be approve by the Station Manager; or by (1) the Deputy Station Manager, (2) :.he Manager s Operations, (3) the Manager, Maintenance, (4) the Manager, Technical, or (5) the Manager, Health Physics as previously designated by the Station Manager; 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 plant management staff, at least one of whom holds, a Senior Reactor Operator's License on the unit affected, The change is documented, reviewed and approved by the Station c.

Manager; or by (1) the Deputy Station Manager, (2) the Manager, i

Operations, (3) the Manager, Maintenance, (4) the Manager, Technical, or (5) the Manager Health Physics as previously designated by the c

Station Manager; within 14 days of implementation.

6.8.4 The following programs shall be established, implemented, and maintained:

a.

Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a seri.s transient or accident to as low as practical levels. The systems include the high pressure safety injection rccirculation, the shutdown cooling system, the reactor coolant sampling system (post-acciderit sampling piping only), the containment spray system, the radioactive waste gas system (post-accident sampling return piping only) and the liquid radwaste system (post-accident sampling return piping only). The program shall include the following:

(1) Preventive maintenance and periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

"See Specification 6.13.1 HOV 15 Ba2 SAN ON0FRE-UNIT 3 6-15

~

/.r.J'I!;1STPATIVE CO::TROLS b.

In-Plant Radiation Monitorine A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.

Th'is program shall include the following:

(1) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment.

c.

Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

(i) Identification of a sampling schedule for the critical variables and control points for these variables, (ii). Identification of the procedures used to' measure the values'of the critical variables, (iii) Identification of process sampling points, including monitoring the discharge of the ccndensate pumps for evidence of condenser in-leakage, (iv) Procedures for the recording and management of data, (v) Procedures defining corrective actions fpr all off-contre' point chemistry conditions, and (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

d.

Post-AccidentSamolino A program

which will ensure the capability to obtain and analyze reactor coolant, radioactive iodints and particulates in plant gaseous affluents, and containment atmosphere samples ur. der accident conditions.

The program

shall include the tratining of personnel, the procedures for sampting and analysis and the provisiens for maintenance of sampling and analysis equipment.

6.9 REPORTING REQUIREMENTS ROU'INE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the fo11owin3 reports shall be submitted to the NRC Regional Administrator unless otherwise noted.

Not required to be implemented until Septe ber I; 19S3.

sa 0:.0FRE-L'4IT 3 6-16 A s a m t NO. 5.

ADMINISTRATIVE CONTROLS STARTUP REPORT 4.9.1.1 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 sty have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a compari-son of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation 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 reoorts shall be submitted within (1) 90 days following comp 1' tion 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 three montna until all three events have been completed.

ANNUAL REPORTS

6.9.1.4 Annual reports covering the activities of the unit as der.cribed 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.

6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 ares /yr and their associated manres 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, TLD, or film twdge measurements. Small exposures totalling less than 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

g..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.

anThis tanulation supplements the requirements of $20.407 of 10 CFR Part 20.

Il0V 151982 SAN ONOFRE-UNIT 3 6-17

ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONNENTAL OPERATING REPORT *

5. 9.1. 5 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 May 1 of the year following initial criticality.

5.9.1.7 The annual radiological environmental operating reports shall include summaries, intenretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on tha environment. The reports shall also include the results of land use censuses required by Specification 3.12.2.

If harmful effects or evidence of irreversible damage are detected by the monitoring, the report.shall provide ar, analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiclogical environmental samples taken during the report period.

In the event that some 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; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.22.3.

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

5.9.1.8 Routine radioactive affluent release reports covering the operation of the unit during the previous 5 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.

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

however, for units with separate radweste systems, the submittal shall l

specify the releases of radioactive material from each unit.

HOV i 51982

~

SAN ONOFRE-UNIT 3 6-18

l ADMINISTRATIVE CONTROLS 6.9.1.9 The radioactive effluent release reports shall include a summary cf the quantities of radioactive liquid and gaseous affluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Ivaluating, 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 femat of Appendix B thereof.

The radioactive effluent release report to be submittsd 60 days after January 1 of each yeer 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 of wind speed, wind direction, ar.d atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous affluents 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 affluents to members of the public due tn their acT.ivities inside the site boundary (Figures 5.1-3 and 5.1-4) 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 meteoro-logical conditions concurrent with the time of release of radioactive materials in gaseous effluents (as detemined by sampling frequency and measurement) shall be used for determiniag the gaseous pathway doses. The assessment of radiation doses shall be perfomed in accordance with the 0FFSITE DOSE CALCULATION MANUAL (00CM).

The radioactive effluent release report to be submitted 60 days after

~

January 1 of each year shall also include 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 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous affluents are given in Regulatory

. Guide 1.109 Rev. 1.

The radioactive affluents release shall include the following information for each type of solid waste shipped offsite during the report period:

a.

Container voltane, b.

Total curie quantity (specify whether determined by measurement er estimate),

c.

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

d.

Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

Type of container (e.g., LSA, Type A, Type B, Large Quantity), and e.

f.

Solidification agent (e.g., cement, urea fomaldehyde).

NOV 151982 SAN ONOFRE-W4IT 3 6-19

ADMINISTRATIVE CONTROLS The radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactite materials in gaseous and liquid effluents en a quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challences to the safety valves, shall be submitted on a monthly basis to the Direct?r, Office of Resource Management, U.S. Nuclear Regulatory Comunission, Washington, D.C. 20555, with a ropy to the Regicnd Aouinistrator of the Regional Office of the NRC, no later than the 15th of each munto following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submiu.ed with the Monthly Operating Report within 90 days in which the change (s) was made effectiv2.

In addition, a rerart of any major changes to the radioactive weste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the Onsite Review Committee.

REPORTABLE OCCURRENCES 6.9.1.11 The REPORTA8tE OCCURRENCES of Specifications 6.9.1.12 and 6.9.1.13 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC.

Supplemental reports may be required to fully describe final resolution of occurrence.

In case of correcten or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.12 The types of events listed below shall be reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone and confimed by telegraph, sailgram, or facsimile transmission to the Regional Administrator of the Regional Office or his designate no later then the first working day following the event, with a written followup report within 14 days. The written *ollowup report shall include, as a minimum, a completed copy of a licensee event report fom.

Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

Failure of the reactor protection system or other systems subject to a.

limiting safety system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint a

specified as the limiting safety system setting in the technicsl specifications or failure to complete the required protective function.

g iU N SAN ONCFRE-UNIT 3 6-20

E a

I f

ADMINISTRATIVE CONTROLS

[

b.

Operation of the unit or affected systems when any parameter or opuration subject to a limiting condition for opsration is less conservative than the least conservative aspect of the Limiting Condition for Operation established in the. Technical Specifications.

c.

Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.

d.

Reactivity anomalies involvin2 disagreement with the predicted value of reactivity balance under steady-state conditions during power operation greater than or equal to 1% Ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified 6

in the Technical Specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if suberitical, an unplanned reactivity insertion of more than 0.5% Ak/k; or occurrence of any unplanteed criticality.

r I-.

e.

Failure or malfunction of one or more ccaponents which prevents or could prevent, by itself, the fulfillment of the functional requirements of systee(s) used to cope with accidents analyzed in the SAR.

E f.

Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements

[

of systems required to cope with accidents analyzed in the SAR.

g.

Conditions arising from natural or man-made events that, as a direct P

result of the event, require unit shutdown, operation of safety systems, or other protective measures required by Technical Specifleations.

h.

Errors discovered in the transient or accident analyses or in the T

methods used for such analyses as described in the safety analysis g

report or in the bases for the Technical Specifications that have or coulci have permitted reactor operation in a manner less conservative g--

than assumed in the analyses.

E 1.

Performance of structures, systems, or components that requires Y

remedial action er corrective measures to prevent operation in a

[

t manner less conservative than assumed in the accident analyses in l 1 the safety analysis report or Technical Specifications bases; or L

discovery during unit life of conditions not specifically considered in the safety analysis report or Technical Specifications that

[

require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

o IE j.

Offsite releases of radioactive materials in liquid and gaseous

[

effluents that exceed the limits of Specifications 3.11.1.1 or 3.11.2.1.

q f

k.

Exceeding the limits in specification 3.11.1.4 or 3.11.2.6 for the

! -]

t storage of radioactive materials in the listed tanks. The written F

follow-up report shall include a schedule and a description of y

activities planned and/or taken to reduce the contents to within the y

specified limits.

=

n

[

1.

Failure of one or more pressurizer safety velves.

h m!151982 h

SAN ONOFRE-UNIT 3 6-21 y

ADM!NISTRATIVE CONTROLS THIRTI DAY WRITTEN REPORTS 6.9.1.13 The types of events listed below shall be the subject of written reports to the NRC Regional Administrator within thirty days'of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Infomation provided on the licensee event report form shall be supplemented, cs needed, by additional narrative material to p-ovice complete explanation of the circumstances surrounding the event.

Reactor protection system or engineered safety feature instrument a,

settings which are found to be less conservative than those estab-lished by the Technical Specifications but which do not prevent the fulfillment of the functional requirements of affected systems.

b.

Conditions leading to operation in a degraded mode permitted by a Limiting Condition for Operation or plant shutdown required by a Limiting Condition for Operation.

c.

Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of l

redundancy provided in reactor protection systems or engineered l

safety feature systems.

l d.

Abnormal degradation of systems other than those specified in 6.9.1.12.c above designed to contain radioactive material resulting from the fission process.

HAZARD 0US CARGO TRAFFIC REPORT 6.9.1.14 Hazardous cargo traffic on Interstate 5 (I-5) and the AT&SF railway shall be monitored and the results submitted to the NRC Regional Administrator once every three years.

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

6.10 RECORD RETENTTON 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.

NOV i 51982 SAN ON0FRE-UNIT 3 6-22

ADMINISTRATIVE CONTROLS 6.10.1 The following records shall be retained for at least five years:

a.

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

b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principc1 items of equipment related to nuclear safety.

c.

All REPORTA8LE OCCURRENCES submitted to the Consission.

d.

Records of surveillance activities; inspections and calibrations required by these Technical Specifications.

e.

Records of changes made to the procedures required by Specification 6.8.1.

f.

Records of radioactive shipments.

g.

Records of sealed source and fission detector leak tests and results.

h.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Unit Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c.

Records of rMiation exposuit for a11 individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

e.

Records of transient or operational cycles for those unit components identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

g.

Records of training and qualification for current members of the unit staff.

yn,y i 51982 I

SAN ON0FRE-UNIT 3 6-23

~

e

.o ADMINISTRATIVE CONTROLS h.

Records of in-service inspections performed pursuant to these Technical Specifications.

1.

Records of Quality Assurance activities required by.the QA Manual.

j.

Records of reviews performed for changes made to procedures or l

equipment or reviews of tests and experiments pursuant to -

10 CFR 50.59.

k.

Records of meetings of the OSRC and the NSG.

1.

Records of the service lives of all snubbers 11'sted in Tables 3.7-4a and 3.7-4b including the date at which the service life commences and associated installation and maintenance records.

Records of secondary water sampling and water quality.

m.

6.11 ItADIATION PROTECTION PROGRAN Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved; maintained and adhered to for all operations involving personnel radiation exposure.

i 6.12 HIGH RA0!ATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 meen/hr but less than 1000 ares /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Exposure Permit (REP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

A radiation monitoring device which continu0usly indicates the a.

radiation dose rata in the area.

b.

A radiation mon'.toring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated i

dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and perJonnel have been ande knowledgeable of them.

" Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the REP issuance requirement during the perfo.reance of their assigwd radiation protection duties, provided they are otherwise following approved plant radiation protection procedures for entry into high radiation areas.

NOV i5 se2 SAN ON0FRE-UNIT 3 6-24

e ADMINISTRATIVE CONTROLS c.

An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Exposure Permit.

6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 aren shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the adminis-trative control of the Shift Supervisor on duty and/or health physics supervision.

Doors shall remain locked except during periods of access by personnel under an_ approved REP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem **

that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual are6s, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

In lieu of the stay time specification of the REP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.#

6.13.2 Licensee initiated changes to the PCP:

1.

Shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:

Sufficiently detailed information to totally support the rationale a.

for the change without benefit of additional or supplemental information; b.

A detemination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and Documentation of the fact that the change has been reviewed and c.

found acceptable by the OSRC.

2.

Shall become effective upon review and acceptance by the 05RC.

"" Measurement made at 18" from source of radioactivity.

The PCP shall be submitted and approved prior to shipment of " wet" solid fadioactive waste.

MN 15 52 SAN ONOFRE-UNIT 3 6-25

__________i_________

e i

ADMINISTRATIVE CONTROLS

( 14 0FFSITE DOSE CALCULATION MANUAL (00CM) 6.14.1 The 00CM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the 00CM:

1.

Shall be submitted to the Commission in the Monthly Operating Report within 90 days of the date tra change (s) was made effective. This submittal shall contain:

a.

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.

Infomation submitted should consist of a package of those pages of the 00CM to be changed with eacn 4

page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying l

the change (s);

b.

A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.

Documentation of the fact that the change has been reviewed and found acceptable by the OSRC.

2.

Shall become effective upon review and acceptance by the OSRC.

6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT $YSTEMS (Liquid, Gaseous and solid) 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid):

1.

Shall be reported to the Commission in the Monthly Operating Report for the period in which the evaluation was reviewed by the OSRO.

The discussion of each change shall contain:

A summary of the evaluation that led to the determination that a.

the change could be made in accordance with 10 CFR 50.59; i

b.

Sufficient detailed infomation to totally support the reason for the cha p without benefit of additional or supplemental information; c.

A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; d.

An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste tr.at differ from those previously predicted in the license application and amendments thereto; SAN ON0FRE-UNIT 3 6-26 o

l ADMINISTRATIVE CONTROLS e.

An evaluation of the change shich shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and ameneents thereto; f.

A comparison of the predicted releases of radioactive materials, in 11guld and gaseous affluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; g.

An estimate of the exposure to plant operating personnel as a result of the change; and h.

Documentation of the fact that the change was reviewed and found acceptable by the OSRC.

2.

Shall become effective upon review and acceptance by the OSRC.

s HOV i 5 BM SAN ON0FRE-UNIT 3 6-27 I

A

f INSTRUNENTATION SADI0 ACTIVE LIQUID EpFLUENT IONITORING INSTRLMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alare/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 a e not exceeoed. The alarm /

trip setpoints of these channels shall be determined in accordance with the OFF5ITE 005E CALCULATION MANUAL (00CM).

APPLICABILITY: At all times.

~

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

(*

th.

With less than the minimum number of radioactiva liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Additionally, if the inoperable instruments are not returned to OPERABLE status within 30 days, explain in the next Semi-annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

I c.

The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13b are not

, applicable.

$URVEILLANCE REQUIREMENTS 4.3.3.8.1 Each radioactive liquid affluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CMECK, CHANNEL CALISRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

4.3.3.8.2 At least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at least one circulating water pump shall be determined to be operating and providing dilution to the discharge structure whenever dilution is required to meet the site radioactive effluent concentration limits of Specification 3.11.1.1.

(

g0v i 5 M SAN ONOFRE-UNIT 3 3/4 3-64

l l

i l

L INSTRUMENTATION js.L0 ACTIVE GASE0US TFFLUENT DONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alam/ trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be detemined in accordance with the 00CM.*

APPLICABILITY: As shown in Table 3.3-13 ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alare/ trip setpoint less conservative than required by the above Specification, imm diately suspend the release of radioactive gaseous affluents monitored by the affected channel or declare the channel inoperable.

b.

With itss than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown g

in Table 3.3-13.

Additionally, if the inoperable instruments are not returned to OPERABLE status within 30. days, explain the next Seet-annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c.

The previsions of Specifications 3.0.3, 3.0.4, and 6.9.1.13b are not applicable.

SURVEILLANCE REQUIREMENTS

'4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CNECK, SOURCE CHECK, CHANNEL CALIBRATION and CNANNEL FUNCTIONAL TEST operations at the fr<quencies shown in Table 4.3-9.

" Continuous monitoring and sampling of the contaiment purge exhaust directly from the purge stack shall be pror'ded for the low and high volume (8-inch and 42-inch) containment purge prior to startup followir:g the first refueling estage. Containment airborne monitor 3RT-7804-1 or 3RT-7807-2 and associated sampling media shall perfom these functions prior to initial criticality.

i.

From initial criticality to the startup following the first refueling outage containment airborne monitor 3RT-7804-1 and associated sampling media shall perfom the above required functions.

SAN ON0FRE-UNIT 3 3/4 3-69

k

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or p tf

'A REACTOR COOLANT SYSTEM

.N

.,l S. -

ACTION: (Continued) j( f, Mr s.

s MDDE5 1, 2, 3, 4 and 5:

g ,

.4

)@!-N d.

With the specific activity of the primary coolant greater than 1.0 microcurf e/ gram DOSE E(JIVALENT I-131 or greater than

,y 100/T microcuries/ gram, perform the sampling and analysis require-

F-sents of item 4 a) of Table 4.4-4 untti the specific activity of the

$.f ;

?

primary coolant is restored to within its limits. A REPORTABLE OCCURRENCE shall be prepared and subettted tc the Commission T@.

pursuant to Specification 6.9.1.

This report shall contain the N ' j~

results of the specific activity. analyses together with the following information:

Y &

h 1.

Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first e.;.... [.

sample in which the limit was exceeded, 4.y.3 3

,J-

' y ",.

2.

Fuel burnup by core region, 3.

Clean-up flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, I

4.

History of de-gassing operation, if any, starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, and s

s

5.. The time duration when the specific activity of the prir,ary coolant exceeded 1.0 microcurie / gram DOSE EQUIVALENT I-131.

SURVEILLANCE REQUIREMENTS 4.4.7 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

(

ytN i 5199

$AN ONOFRE-UNIT 3 3/4 4-25

_m.

ELECTRICALPthERSYSTEMS SURVEILLANCE REQUIREMENT 5 (Continued)

13. Verifying that the automatic load sequence timer is OPERABLE with the interval between each load block within + 10%.of its design interval.

14. Verifying EMt lockout relay K23 prevents diesel generator starting when the diesel generator is actuated.

~

e.

At least once per 10 years or after any modifications'which could affect diesel generator interdependence by ste-ting the diesel generators simultaneously, during shutdown, and verifying that the diesel generators accelerate to at least 900 rps in less than or equal to 10 seconds.

f.

At least once per 10 years by:

~

1.

Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution or the equivalent, and

(-

2.

Perforsing i pressure test c'f those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME

- ~ -

Code at a test pressure equal to 110 percent of the system design pressure.

4.8.1.1.3 Reports - All diesel generator failures, valid or non-valid, shall be reported to the Commission pursuant to Specification 6.9.1.

Reports of diesel generator failures shall include the information recommended in Regula-tory Position C.3.b of Regulatory Guide 1.108, Revision 1. August 1977. If the ntmber of failures in the last 10'J valid tests (on a per nuclear unit basis) is greater than or equal to 7, the report shall be suppionented to include the additional information reconnended in Regulatory Position C.3.b of Regulatory Guide 1.108. Revision 1 August 1977.

(

SAN ONOFRE-UNIT 3 3/4 8-6

r.

o

/

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGPAM LIMITING CONDITION FOR OPERATION 2.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a.

With the radiologit.a1 en-ironmental t,nitoring program not being -

conducted as specified in ':ble 3.12-1, in lieu of any other report ritquired by Specification 6.9.1, prepare and submit to the Com-mission, 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.

b.

With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Coernission within

(

30 days from the end of the affected calendar quarter a Report pursuant to Specification 6.9.1.13.

When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1), concentration (2) + * '> 1.0 limit level (1) limit level (2)

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not required if the seasured 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 Er:vironmental Operating Report.

c.

With fresh leafy vegetable samples or fleshy vegetable samples unavail-able from ena or more of the sample locations required by Table 3.12-1, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specific-ation 6.9.2, a Special Report t.hich identifies the cause of the unavail-ability of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may then be deleted from those required by Table 3.12-1, provided the locations from which the replacement samples were obtained are added to the environmentai conitoring program as replacement locations.

('

d.

The provisions of Specificatiois 3.0.3 and 3.0.4 are not applicable.

NOV 151982 SAN ONOFRE-UNIT 3 3/4 12-1 I

[A e

ATTAQIMENT C PROPOSED TECHNICAL SPECIFICATIOtG

- SAN CNOFRE NUCLEAR GENERATING STATION - UNITS 2 AND 3

s..

e 4

4

l

- DEFINITIONS 4

PURGE - PURGIIC 1.23 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain tenperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is requ' ed to purify the confinement.

RATED THERMM, POWER 1.24 RATED THERMM, POWER shall be a total reactor core heat transfer rate to the reactor cr.olant of 3390 mit.

REACIOR TRIP SYSTEM RESPONSE TIME 1.25 The REACIOR TRIP SYSTEM RESPONSE TIME shall be tne time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

REPORTABLE EVENT

-1.26 A REPORFABLE EVENT shall be any of those conditions specified in 50.73 to 10 CFR Part 50.

SEUTDOW MARGIN 1.27 SHITIDOW MARGIN shall be the instantaneous amount of r6 activity by which the reactor is subcritical or would be suberitical from its present condition assuming (1) all full length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully witrxtrawn, and (2) no change in part length control element assenbly position.

SOF% RRE 1.28 The digital conputer SOFTWARE for the reactor protection system shall be

,the program codes including their associated data, documentacion and procedures.

_ SOLIDIFICATION 1.29 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systuns to a homogeneous (uniformly distributed), monolithic, innobilized

' solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing)..

SOURCE CHECK 1.30 A SOURCE CEE3 shall be the qualitative assessment of channel response when the dannel sensor is exposed to a radioactive source.

p, SAN ONOFRE-tEIT

&_m____.______

ADMINISTRATIVE CENIROLS 6.1 RESPONSIBILITY 6.1.1 Se. Station Manager shall' be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 S e Shift Superintendent (or during his absence from the Control Room Area, a desi p ated individual) shall be responsible for the Control Room connand function. A management directive to this effect, signed by the Vice President and Site Manager, Nuclear Generation Site shall be ieissued to all site / station personnel on an annual basis.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown in Figure 6.2-1.

UNIT STAFF

-6.2.2 The Unit organization shall be as shown in Figure 6.2-2 and:

Each on duty shift shall be conposed of at least the mininum shift a.

crew conposition shown in Table 6.2-1.

b.

At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor. In addition, while the unit is in MDE 1, 2, 3 and.4, at least one licensed Senior Reactor Operator shall be in the Control Room area identified as such on Table 6.2-1.

A health physics technician # shall be on site when fuel is in the c.

reactor.

d.

All core AgrERATIONS aball be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator I.imited to Fuel Bandling who has no other concurrent responsibilities during this operation.

A site Fire B(igade of at least 5 meabers shall be maintained onsite e.

at all times.' The Fire Brigade shall not include the Shift Superintendent and the 2 other members of the mininum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

The health physics technician and Fire Brigade composition may be less than the mininum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to acr==whte unexpected absence provided insnediate action is taken to fill the required positions.

SAN ONOFRE UNIT gp 9

I Chas.. nan of the Board I

Executive Vice President l

Senior Vice President

)

Vice President Vice President Vice President (Engineering Vice Pree4 dent

& Site Manager (Nuclear Engineer-Vice President and (Power Supply)

(Nuclear lag. Safety and (Fuel Supply)

Construction)

Generation Site)

Licensing) l O,ay-M.c g.

M.anager.

a mas.

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ra Licensing Engineering Deelen

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Manager.

operassone

,y,,,,,er 8"*g

"*"*8*

ed and

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Quauty Nuclear Aes.,a-o S.tet, Main - e S pert i

Ptolect Manager.

Nuclear Can Sur*getsand Safety

- *8"'

Cost Control Group i

j Project Mansger' i

Manager.

San Onofre TrWning Units 2 & 3 i

On Site Supervising gg,ggo, Head ters Managw Co t ee iSE

$3, gg,,

g FIGURE 6.2-1 OFFSITE ORGANIZATION SAN ONOFRE NUCLEAR GENERATING STATION

E Station Manager Deputy Station Manager

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Manager, Manager,

Manager, Station Emergency Compliance Station Security Preparedness I

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Manager, Manager,

Manager, Manager, Health Physict Technical Operations Maintenance l

Health Physics Supervising Plant Supervisor of Supervisor Engineer, NSSS Superintendent Maintenance Units 2 & 3 Support Units 2 & O E ;":::.-if g I

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Health Physics Supervising Contractor 8

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Engineer, Supervisor STA Operators J

Supervisor of Plant I. At tune of oppoentmer>t to the position. Seriior Reactor Operator Cheniistry Lic= ***s.

2. SensorReactor Licensereesired.

3. Control end Assistent Control Operatore see holdere et Reactor Operator Licenses.

4. Includes fire protection.

FIGUnE s.2-2 UNIT ORGANIZATION SAN ONOFRE NUCLEAR GENERATING STATION

Table 6.2-1 MIND 0M SHIFT CREW CDMPOSITI0ti WITH UNIT 3 IN MODE 5 OR 6 OR DE-FUEL?..D POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION E DES 1, 2, 3 & 4 MODES 5 L 6 SS la la CRS(SRO) 1 None RO 2

1 AD 2

2b STA 1

-None WITH UNIT 3 IN MODES 1, 2, 3 OR 4 POSITION 10MBER OF INDIVIDUAIS REQUIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 SS la la CRS(SRO) la Ibne RO 2b i

AD 2b i

STA la Ibne 3/

Individual may fill the same position on Unit 3 b/

One of the two required individuals may fill the same position on Unit 3.

Shift Superintendent with a Senior Reactor Operators License on SS Units 2 and 3 CRS(SRO) -

Control Room Supervisor (Individual with a Senior Reactor Operators License on Units 2 and 3)

Individual with a Reactor Operators License on Unita 2 and 3 RO Auxiliary Operator AO Shift Technical Advisor STA Except for the Shift Superintendent, the Shift Crew Cocposition may be one less than the mininum requirements of Table ;.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accomodate unexpected absence of on-duty shift crew meubers provided imediate action is taken to restore the Shift Crew Couposition to within the minimm requirements ed Table 6.2-1.

This provision does not permit any shift crew posit. ion to be unmanned upon shift change due

.to an orwzaing shift crewman being late or absent.

During any absence of the 'hift Superintendent from the Control Room Area shown in Figure 6.2-3 while the unit is in IODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid SRO license shall be

. designated to assume the Control Room comand function. During any absence of the Shift Superintendent from the Control Rocm Area shown in Figure 6.2-3 while the unit is in MODE 5 or 6, an individual with a valid SRO or RO license shall be designated to assume the Control Room comands function.

SAN ONDFRE-UNIT 2

Table 6.2-1 MINIEM SHIFT CREW COMPOSITICH WITH UNIT 2 IN MODE 5 OR 6 OR DE-FUELED POSITION NUMBER OF INDIVIDUALS REQUIRED M FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 la la SS CRS(SRO) 1 None RO 2

1 AD 2

2b STA 1

None WITH UNIT 2 IN E DES 1, 2, 3 OR 4

-POSITION NUMBER OF INDIVIDUAIS REQUIRED TO FILL POSITION MODES 1, 2, 3 & 4 rODES 5 & 6 la la SS OtS(SRO) la None RO 2b i

AO 2b i

STA la None 3/

Individual may fill the same position on Unit 2 bj One of the two required individuals may fill the same position on Unit 2.

Shift Superintendent with a Senior Reacter Operators License on SS Units 2 and 3 CRS(SRO) -

Control Room Supervisor (Individual with a Senior Reactor Operators License on Units 2 and 3)

Individual with a Reactor Operators License on Units 2 ar.d 3 RO Auxiliary Operator AO Shift Technical Advisor STA Except for the Shift Superintendent, the Shift Crew Conposition may be one less than the mininum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to acconnodate unexpected absence of on-duty shift crew mentzers provided immediate action is taken to restore the Shift Crew Oonposition to within the minimum requirements of Table 6.2-1.

This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the Shift Superintendent from the Control Room Area shown in Figure 6.2-3 while the unit is in EDE 1, 2, 3 or 4, an individual (other than the SHft Te:tnical Advisor) with a valid SR) license shall be designated to assume the control Room connand function. During any absence of the Shift Superintendent from the Control Room Area shown in Figure 6.2-3 while the unit is in EDE 5 or 6, an individual with a valid SRO or RO license shall be designated to assume the Control Room connands function.

SAN OtOFRE-UNIT 3

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ADMINISTRATIVE CDtTrROLS 6.2.3 INDEPENDErff SAFETY ENGINEERING GROUP (ISEG)

FUtCTION 6.2.3.1 2 e ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event F? ports and other sources of plant design and operating experience information which may indicate areas for irproving plant safety.

COMPOSITION 6.2.3.2 2e ISEG shall be conposed of at least five dedicated full-time engineers. Each shall have a Bachelor's Degree in Engineering or Physical Science or egaivalent and at least two years professional level experience in his field. Off-duty qualified Shift Technical Advisors may be used to fulfill this requirement.

RESPONSILILITIES 6.2.3.3 W e ISEG shall be responsible for maintaining surveillance of plant activities to provide independent verification

that these activities are performed correctly and that human errors are reduced as nuch as practical.

AttrHORITY 6.2.3.4 S e ISEG shall make detailed recommendations for revi ed procedures, equipment :nodifications, maintenance activities, operations activities or other means of inproving plant safety to the Supervisor, Nuclear Safety Group.

RECIRCS 6.2.3.5 Records of activities performed by the ISEG shall be prepared, maintained, and forwarded each calendar nonth to the NSG Supervisor.

6.2.4 SHIFT TECHNICAL ADVISOR The Shift Technical Advisor shall provide technical support to the Shift Superintendent in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit. W e Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design ar.d in the response and analysis of the plant for transients and accidents.

6.3 UNIT STAFF QUALIFICATION 6.3.1 Each member of the unit staff shall meet or exceed the minir.um qualifications of ANSI N18.1-1971 for conparable positions, except for the Health Physics Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

Not responsible for sign-o H function.

SAN ONOFRE-UNIT

i ADMINISTRATIVE COtCROLS 6.4 TRAINING 6.4.1 A retraining and replacement 1.rt.

-am for the unit staff shall be maintained under the direction of the.

.ager. luclear Training and shall meet or exceed the requirements and recomendatiors of Sections 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience identified by the ISEG.

6.5 REVIEW AIM AUDIT 6.5.1 ONSITE REVIEW COMMITTEE (OSRC)

FUNCTION 6.5.1.1 The Onsite Review Cornittee shall function to sdvise the Station Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Onsite Review Cormittee shall be composed of the:

Chairman:

Station Manager Merber:

Deputy Station Manager Member:

Manager, Operations Member:

Manager, Technical Member:

Plant Superintendent SONGS Units 2 and 3 Member:

Supervisor of IEC Member:

Manager, Health Physics Member:

Supervisor of Chemistry Member:

Manager, Maintenance Member:

Supervising Engineer (NSSS, NSSS Support, Conputer, or STA)

Memoer:

San Diego Gas &

ric Representative, Senior Engineer ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the OSRC Chairman to serve on a tenporary basis; however, no more than two alternates shall participate as voting members in OSRC activities at any one time.

(1)BS degree in Engineering or Physical Science plus at least four years professional level experience in his field. At least one or the four years experience shall be nuclear power plant experience.

SAN ONOFRE-UNIT

l-.

ADMINISTRATIVE 0:XEROLS MEfT. ING FREQUENCY 6.5.1.4 2e OSRC shall meet at least once per calendar conth and as convened by the OSRC Oldirman or his designated alternate.

M.

6.5.1.5 2 e minimum quorum of the OSRC necessary for the performance of the OSRC responsibility and authority provisions of these Tednical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.5.1.6 2e Onsite Review Convaittee shall be responsible for:

Investigation of all violations of the Tecnnical Specifications a.

including the preparation and forwarding of reports covering evaluation and reconnendations to prevent recurrence to the Nuclear Safety Group (NSG).

f b.

Review of all REPORTABLE EVENIS.

Review of unit operations to detect potential nuclear safety hazards.

c.

d.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Station Manager or the NSG Supervisor.

Review and documentation of judgement concerning prolonged operation e.

in bypass, dannel trip, and/or repair of defective protection channels of process variables placed in bypass since the last OSRC meeting.

f.

Review and approval of using and entering values of CPC addressable constants entside the allowable range of Table 2.2-2.

,AtmDRITY 6.5.1.7 he Onsite Review Connittee (OSRC) shall:

Render determinations in writing with regard to whether or not itens a.

considered under 6.5.1.6(a) above constitute unreviewed safety questions.

b.

. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the NSG Supervisor and Vice President and Site Manager, Nuclear Generation Site of disagreement between the OSRC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

SAN ONOFRE-UNIT i

e o

ADMINIS3ATIVE CDtEROIS RECORDS 6.5.1.8 The Onsite Review Comittee shall maintain written minutes of each OSRC meeting that, at a mininum, document the results of all OSRC activities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the Nuclear Safety Group.

6.5.2 TECHNICAL REVIEW AND COtCROL AcrIVITIES 6.5.2.1 The Station Manager shall assure that each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified individual / organization. Each such procedure, and changes thereto, shall be reviewed by an individual / group other than the individual / group which prepared the procedure, or changes thereto, but who may be from the same organizatinn as the individual / group which prepared the procedure, or changes thereto.

6.5.2.2 Proposed changes to the Appendix "A" Technical Specifications shall be prepared by a qualified individual / organization. The preparation of each

=

proposed Te&nical Specifications change shall be reviewed by an individual / group other than the individual / group which prepared the proposed dange, but who may be from the same organization as the individual / group whid prepared the proposed change. Proposed changes to the Technical Specifications shall be approved by the Station Manager.

'6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems, and components shall be designed by a qualified individual / organization. Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modification. Proposed modifications to nuclear safety-related structures, systems and couponents shall be approved prior to inplementation by the Station Manager; or by the Manager, Technical as previously designated by the Station Manager.

6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5.2.2 and 6.5.2.3 shall be mornbers of the station / site supervisory staff, previously designated by the Station Manager to perform such reviews.

Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary. If deemed necessary, such review shall be performed by the appropriate designated review personnel.

6.5.2.3 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager, or menbers of the station / site management staff previously designated by the Station Manager.

SAN ONOPRE-UNIT

ADMINISTRATIVE CONTROLS ACTIVITIES (Continued) 6.5.2.6 The station security program and implementing procedures, shall be reviewed in accordance with 10 CFR 73.55(g)(4). Reccmmended changes to the security program or its implementing procedures shall be approved by the Station Manager, his Deputy or the Manager, Station Security.

6.5.2.7 The station emergency plan and implementing procedures, shall be reviewed in accordance with 10 CFR 50.54(t). Re:Ommended changes to the emergency plan or its implementing procedures shall be approved by the Station Manager, his Deputy or the Manager, Station Emergency Preparedness.

6.5.2.8 The Station Manager shall assure the performance of a review by a qualified individual / organization of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the NSG and Vice President and Site Manager, Nuclear Generation Site.

~

6.5.2.9 The Station Manager shall assure the performance of a review by a qualified individual / organization of changes to the PROCESS CONTROL PROGRAM and radwaste treatment systems. The Manager, Nuclear Safety shall assure the performance of such a review of changes to the ODCM.

6.5.3 NUCLEAR SAFETY GROUP (NSG1 FUNCTION 6.5.3.1 The Nucle.ar Safety Group shall function to provide independent review and audit of designated activities in the areas of:

a.

nuclear power plant operations b.

nuclear engineering c.

chemistry and radiochemistry

\\

d.

metallurgy e,

instrumentation and control f.

radiological safety g.

mechanical and electrical engineering h.

quality assurance practices SAN ONOFRE-UNIT

1 L

ADMINISTRATIVE ONPN2 r

CDMPOSITION 6.5.3.2 NSG shall consist of a Supervisor and at least three staff specialists. The Supervisor shall have a Bachelor's Degree in Engineering or Physical Science and a minimum of 6 years of professional level managerial experier.ce in the power field. Each staff specialist shall have a Bachelor's Degree in Engineering or Physical Science and a minimum of 5 years of professional level experience in the field of his specialty.

The NSG shall use specialists from other technical organizations to augment its expertise in the disciplines of 6.5.1.2.

Such specialists shall meet the same qualification requirements as the NSG menbers.

CONSULTANTS 6.5.3.3 Ccnsultants shall be utilized as determined by the NSG Supervisor to provide expr rt. advice to the NSG.

REVIE 6.5.3.4 The NSG shall review:

The safety evaluations for 1) changes to procedures required by a.

(

Specification 6.8, equipment or systems and 2) tests or experiments j

cocpleted under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b.

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

Proposed tests or experiments which involve an unreviewed safety c.

question as defined in Section 50.59, 10 CFR.

d.

Proposed changes to TtM:hnical Specifications or this Operating License.

Violations of codes, regulations, orders, Technical Specifications, e.

license requirements, or of Internal procedures or instructions having nuclear safety significance.

f.

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

g.

All REPORL'ABLE EVENTS.

h.

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

i.

Reports and meeting minutes of the Onsite Review Conmittee.

SAN ONOFRE-UNIT

ADMINISTRATIVE CDtN_R AUDIT 6.5.3.5 Audits of unit activities shall be performed under the cognizance of the NSG. Wese audits shall encoupass:

a.

% e conformance of unit operation to provisions contained within the Technical specifications and applicable license conditions at least once per 12 months.

b.

We perforance, training and gaalifications of the entire unit staff at least once per 12 months.

c.

W e 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.

We performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendi:: "B",10 CFR 50, at least once per 24 months.

Any other area of unit operation considered appropriate by the e.

Nuclear Safety Group or the Vice President and Site Manager, Nuclear Generation Site.

f.

W e Fire Protection Program and implementing procedures at least once per 24 nonths g.

An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified off-site licensee personnel or an outside fire protection firm.

h.

An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

AtmORITY 6.5.3.6 2e NSG shall report to and advise the Manager, Nuclear Safety on those areas of responsibility specified in sections 6.5.3.4 and 6.5.3.5.

RECCRDS 6.5.3.7 Records of NSG activities shall be prepared and maintained. Report of reviews and audits shall be distributed monthly to the Station Manager and to the management positions responsible for the areas audited.

SAN ONOFFE-UNIT

____x._

-________d

l ADMINISTRATIVE CONTROLS 6.6 REPGEABLE EVDC ACTION 6.6.1 "me following actions shall be taken for REPORTABLE rVENIS:

a.

We crunnission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE EVENT shall be reviewed by the OSRC and the results of this review shall be submitted to the NSG and the Vice President and Site Manager, Nuclear Generation Site.

6.7 SAFETY LIMIT VIOLATION 6.7.1 t e following actions shall be taken in the event a safety Limit is violated:

a.

S e NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. S e Vice President and Site Manager, Nuclear Generation Site and the NSG Supervisor shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

A Safety Limit Violation Report shall be prepared. S e reprt shall be reviewed by the OSRC. 21s report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility co g onents, systems or structures, and (3) corrective action taken to prevent recurrence.

c.

W e Safety Limit Violation Report shall be submitted to the Conraission, the Vice President and Site Manager, Nuclear Generation

' Site and the NSG within 14 days of the violation.

d.

Critical operation of the unit shall not be resumed until authorized by the Comission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, ig lemented and maintained

~

covering the activities referenced below:

a.

W e applicable procedures re m.w.ded in Appendix "A" of Regulatory Guide 1.33, Bevision 2, February 1978.

b.

Refueling operations c.

Surveillance and test activities of safety related equipment, d.

Security Plan iglementation.

e.

Emergency Plan iglementation.

SAN ONOFRE-UNIT W

~..

ADMINIS"'RATIVE COtCROLS f.

Fire Protection Program iglementation.

g.

PROCESS CDtmtOL PROGRAM iglementation.*

h.

OFFSITE DOSE CALCULATION MANUAL iglementation.

i.

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

j.

Modification of Core Protection Calculator (CPC) Addressable Constants.

See Specification 6.13.1 M72: Modification to the CPC addressable constants based on information obtained through the Plant Cog uter - CPC data link shall not be made without prior approval of the Onsite Review Comittee.

6.8.2 Each iglementing procedure of 6.8.1 above, and changes thereto, shall be approved by the Vice President and Site Manager, Nuclear Generation Site, or the Station Manager, or Deputy Station Manager, or Manager of Nuclear Generation Services or Cognizant Managers reporting directly to them, prior to iglementation and shall be reviewed periodically as set forth in administrative procedures.

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

a.

W e intent of the original procedure is not altered.

b.

Se change is approved by two ment >ers of the station / site management staff, at least one of wh m holds a Senior Reactor. Operator's License on the unit affected.

c.

Se change is documented, reviewed and approved by responsible management as delineated in 6.8.2 above within 14 days of imlementation.

6.8.4. S e following programs shall be established, iglemented, and maintained:

a.

Primary Coolant Sources Outside Containment

. A program to reduce leakage from those portions of systems outside containnent that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. Se systems include the high pressure safety injection recirculation, the shutdown cooling systcm, the reactor coolant sampling system (post-accident sagling piping only), the containment spray system,

_ the radioactive waste gas system (post-accident sL1pling return SAN ONOFRE-UNIT m-

___._m._m._

7_

e ADMINISTRATIVE C WfROLS piping only) and the liquid radwaste system (post-accident sa@ ling return piping only). S e program shall include the following:

(i) Preventive maintenance and periodic visual insF ction requirements, and (ii) Integrated leak test requireme.

for each system at refueling cycle intervals or less, b.

In-Plant Radiation Monitoring A program which will ensure the capability to accurately datermine the airborne iodine concentration in vital areas under accident conditions.

" is program shall include the following:

(i) Training of personnel, (ii) Procedures for nonitoring, and (iii) Provisions for maintenance of sa@ ling and analysis equipment.

c.

Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. m is program shall include:

(i)

Identification of a sampling schedule for the critical variables and control points for these variables, (ii)

Identification of the procedures used to measute the values of the critical variables, (iii)

Identification of process sa mling points, including monitoring the discharge of the condensate pu@s for evidence of condenser in-leakage, (iv) Procedures for the recording and management of data, (7) Procedures defining corrective actions for all off-control point chemistry conditions, and (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action, d.

Post-Accident Sanpling.

A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. We program shall include the training of p~:?nnel, the procedures for sampling and analysis and the provisions for maintenance of sa @ ling and analysis eqaipment.

SAN ONOFRE-UNIT O

JO-o ADMINISTRATIVE CDtTTRO S 6.9 REPOECING REQUIRDERS

_ ROUTINE REPOfU_S 6.9.1 In addition to the applicable reporting requirements of Title 10, Code

.of Federal Regulations, the following reports s ah ll be submitted to the NRC Regional Administrater unless otherwise noted.

STARrUP REPORT 6.9.1.1 A sumary report of plant startup and power a.scalation 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 plant.

6.9.1.2 t e Startup report shall address each of the tests identified in the

. FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and conparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other comitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following conpletion of the startup test program, (2) 90 days following resunption or comencement of comercial 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, coupletion of startup test program, and resunptioni or comencement of comercial operation) supplementary reports

'shall be subnitted at least every three months until all three events have been coupleted.

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

6.9.1.5 Reports required on an annual basis shall include a tabulation on an

. annual basis of the nunber of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrenVyr and their associated manrem exposure according to work and job functions,** e.g., reactor operations and surveillance, inservice inspection, routine maintenance, A single submittal may be for a nultiple unit station. S e submittal should combine those sections that are comon to all units at the station.

- Wis tabulation supplements the requirements of 10 CFR 20.407.

SAN ONOFRE-UNIT m______________m-______--___

ADMINISTRATIVE CONTROLS special maintenance (describe maintenance), waste processing, and refueling.

l The dose assignments to various duty functions may be estimated based on pocket dostmeter. TLD, or film badge measurements. Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.

I In the aggregate, at least 80 percent of the total whole body dose received l

from external sources should be tssigned to specific major work functions.

"""AL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

6.9.1.6 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 May 1 of the year following initial criticality.

.6.9.1.7 The annual radiological environmental operating reports shall include summaries, 19terpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a compartson with preoperational studies, operational controls (as appropriate)..and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.

The renorts shall also include the results of land use censuses required by Specification 3.12.2.

If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviale the problem.

The annual radiological environmental operating reports shall include sunnarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available f;r inclusion V th 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; a map of all sampling locations keyed to a table giving distances and directions from the site reference point; and the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3.

SEMIANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT

6.9.1.8 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 90 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality.

A singla submittal may be made for a multiple 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.

SAN ONOFRE-UNIT k

_ _____________ _ o

ADMINISTRATIVE COtTIROLS

-6.9.1.9 he radioactive effluent release reports shall include a sumary 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 sumarized on a quarterly basis following the format of Appendix B thereof.

S e radioactive effluent release report to be submitted 90 days after January 1 of each year shall include an annual sumary of hourly meteorological data collected over the previous year. 2is annual sumary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of stability. m is same report shall include an assessment of the radiation doses due to the radioactive liquid and geseous effluents released from the unit or station during the previous calendar year. mis same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to meters of the public due to their activities inside the site boundary (Figures 5.1-3 and 5.1-4) during the report period. All assur:ptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. Se assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCUIATION MANUAL (CDCM).

Se radioactive effluent release report to be submitted 90 days after l

January 1 of each year shall also include an assessment of radiation.tses to the likelf nost exposed member of the public from reactor releases and other nearby urani m fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show

conformance with 40 CPR 190, Environmental Radiation Protection Standards for Nuclear Pouer Operation.

S e radjoactive effluents release shall include the following information for ead type of solid waste shippM offsite during the report period:

a.

Container volume, b.

Stal curie quantity (specify whether determined by measurement or estimmte),

c.

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

d.

Type of waste (e.g., spent resin, compacted dry waste, evaporator i

bottoms),

SAN ONOFRE-UNIT

e ADMI"ISTRATIVE CNIROIS Type of container (e.g., ISA, Type A, Type B, Large Quantity), and e.

f.

Solidificatiion agent (e.g., cement, urea formaldehyde).

The radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS CONIROL PROGRAM (PCP) made during the reporting period.

'MDNIHLY OPCRATING REPOEC 6.9.1.10 Routine reports of operating statistics and shutdown experience, including doctunentation of all dallenges to pressurizer safety valves, and diesel generator failures pursuant to Specification 4.8.1.1.3 shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Connission, Washington, D.C. 20555, with a ccpy to the Regional Administrator of the Regional Office of the N#C, no later than the 15th of each month following the calendar month covered by the report.

Any danges to the OFFSITE DOSE CAIGLATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective. In addition, a report of any major changes to the radioactive waste treatment systems shall be sulanitted with the Mor.thly Operating Report for the period in which the change was made effective.

HAZARDOUS CARGO TRAFFIC REPORT 6.9.1.11 Hazardous cargo traffic on Interstate 5 (I-5) and the ATESF railway shall be monitored and tLe results submitted to the NRC Regional Administrator ^

once every three years.

EMERGENCY GRE 000LIh5 SYSTEM OUTAGE REPORT 6.9.1.12 An annual report shall be submitted to the Director, Office of Intelear Reactor Regulation, Division of Licensing, detailing cum 11ative outage time for ECC systems and components. The report should contain the (1) ECC system or couponent involved; (2) cause of outage; (3) duration of outage; and (4) corrective actions taken. Proposed changes to inprove the availability of the ECG equipment, if needed, shall also be discussed. Reports covering ECCS l.

outages during the previous calendar year shall be submitted prior to April 1 of eacti year.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the NRC Regional Administrator within the time period specified in the Technical Specification Action Statement for each report.

SAN ONOFRE-UNIT T

-r-'

_._,y

ADMINISTRATIVE (DITIROLS RECORD RETE!EION 6.10 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 minirna period indicated.

6.10.1 n e following records shall be retained for at least five yee s:

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

power level.

b.

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

c.

All REPOICABLE EVE!CS submitted to the Comission.

d.

Records of surveillance activities; inspections and calibrations required by these Technical Specifications.

Records of changes rude to the procedures required by Specification e.

6.8.1.

f.

Records of radioactive shipments.

g.

Records.of saaled source and fission detector leak tests and results.

h.

Records of annual physical inventory of all sealed source material of record.

6.10.2 Se following records shall be retained for the duration of the Unit Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup bintories.

Records of radiation exposure for all individuals entering radiation c.

control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

e.

Records of transient or operational cycles for those unit camponents identified in Table 5.7.1.

f.

Records of reactor tests and experiments.

SAN ONOFRE-UNIT

- - - - - - _ - ~ _ _ _, -.

i ADMINISTRATIVE 00tCROLS Records of training and qualification for current members of the g.

unit staff."

- h.

Records of in-service inspections performed pursuant to these Te&nical specifications.

1.'

Records of Quality Assurance activities required by'the QA Manual, j.

Records of reviews performed for changes made to procedures or egaipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the OSRC and the NSG.

1.

Records of the service lives of all snubbers listed in Tables 3.7-4a and 3.7-4b including the date at which the service life cormences and associated installation and maintenance records, Records of secondary water sampling and water quality.

m.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGII RADIATION AREA 6.12.1 In 'eu of the "contreil device

or " alarm signal" required by paragraph 2< <D3(c)(2) of 10 CPR 20, each high radiation area in which the intensity of radiation is greater than 100mreWhr but less than 1000 mreWhr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation

$ 2nre Permit (REP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or armw nied by one or more of the following:

A radiation monitoring device which continuously indicates the a.

radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of r. hem.

11ealth Physics personnel or personnel escorted by Health Physics personnel shall be exenpt from the REP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following approved plant radiation protection procedures for entry into high radiation areas, SAN ONOFRE-UNIT r

ALMINISTRATIVE CONTROLS c.

An individual qualified in radiation protection procedures who is-equipped with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Rediation Exposure Permit.

6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 arem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved REP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 arem** that are located within large areus, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

In lieu of the stay time specification of the REP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCF) 6.13.1 The PCP'shall be aporoved by the Commission prior to implementation.#

6.13.2 Licensee initiated changes to the PCP.

l

(

1.

Shall bc submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change (s) was i

l.

made effective. This submittal shall contain:

a.

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; b.

A determination that the change did not reduce the overall conformance of the solidtfied waste product to existing criteria for solid wastes; and c.

-00cumentation of the fact that the change has been reviewed and found acceptable pursuant to 6.5.2.9 2.

Shall become effective approval by the Manager, Hcalth Physics.

- Measurement made at 18' from source of radioactivity.

~~

The PCP shall be submitted and approved prior to shipment of " wet" solid radioactive waste.

SAN ONOFRE-UNIT I

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ADMINISTRATIVE C0NTROLS

' 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licenses initiated changes to the ODCM:

1.

Shall be submitted to the Commission in the Monthly Operating Report within 90 days of the date the change (s) was made effective. This submittal shall contain:

a.

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.

Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);

-b.

A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.

Documentation of the fact that the change has been reviewed and found acceptable pursuant to 6.5.2.9.

2.

Shall become ef fective upon approval of the Manager, Nuclear Safety.

6.15 MAJOR CHANGES TO RAdI0 ACTIVE WAS'TE TREATMENT SYSTEMS (Liquid, Gaseous and solid)

Licensee initiated major changes to the radioactive waste systems 6.15.1 (liquid, gaseous and solid):

1.

Shall be reported to the Commission in the Monthly Operating Report for the period in which the change was made effective pursuant to 6.5.2.

The discussion of each chance shall contain:

a.

A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; b.

Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c.

A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; d.

An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from thuse previously l

predicted in the license application and amendments thereto; SAN DNOFRE-UNIT

<+

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,yg,,

ADMINISTRATIVE CONTROLS e.

An evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license applicrtion and amendments thereto; f.

A comparison of the predicted releases of radioactive materials, in liquid and gaseous efflutnts and in solid waste,

~

to the actual releases for the perind prior to when the cnanges are to be made; g.

An estimate of the exposure to plant operating personnel as a result of the change; and h.

Documentation of the fact that the change was reviewed and found acceptable pursuant to 6.5.2.9.

2.

Shall become effective upon approval of the Manager Techr.ical.

\\

~

SAN ONOFRE-UNIT

INSTRUMiKTATION RA070 ACTIVE L10UID [FFLUEN7 M3NITORING INSTRUMINiAT]DN L16'!T2N3 CDCITION FOR 08tR&T!DN 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensura that the lirits of Specification 3.11.1.1 are not excences. The alare./

trip setacints of these charnels shall be seterrined in accoraance with the DFF53TE D25! CALCULAT3DN MANUAL (DDCH).

A*PL10 A!! LITY: At all times.*

ACTION:

a.

With a radioactive liquid affluent monitoring instrumentation channel alarm / trip setpoint less conserve'cive than required >y the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, b.

With less than the miniese number of radioactive liquid effluent etnitoring instrumentation channels OPERAELE, take the ACT30N shown in Table 3.3-12.

Additionally, if the inoperable instruments are nat returned to. OPERASLE status within 30 days, explain in the naxt Seei-annual Radioactive Effluent Release Report why the inoperability was net corrected ir. a timely manner.

c.

The provisions of Specifications 3.0.3, 3.0.4, are not applicable.

SURVIILLsN:s REQUIREMIKT5 l

4.3.3.8.1 Each radiepetive 1f quid effluent monitorint instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CM!CK, CHANNEL CAL 18 RAT 3DN and CMANhEL FUN TIDNAL TEST operations at the frecuencias shown in Table 4.3-8.

4.3.3.8.2 At least once per 4 honts at least one circulating water pump shall te 6etermined to be operating and providing dilution to the discharge structure whenever dilution is required to meet the site radioactive affluent con;entration limits of Specification 3.11.1.1.

(

5ee specisi Test Esception 3.10.5.

$AN ONDFRE-UN!T 2 3/4 3-E3 l

1 I. -..

a

+

INSTRLMENTATION RADI0 ACTIVE L10010 EiFLUENT 90NITORING INSTRlMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alare/tt ip setpoints set to l

ensure that the limits of Specification 3.11.1.1 are not exceeded. The alam/

trip setpoints of these channels shall be determined in accordance with the DFF5ITE 805E CALCULATION MANUAL (00CM).

APPLICABILITY: At all times.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation

~

channel alarm / trip setpoint less conservative than reautred by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

tb.

With less than the minine number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Additionally, if the inoperable instruments are not returned to OPERABLE status within 30 days, explain in the next Seni-annual Radioactive Effluent Release Raport why the inoperability was l

not corrected in a tieely manner, c.

The provisions of Specifications 3.0.3, 3.0.4, are not applicable.

ERVE!LLANCEREQUIREMENTS 4.3.3.8.1 Each radioactive liquid offluent monitaring instrumentation channel shall be demonstrated OPERABLE by perfemance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shoe in Table 4.3-8.

4.3.3.8.2 At least ecce per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at least one circulating water pump shall te determined to be operatine and providing diletten to the discharge structure whenever dilutten is required to meet the sita radioactive effluent concentration l

Itatta of specification 3.11.1.1.

%\\' i D SAN ONOFRE-UNIT 3,

3/4 3-64

J 3NSTRuniwT AT10%

RC2040TIVE GASEOUS EFFLUIN1 M3NITOR}N3 7NSTRp!NT AT]DN LIMI*1N3 CDUDIT20N FOR OsERtTION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be DPERABLE with their alarm / trip setpoints set to ensure that the limits ef Specification 3.11.2.1 are not excee5ed. The alarm / trip setpoints of these channels shall be ettermined in a:cercan:e with the CDCM.

~ASPLIC Af! LITY:

As shown in Table 3.3-13" A T!DN:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpcint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous affluents monitored by the affected channel or declare the channel inoperable.

b.

With less than the minimum nu-ber of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Aasitionally, if the inoperable instruments are not returned to OPERAELE status within 30 days, explain the next Semi-annual Radioactive Effluent Release Report why the inoperability was not correctec in a timely manner.

c.

The provisions of specifications 3.c.3, 3.0.4, are not applicable.

5'JEVElLLaN!! REQUIREMENT 5 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be 6emonstrated OPERA 5LE by performance of the CHANHEL CHECK, SOURCE CHECK, CHANNEL CALIERAT3DN and CHANNEL FUN:TIONAL TEST operations at the frecuencies shown in Table 4.3-9.

l

~

5ee Spe:ial Test Exception 3.20.!

l 5AN DNOFRE-UNIT 2 3/4 3-65

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4 INSTRUMENTATION RADI0 ACTIVE GASEQUS TFFLUENT IONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instroentation channels shown in Table 3.3-13 shall be OPERA 8LE with their alam/ trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alam/ trip setpoints of these channels shall be determined in accordance with the 00CM.*

APPLICABILITY: As shown in Table 3.3-13 ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation

~

channel alare/ trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

b.

With less than the miniaw. neber of radioactive gaseous effluent eonitoring instroentation channels OPERABLE, take the ACTION show i in Table 3.3-13.

Additionally, if the inoperable instements are not returned to OPERABLE status within 30 days, explain the next Seet-annual Radioactive Effluent Release Report why the inoperability was l

not corrected in a timely manner.

c.

The provisions of Spe:1fications 3.0.3, 3.0.4, are not applicable.

SURVE!LLANCE REQUIREMENTS

'4.3 3 9 fach radioactive gaseous effluent monitoring instroentation channel

~

shall be demonstrated OPERABLE by perfomance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAL 18 RATION and CMANNEL FUN:TIONAL TEST operations at the frequencies shown in Table 4.3-9.

" Continuous monitaring and sampling of the contalment purge exhaust directly from the purge stack shall be provided for the low and high volme (8-inch and 42-inch) containment purge prior to startup following the first refueling outage. Containment airborne monitor 3RT-7404-1 or 3RT-7807-2~ and associated sampling media shall perform these functions prior to initial criticality.

From initial criticality to the startup following the first refueling outage contalment airborne monitar 3RT-7804-1 and associated sampling media shall perfom the above required functions.

SAN ONOFRf-UNIT 3 3/a 3-Ke

RE A-~04 CO3'. ANT Sv5Tij A-20:,:

(Continvec)

MCDES 1, 2,J, 4 anc 5:

e.

With the specific activity of the prima y coolant greater than 1.0 micro:urie/ gram DCSE EQUIVALENT I-131 or greater than 100/T sierocuries/grar., perfort the sat: ling and analysis recuire-ments of iter. A a) of Table 4.4-4 until the spe:ific a:tivity cf the prir.ary coolant is restored to within its limits. A SPECIAL REPORT shall be prepared and submitted to the Commission within 30 days pursuant to Specification 6.9.2.

This report shall contain the results of the specific activity analyses together with the followino information:

1.

Rea: tor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months price to the first sampla in which the limit was exceeded, 2.

Fuel burnup by core region, 3.

Clean-up flow history starting 48 heurs prior to the first sae;1e in which the lir.it was exceeded, 4

Histcry of de gassing operation, if any, starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior te the first sa ;1e in e.ich the limit was exceenet, ang 5.

The time duration when the spe:ific activity cf the prir.a y coolant exceesec 1.0 microcurie / gram DOSE EQU2 VALENT 3-131.

5URV!]LLAN*E REOJI*.EMENis 4.4.7 The specific activity of the primary coclant shall be deterr.ined to be w'. thin the limits by performance of the sa pling and analysis prograr of Tatle 4.4-4 SAN ONOFRE-UN]i 2 3/4 4-24

4 REACTOR COOLANT SYSTEM ACTION: (Continued) icDES 1, 2. 3. 4 and 5:

d.

tfith the specific activity of the primary coolant greater than 1.0 microcurie / gras 00$E EQUIVALENT I-131 or greater than 100/E aicrocuries/ gram, perfore the sampling and analysis require-ments of item 4 a) of Table 4.4-4 untti the specific activity of the primary coolant is restored to within its limits. A SPECIAL REPORT shall be prepared and submitted to the Commission within 30 days pursuant to Specification 6.9.2.

This report shall contain the results of the specific activity analyses together with the following infonnation:

1.

Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded.

2.

Fuel burnup b.t core region, 3.

Clean-up flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first snaple in which the limit was exceeded.

4.

History of de gassing operation, if any, starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, and 5.

The tisse duration when the specific activity of the primary coolant exceeded 1.0 microcurie / gram Dose EQUIVALENT I-131.

SURVEtLLANCE REQUIREMENTS x

l 4.4.7 The specific activity of the primary coolant shall be detersined to be l

erithin the limits by performance of the sampling and analysis program of l

Table 4.4-4.

i l

l p 15 m2 SAM ONOFRE-UNIT 3 3/4 4-25

a n

ILfCTRICAL PD4 R SYSTEE SURVIILLAN*i Rfou!'atqcs (continuee)

13. - verifying that the automatic loss sequence timer is CPIRAELE with the interval between each loac block within ;,1(3 of its design interval.

14.

Verifying that lockout relay K23 prevents diesel generator staeting wnen the diesel generator is actuatec.

e.

At least once per 10 years or after any modifications which could effect diesel generator interdependence by starting the diesel generators simultaneously, during shutdown, and verifying that the diesel psnerators accelerate to at least 900 rys in less than or equal to 10 seconds.

f.

At least once per 10 years by:

1.

Draining each fuel oil sto age tank, removing the accumuisted sediment anc cleaning the tank using a sodium hypochlorite solution or the equivalent, and 2

Perfoming a pressure test of those portions of the diesel fuel oil syster designed to Section III, subsection C of the ASE Code at a test pressure equal to 110 percant of the systee Gesign pressure.

4.8.1.1.3 Recons - All diesel generator failu es, valid or non-valie, shali t>e reported to the Courission pursuant te Specification 6.9.1.10.

Reports of giesel generator f ailures shall incluet the information recoupenoeg in Reguia-tory Position C.3.6 of ilegulatory Guise 1.106, Revision 1 August 1977. If the number of failures in the last 100 valia tests (on a per nuclear unit basis) is greater than er equal to 7, the report shall be supplemented to include the additional infomation reconnended in Regulatory Position,C.3.6 of Regulatory Guide 1.108 Revi: ion 1 August 1977.

SAN ONDFRE UNIT 2 3/48-6

~

ELECTR* CAL POWER SYSTEMS

$URVEILLANCE REQUIREMENTS (Continued)

13. Werifying that the automatic lead sequence timer is OPERABLE with the interval between each load block within + IOK of its design interval.

14. Verifying that lockout relay K23 prevents diesel generator starting when the diesel generator is actuated.

e.

At least once per 10 years of after any modifications'which could affect diesel generator interdependence by starting the diesel generators simultaneously, during shutdown, and verifying that the diesel generators accelerate to at least 900 rpm in less than or equal to 10 seconds.

f.

At least once per 10 years by:

1.

Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution or the equivalent, and 2.

Performing a pressure test of those portions of the diesel fuel oil syster designed to Section III, subsection ND of the ASME Code at a test pressure equal to 110 percent of the system design prassure.

4.8.1.1.3 Reports - All diesel generator failures, valid or non-valid, shall be reported to tLe Commission pursuant to Specification 6.9.1.10.

Reports of l

diesel generator failures shall include the information recommended in Regula-tary Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977. If the number of failures in the last 100 valid tests (on a per nuclear unit basis) is greater than er equal to 7, the report shall be supplemented to include the additional information reconnended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1. August 1977.

l l

I N

l SAN OfCFRE-tMIT 3 3f4 g.5

6 e'

n R CIDACTIVE FFLUENTS Elf.

LIMIT 1C COCIT!DN FOR O'ERATION 3.11.1.2 The cose or sese cour.itamsnt to an individual from radioactive asterials in lisuid effluents released, fror each reactor unit, from the site (see Figure 5.1-4) shall be limitee:

I a.

During any calendar quarter to less than or equal to 1.5 seer to the total bosy and to less than or equal to 5 ares to any organ, and b.

During any calendar yes* to less than or equal to 3 eram to the total body and to less than or equal to 10 seem to any organ.

A*PLICABILin: At all'tiscs.

ACTION:

~.

With the calculated dose free the release of radioactive materials a

in liquid effluents exceeding any of the above lisits, in lieu of any other report requirec by Specification 6.9.1, prepace and subrit te the Coe-ission within 30 days, pursuant to Specificatier: 6.9;2, a 5pecial Report which identifies the cause(s) for exceeding the limit (s) aN: defines the corrective actions taken to reduce the releases and the p* ort, sed actions to be taken to assure that subsequent releases will be in compliance with Specification 3.u.1.2 The provisions of specifications 3.0.3,'3.d.4 are not applicable.

b.

SURVE!LLANCE RE0VIREMEWT5 4.11.1.2 Dese Calculations. Cumulative dose contributions free liquid effluents snall se seterrined in accordance with the ODCM at least once per 31 days.

i. :

SAN ONOFRE-WIT 2 3/4 u-5

e 3/4.12 RCIOLOCICAL ENVIRO *MEWTAL DONITOR!d3 3/4.12.1 8DNTTORIN3 DR33 RAM L3MITitC CONDIT3DN FOR O'fRATION 3.12.1 The radiological environmental monitoring progras shall be conducted as specified in Tacle 3.12-1.

AePLita31LTTY: At all times.

ACT!DN:

With the radiological environmental monitoring progree not being a.

conducted as specified in Table 3.12-1, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Coe-sission, in the Annual Radiclogical Operating Report, a description of the reasons for act conducting the progras as required and the plans for preventing a recurrence.

b.

With the level of radioactivity in an environmental sampling medium exceeding the reporting. levels of Table 3.12-2 when averagec over any calencar quarter, in lieu of any other report requires by Specification 6.9.1, prepare and subrit to the Coerission within 30 days fror the end of the affected calendar evarter a Special lleport pursuant to Specification 6.9.2.

When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be substitted if; concentrat,f on (1), concentration (2) + * **> 1.0 litn level (1) limit level (2)

Wnen radionuclides other than those in Tchle 3.12-2 are setectec and are the result of plant effluents, this report shall be subtitted if the potential annual sose to an individual is equal to or prester than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not req.: ired if the measured level'of radicactivity 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.

c.

With fresh leafy vegetable samples or fleshy vegetable samples unavail-able free one or more of the sample locations required by Table 3.12-1, in lieu of any other report required by Specification 6.9.1, prepare l

and submit to the Commission within 30 days, pursuant ta Specific-l ation 6.9.2, a Special Report which identifies the cause of the unavail-ability of samples and identifies locations for obtaining replacement samples. The lacations free which samples were unavailable may then be deleted from those required by Table 3.12-1, provided the locations free which the replacement samples were obtained are added.to the envireamental monitoring program as replacement locations.

d.

The provisions of 5pecifications 3.0.3 and 3.0.4 are not applicaele.

SAN ON3FRf-UNIT 2 3/4 22-1 l

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l 3/4.12 RADIOLOGICALENVIRONMENTALMONITORIhG 3/4.12.1 9CNITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a.

With the radiological environmental sonitoring program M t being conducted as specified in Table 3.12-1, in lieu of any other report required by Specification E.9.1, prepare and submit to the Coa-l mission, 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.

b.

With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of any other report required by-Specification 6.9.1, prepare and submit to the Commission within 30 days from the and of the affected calendar quarter a Special Report pursuant to Specification 6.9.2.

When more than one of

.the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1), concentration (2) + "*> 1.0 limit level (1) limit level (2)

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equel to or greater than the calendar year limits of Spe:ifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not required if the sensured 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.

c.

With fresh leafy vegetable samples or fleshy vegetable samples unavail-able free one er more of the sample locations required by Table 3.12-1, in lieu of asy other report required by Specification 5.9.1, prepare and submit to the Commission within 30 days, pursuant to Specific-ation 6.9.2, a Special Report which identifies the cause of the unavail-ability of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailab1s may then be deleted from those required by Table 3.12-1, provided the locations free which the replacement samples were obtained are added to the environmental monitoring program as replacement locations.

d.

The provistens of specifications 3.0.3 and 3.0.4 are not applicable.

50V15542 SAN ONOFRE-UNIT 3 3/4 12-1 e-

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v t e Letter Sequence Other
TAC:54698, (Approved, Closed) TAC:54699, (Approved, Closed) TAC:54700, (Approved, Closed) TAC:54701, (Approved, Closed) TAC:61516, (Approved, Closed) TAC:61517, (Approved, Closed)
Initiation Request, Request Acceptance... Administration Meeting Questions Answers Results Approval Other: ML13305A890, ML20081B573, ML20207N580, ML20212R628
MONTHYEAR1985-03-06 [Table View]

ML20081B573

Text

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