ML20081B591

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

ML20081B591
Person / Time
Site:	San Onofre
Issue date:	03/07/1984
From:	Baskin K SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML13305A539	List: ML20081B564 ML20081B573 ML20081B579 ML20081B591
References
NUDOCS 8403090238
Download: ML20081B591 (117)

Text

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( ELECTRICAL POWER SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

b. Demonstrated OPERA 8LE 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 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 rpe 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

( 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 adcitional 60 minutes, and

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

b. At least once per ll1 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.

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

the storage tanks by verifying that a sample obtained in accordance

' with ASTM-D270-1975 has a water and sediment cent,ent of less than or i equal to .G5 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 tested 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-02274-70.

l I d. At least once per 18 months during shutdown by:

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

2. Verifying the generator capability to reject a loac of greater than or ecuel to 655.7 kw while maintaining voltage at l

4360 : 436 volts and frequency at 60 ; 6.0 Hz.

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ELECTRICAL POWER SYSTEM SURVEILLANCE REOUIREMENTS (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 transfer pump can be started and transfers fuel fro'n 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 vo.itage; and frequency shall he 4360 1 436 volts and 60 1 1.2 Hz within 10 seconds after the start signal. The diesel generator shall be started for this test Dy 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

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

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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.

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-D270-1975 has a water and sediment content of less than or equal to .05 volume percent and kinematic viscosity 04000 of greater than or equal to 1.9 but les; 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 l

accordance with ASTM-D2274-70. A diesel generator is not considered l inoperable on the basis of fuel oil failure to meet the 2 mg of insolubles per l 100 mi limit provided that within 14 days, fuel qualit,1 can be demonstrated to l be within this lisait.

l d. At least once per 18 months during shutdown by:

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1. Subjecting the diesel to an inspection in accordance with procedures l prepared in conjunction with its manufacturer's recommendations for this l 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 ONOFRE-UNIT 2 3/4 8-3

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[ ELECTRICAL POWER SYSTEM 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

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

! STAGGERED TEST BASIS by:

1. Verifying the fuel lavel 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 leest 900 rps in less than or equal to 10 seconds. The ger.erator voltage and frequency shall be 4360 1 436 volts and 60 1 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.

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I b. At least once per 31 days and after each operation of the diesel I where the period of operation was greater than or equal to I hour 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-D270-1975 has a water and sediment content o'f less then or 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 tested in accordance with ASTM-D975-77, and an impurity level of l

1ess 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:

l l 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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ELECTRICAL POWER SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

b. Demonstrated OPERA 8LE 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:

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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 accelera'es t 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 seconds-after the start signal. The diesel generator shall be started for this test by using the manual start rignal.

5. Verifying the generator is synchtonized, 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

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 l removing accumulated water from the day tank.

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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 l

. ASTM-D270-1975 has a water and sediment content of less than or equal to .05 volume pe.' cent 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-0975-77, and an impurity level of less than 2 mg of insolubles per 100 ml. when tested in accordance with ASTM-D2274-70. A diestl generator is not c9nsidered inoperable on the basis of fuel oil failure to meet thc- 2 mg of insolubles per 100 m1 limit provided that within 14 days, fuel quality can be demonstrated to be within th's t 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 ONOFRE-UNIT 3 3/4 8-3

DESCRIPTION OF PROPOSED CHM GES NPF-10-83 AND NPF-15-83 AND SAFETI AIRLYSIS m is is a request to revise cocpany 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 nodify the text of Section 6.0 -

Administrative Oontrols 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 Attach:nent B Proposed Technical Specifications Unit 2 & Unit 3 See Attachment C Description In general, these changes revise Section 6 - Adrainistrative Controls of San Onofre thaclear Generating Station Units 2 and 3 Operating License Appendix A h chnical Specifications to reflect changes in organization structure which will consolidate and increase executive level attention and oversight of all nuclear activities.

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

A sunraary of ead change "is provided as follows:

1 TECHNICAL

! SPECIFICATION SECTION GANGE SUMIRRY 1.26 Definition of REPORTABLE 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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2-Fig. 6.2-1 & 6.2-2 Revised to reflect the new organization structure.

Table 6.2-1 Revised to reflect the existence of a comon 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 Operations Support Office to the Control Room Area.

6.2.4 St* ~: Supervisor revised to shift Superintendent 6.5.1.6.b Revised per Generic Letter 83-43 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 ectivities.

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 implementing procedures and added reference to 10 CTR review requirement 6.5.2.7 Revised review and approvhl authority of the Station Emergency Plan and its inplementing procedure.s and added ref rence to 10 CFR review requirement 6.5.2.8 Revised Mantger, Nuclear Operations to Vice President and Site Manager, Nuclear Generation Site, 6.5.2.9 Reviced review and approval authority of the PCP, radwaste treatment system changes and the ODCM.

6.5.2.10 Deleted requirement for publishing reports of review activities since each review is individual y documented for the record.

6.5.3.4.g Revised per Generic Lette 8343 l

l j 6.5.3.5.e Revised Manager, Nuclear Operations to Vice President I

and Site Manager, Nuclear Generation Site.

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

6.6 Revised per Generic Intter 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 l

' authority consistent with new organization.

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l 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 far preparation of 6.9.1.9 Radioactive Effluent Release Report to ensure accuracy and conpleteness. Redundancy to OD 3 has been renoved.

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 6.9.1.33 (Old) 6.9.1.14 (Old) Renumbered to 6.9.1.11 6.9.1.12 (New) Added per !RREG-0737, Item II.K.3.17 6.9.2 Clarified Special Reporting requirements 6.10.1.c Revised per Generic Intter 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 Treatrent 6.15.1.1.h System change acceptance consistent with current l G.15.1.2 review and approval process.

l In addition, as a result of the revisions.to NRC reporting requirements outlined in Generic IAtter 83-43, the following 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 __ _

l-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) i 3.4.7 4-24 4-25 Reportable Occurrence changed to SPECIAL REPORr in 30 days pursuant to 6.9.2.

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SECTION 3/4 PAGE NO.

IfD NO. U2 U3 DESCRIPTION 3.S.I.1 8-06 8-06 Cberected reference to diesel generator failure reporting requirement. .

3.11.1.2 11-5 WA 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 changes involve a significant increase in the probability or coneequences of an accident previcusly evaluated?

Response: No Sese 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 i.hese changes.

2. Will operation of the facility in accordance with these proposed

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

Response: lb D 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 changes. ,

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! 3. Will operation of the facility in accordance with these proposed

& anges involve a significant reduction in a margin of safety?

l Response: No S 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 changes.

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Safety and Significant Hazards Determinat. ion Based on the above discussion, Proposed Qianges NPF-10-83 and NPF-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 from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. In addition, it is concluded that: (1) there is reasorable 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 ir. pact of the station on the environment as described in the NRC Final Environmental Statement.

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EXISTING TECENICAL SPECIFICATIONS SAN ONOFRE NOCLEAR GENERATI!G STATION - UNIT 2 i

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i 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 Arta, {

a designated individual) shall be responsible for the Control Room comunand function. A management directive to this effect, signed by the Vice-President of Nuclear Operations shall be :sissued 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 orcsnization 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 in Table 6.2-1.

b. At least one licensed Reactor Operator shall be in the Control Room wnen fuel is in the reactor. In addition, while the unit is in MDDE 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.

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

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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.

e. A site F1 6 Spigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include the Shift Super-i visor and the 2 other members of the minimum shift crew necessary for l safe shutdown of the unit and any pertonnel required for other

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essential functions during a fire emergency, l

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

SAN ONOFRE-UNIT 2 6-1 Amendment No. 4 JULi6 EZ l

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I I I I I VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT ViCE PRESIMNT V1CE PRESIDENT INUCLEAR ENGINEERING ISYSTEM (ENGINEERING & (ADVANCED (FUEL SUFFLYl (POWER SU' PLY)

AND OPERATIONS) DE'.1LOPMENT) CONSTRUCTICN) ENGINEE RING)

I i MANAGER OF . MANAGER OF MANAGER OF MANAGER OF NUCLEAR ENGINEERING, NUCLEAR ENVIRONMENTAL ENGINEERING SAFETY & LICENSING OPERATIONS . AFFAIR $ DESIGN

• I DIRECTOR OF MANAGER, OUALITY i TRAINING RESEARCH AND l

MANAGER DEVELOPMENT ASSURANCE l

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NUCLEAR LICEkSING p y SAN ONOFRE UNITS 2 & 3 SY [MS &D

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COMMITTEE Figwe 8.21 l OFFSITE ORGANIZATION l SAN ONOFRE NUCLEAR GENERATING $TATION = UNIT 2

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_ . _. SNorf 3 CwtutSTRY PERSOceNEL l 1. AT TIME OF APPOlofTMENT TO TNE POSfflOes. SENIUR REACTOR OPERATOR UCEssSE REQUIRED.

2. SENeOR REACTOR UCENSE REQUIRED.

3 COerTROL AND ASSISTANT CONTROL OPERATOstS ARE seOLDERS OF REACTOR OPERATOR UCENSES.

4 lesCLUDES Pir,E rit3TECTIOes.

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Reute 6.2-2 Unit Organization Sen Onofre Nuclear Generting Station Unit 2 l-l \

SAN ONOFRE-UNIT 2 6-3 Amendment No. 4 JUL 16 hi:

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, i Table 6.2-1 MINIMUM SHIFT CREW COMPOSITION l 3.

POSITION NUS ER OF INDIVIDUALS REQ!5 RED TD FILL POSITION MODES 1, 2, 3 & 4 M00ES 5 & 6 SS 1 1 SRO 1 'None l R0 2 1 AD 2 .1 STA 1 None l

SS - Shift Supervisor with a Senior Reactor Operators License on l Unit 2 SR0 - Individual with a senior Reactor Operators License on Unit 2 R0 - Individual with a Reactor Operators License on Unit 2 AD - Auxiliary Operator STA -

Shift Technical Advisor Except for the Shift Supervisor, the Shift Crew Composition may 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew i members provided immediate action is taken to restore the Shift Crew Composi-tion to within the minimum requirements of Table 6.P l. This provision does not permit any shift crew position to be unmanned upon shift change due to an l 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 the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Control Room command function. During any absence of the Shift l l

Superviso- from the Control Room Area shown in Figure 6.2-3 while the unit is t l

in NODE 5 or 6. an individual with a valid SRO or R0 license shall be designated l to assume the Control Room t.osumand function.

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ADMINISTRATIVE CCNTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION ~

6.2.3.1 The ISEG shall 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 ar,eas for improving plant cafety.

COMPOSITION

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

RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintainir" surveillance of plant' activities to provide independent verification" that 6hese activities are performed correctly and that human errors are reduced as much as practical.

t AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, 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 ^.o 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 i

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. gggg 6-5 Amendment No. 15 SAN ONOFRE-UNIT 2

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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 suppiamental 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 C0WITTEE (OSRC)

, FUNCTION ,,

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

COMPOSITION l

6.5.1.2 The Onsite Review Committee shall be composed of the:

Chairman: Station Manager

(. Member: Depsty Station Manager I

Member: Manager, Operations Member: Manag; , Technical Member: Plant Superintendent SONGS Unit 2 & 3 Member: Supervisor of I&C Member: Manager, Health Physics l Member: Supervisor of Chemistry Member: Maneger, Maintenance l l

Member: Supervising Engineer (NSS5, NSSS Support, Computer, or STA)

Member: SanDiegoGasagectricRepresentative, g

Senior Engineer l

ALTERNATES _ ,_

6.5.1.3 All alternate members shall be appointed in writing by the OSRC 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.

1}85 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 experience.

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

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( ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The 0$RC shall meet at least once per calendar month and as convened by the OSRC Chairman or his designated alternate.

DUORUM 6.5.1.5 The a:inimum quorua of the OSRC necessary for the performance of the

05RC responsibility and authority provisions of these Technical Specifications I 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 . w rts covering evaluation and recommendations to prevent recurrence to the Nuclear Safety Group (NSG).

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

c. Review of unit operations to dttact potential nuclear safety hazards.

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

I

e. Review an' d docussatation of judgment 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 enta'ing values of CPC addressable constants outside the allowable range of Table 2.2-2.

i SAN ONOFRE-UNIT 2 6-7

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_ ADMINISTRATIVE CONTROL 5 AUTNORITY 6.5.1.7 The Onsite Review Coeriittee (05AC) shall:

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

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

b. Provide written netification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Manager of Nuclear Operations and N5'i of disagreement between the 05RC and the Station Manager; however, the Station Manager shall have responsibility for resolution of sch disagre=ments pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The Dnsite Review Committee shall maintain written minutes of each 05RC meeting that, at a minimum, document the results of all DSRC activities performed under the respensibility and authority provisions of these technical specifications. Copies spall 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 tNreto, is prepared by a qualified individual / organization. Each such procedure, and changes thereto, shall be reviewed by an individual / group l

other than the individual / group which prepared the procedure, or changes thereto, i but who may be from the same organization as the individual / group which prepared the procedure, or changes thereto.

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

group other than the individual / group which prepared the proposed change, but who may be from the same organization as the individual /g-oup which prepared t.he propped change. Ptsposed 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 sh.111 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 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. l SAN ON0FRE-UNIT 2 6-8 JUL16 h.

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i l ADMINISTRATIVE CONTROLS ACTIVITIES (Continued)

~ 6.5.2.4 Individuals responsible for reviews perfomed 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 tha Station Manager to perfom such reviews.

Each such review shall include a detemination of whether or not additional, ,

l cross-disciplinary, review is necessary. If deemed necessary, such review shall be perfomed .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, 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 The station security program, 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 N5G.

6.5.2.7 The station emergency plan, and implementing procedures, shall be reviewed at lea:;t 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 Station Manager shall assure the performance of a review by a

(

qualified individual / organization of every unplanned onsite release of radio-l active material to the environs including the preparation and fo marding of reports covering evaluation, reconnendations and disposition of the corrective 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 i qualified individual / organization of changes to the PROCESS CONTROL PROGRAM, l OFFSITE DOSE 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 be provided to the Manager of Nuclear Operations and the Nuclear Safety Groie.

6.5.3 NUCLEAR SAFETY GROUP (N5G)

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

P

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SAN ON0FRE-UNIT 2 6-9 Amentiment No. 4

l. ADMINISTRATIVE CONTROLS

. l FUNCTION (Continued)

a. nuclear power plant operations

b. nuclear enginearing.

c. chemistry and radioc'homistry

d. metallurgy

e. instrumentation and control

f. , radiological safety

g. mechanical ard electrical engineering

h. quality assurance practices COMPOSITION

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

! The Supsrviser shall have 2 Bachelor's Degree in Engir.eering or Physical Science and a minimum of six 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 five years of professional level experience in the field of his specialty.

i The NSG shall use specialists from other technical organizations to augment its expertise in the diaciplines of 6.5.2.1. Such specialitts 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.

l 6.5.3.4 'The NSG shall review:

a. The safety evaluations for 1) changes to procedures required by Specification 6.8, equipment or systems and 2) tests or experiments completnad 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, equipmea. or systems which involve-an unreviewed safety question as defined in Section 50.59, 10 CFR.

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

A SAN ON0FRE-UNIT 2 6-10 Amendment No. 4 Jill j 6 E ww -w--- _v- - n-----

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ADM!n:STRATIVE CONTR01.5 _- '

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

e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of inteenal procedures or instructions having nuclear safety significanc2. -

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

g. Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commissica.

l

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

i. Reports and meetings minutes of the Onsite Review Cosaittee.

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

a. The conformance of unit operation t6 provisions contained within the Technical Specificatiens 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.

l c. The results of actions taken to correct deficienciits 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 l

l Assurance Program to reet the criteria of Apper. dix "B", 10 CFR 50, at least once per 24 months.

i

e. Any other area of unit operatien considered appropriate by the ,

Nuclear _ Safety Group or Manager of Nuclear Operations. l

f. The Fire Protection Program and implementing procedures at least l 1

once per 24 months.

i

g. An independent fire protection and loss prevention inspection and 'j audit shall be performed annually utilizing either qualified "offsite licensee personnel or an outside fire protection firm.  ;

! h. An inspection and audit of the fire protection and loss prevention i

( ,

pregram shall be performed by an outside qualified fire censultant

- at intervals no greater than 3 years. l MAY 16 W 6-11 AMEt:0 MINT t:0. 16 SA*4 ONCFRE-UNIT 2

s .

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ADW NISTRATIVE CONTROLS 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 and 6.5.3.5.

RECORDS Report 6.5.3.7 Records of NSG activities shall be prepared and maintained.

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

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MAY1619R' AMEC4I!;T tiO.15 SAN CNOFRE-UNIT 2 6-12 l

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MINISTRATIVECONTROLS 6.6 REPORTABLE OCCURRENCE ACTION ,

6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

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

b. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the 05RC and submitted to the NSG l and the Manager of Nucitar Operations.

l 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety Limit is

, violated:

l

' a. The NRC Operations Canter shall be notified by telephone as soon es 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. A Safety Limit Violation Report shall be prepared. The report shall l be reviewed by the 05RC. This report shall describe (1) applicable i circumstances preceding the violation, (2) effects of the violation i

upon facility components, systems or structures, and (3) corrective l ,

action taken to prevent recurrence.

c. The Safety Limit Violation Report shall be sutrsitted to the Commissici, 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 AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

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

b. Refueling operations.

. c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

a. Emergency Plan implementation.

f. Fire Protection Program implementation.

6-13 SAN ON0FRE-UNIT 2 95 I' D32 l

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l ADMINISTRATIVE CONTROLS

g. PROCESS CONTROL PROGRAM implementation."

h. OFFSITE DOSE CALCULATION MANUAL implementation.

-1. Quality Assurance Program for affluent 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 sat 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 en the unit affected.

c. The change is documented, reviewed and approved by the Station 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 designatad 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 :s 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 return piping only). The program shall include the following:

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

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• "See Specification 6.13.1 MAY i 61989 SAN ONOFRE-UNIT 2 6-14 AMEN 0 MENT NO. 16

AM1HISTRATIVE CONTROLS __

b. In-Flant Radiation Mor.itorino

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A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

(i) 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 cf secondary water chemistry to inhibit steam generator tube degradation. This prgram shall include:

(1) 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 condenser in-leakage, (iv) Procedures for the recording and canagement of data, (v) Procedures defining corrective actions for all off-control point chemistry conditions, and (vi) . A precedure identifying'(a) the authority respcnsible for the interpretation of the data, and (b) the sequence and timing cf administrative events required to initiate corrective action.

. d. Pos't-Accident Samplino A*pregram* which will ensure the capability to obtain and analyze reactor coolant,. radioactive iodines and particulates in plant gaseous affluents, and c'ontainment atmosphere samples under accident conditions. The program

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

6.9 REPORTING REQUIREMENTS ' _.

ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the folicwing reports shall be submitted 10 the NRC Regicnal Administrator unless otherwise noted.

• t:ot required to be implacented until Septecer 1,1923.

SA's ONO RE-UNIT 2 6-15 AMDCENT NO.17 APR 2 91983 I

s ADMINISTRATIVE CONTROLS

STARTUP REPORT l

6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license. (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has ben 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 f based on other commitments shall be included in this report. /g

C.s.1.3 Startup reports shall be submitted within (1) 90 days following d ;A t completion of the startup test program, (2) 90 days following resumption or commencementofcommercialpoweroperation,or(3)9monthsfollowing criticality, whichever is earliest. If the Startup Report does not cover all ,o?

three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary reports F. cW i ~

i shall be submitted at least every three months until all three events have been completed.

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l ANNUAL RE*0RTS*

6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar ,,.rar 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 mrea/yr and their associated manrem exposure according to work and job functions,** a.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 dosimeter, TLD, or l film badge measurements. Small exposures totalli less t reent of i the individual total dose need not be accounted f . In aggre at least 80 percent of the total whole body dose rec 'ved from extet Qou should be assigned to specific major work functi s. CON 7,7..

, iT/(las !

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

==

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

SAN ONOFRE-UNIT 2 6-16 EE 17 m ,

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s ADMINISTRATIVE CONTROLS

, -i ANNUAL RADIOLOGICAL ENVItCNMENTAL OPERATING fiEPORT*

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 cf 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 l 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 ef the plant operation or, 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 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 m n 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 3.12.3.

SEMIANNUAL RADI0 ACTIVE 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.

jon. ISSugo b tal l A single submittal may be made for a multiple uni s The s i

should combine those sections that are common to 6f'.at t.he station; however, for units with separate radwaste systems, the tal sha 1 ,

specify the releases of radioactive material from each unit. - 170fg ,/

SAN ON0FR5-UNIT 2 6-17 FES

• 7 532 t

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s ADMINISTRATIVE CONTROLS 6.9.1.9 The radioactive affluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-cooled Nuclear Power Plants " Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The radioactive effluent release report to be submitted 60 days after

, January 1 of each year shall include an annual summary of hourly meteorological

! data collected cver the previous year. This annual susuary 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 i 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 determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation cosas shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The radioactive affluent release report to be submitted 60 days after l

January 1 of each year shall also include an assessment of radiation doses to j 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 liqcid and gaseous effluents are given in Regulatory l

Guide 1.109, Rev. 1. .

The radioactive effluents release shall include the f information for each type of solid waste shipped offsite during the port pe -

a. Container volume, / k6 ; ,

b. Total curie quantity (specify whether de Wed.by measurene'nt or estimate), '"'e.., .

c. Principal radionuclic'es (specify whether determined asureme,nt .

6r estimate), W'

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

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

f. Solidification agent (e.g., cement, ures formaldehyde).

i SAN ONOFRE-UNIT 2 6-18 FEB : 71932

,0MINISTRATIVE CONTROLS t The radioactive effluent release reports shall ir.clude unplanned releases from the sitit to unrestricted areas of radioactive materials in gaseous and liquid effluents en a quarterly basis.

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

MONTHLY OPERATING REPORT i

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 Conctssion, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month fc110 wing the calende.r sonth 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 radioactive waste treatment systems shall be submitted with the Monthly Operating Repcrt I for the period in which the evaluation was reviewed and accepted by the Onsite Rev'ev Cawaittee.

REFSRTABLE OCCURRENCES 6.9.1.11 The REPOR7ABLE 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 rep' orts may be required to fully describe f"nal resolution of occurrence. In case of corrseted or supplemental reports, a licensee event report shall be completed and reference shall be j

made to the original report date.

P?0MPT NOTIFICATION WITN WRITTEN FOLLOWUP 6.9.1.12 The types of events listed below shall be reported within 2[ hours by takphone and confirmed by telegraph, mailgram, or facsimile transmission to the NRC Regional Administrater, or his designate no later than the' first worir.ing day following the event, with a written followup report within' 14 days. The written followp report sh&11 include, as a minimum ~, a completed copy of a licensee event report fom. Information provided on the. licensee

! event report form shall be supplanented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a. Failure of the reactor protection system or other systems subject to lidting safety system settings to initiate the required protective i

function by the tire a monitored parameter reaches the setpoint specified as the limitirag safety system setting in the technical l specifications or failure to complete the required protective l

l function.

MAY 161983 SA'l CNOFRE-UNIT 2 6-19 RiE C !E.iT NO. If

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

~ cperation subject to a limiting condition for operation is less conservative than the legit' censervative aspect of the Limiting ECendition for Operation established in' the Technical Specifications.  ;

e, v Abnormal degradation'discevarad-in: fuel cladding, reactor coolant pressure boundary,.or primary centainment.

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

, :of reactivity balance under steady state conditions'during power

. operttion greater than or equal to 1% ok/k; a calculated reactivity balance indicating 4 SHtJTDOWMARGIN.less conservative than specified in ths Technical Specifications; shcrt-term reactivity in reases that correspond to a sanctor peried 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.

e. Failure or ralfunction of one or more components which prevents or could prevent, by itself, the. fulfillment of the functional require-ments of system (s) used to cope with accidents analyzed in the SAR.

' f.

Persennel arror or procedural inadequacy which peevents or could prevent, by t'tself, the fulfillment of the functional requirements of s,ystems rdquired to cop's with' accidents analyzed in the SAR.

g .' Conditions arising from natural or eian-made events that, as a direct result of the avant require unit shutdown, operation of safety systams, or other protecthe measures required by Technical Specifications.

h. ' Errcrs discovered in thi transient or accident analyses or in the t

,=ethods used for such analyse's as. described in the. safety analysis raport er in the bases for the Technical Specifications that have or could have permitted reactor operation in a manner less conservative than assuraed in the analyses.

1. Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manaar les~s conservative than assumed in the accident analyses in thc. safety analysis report er Technical Specifications bases; or discovery during ur.it life of conditions not specifically considered in the safety analysis report or Technical Specifications that

- requir'o retdedial? ccion or corrective measures to prevent the existence or development of an unsafe cohdition.

j. 0ffsite releases cf radioactive ' materials in liquid and gaseous efflu-ents that exceed the limits of Specifications 3.11.1.1 or 3.11.2.1. i i

i t

k. Exceeding the limits' in Specification 3.11.1.4 or 3.11.2.6 for the L

storage ef. radioactiva matertab in the listed tanks. The written l l

'~ follow-upireport shall include a schedule and a description of acti-vitie:; planned and/or taken to reduce the contents to within the specified limits. ,

1. Fai re of.one er more pressurizer safety valves. t9( i 61983 6-20

1. M ENT N3. 16 SAN ONOFRE-UNIT ~2 T -

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( 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 Administrator within thirty days of occurrence of

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

l l a. Reactor protection system or engineered safety feature instrument l settings which are found to be less conservative than those estab-lished by the Technical Specifications but which do not prevent the ful'?illment of the functional requirements of affected sysums.

b. Cond.itions leading to operation in a degraded mode pemitted by a t Limiting Conditica for Operation or plant shutdown required by a Limiting Condition for Operation.

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

d. Abnomal 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 (I-5) and the AT&SF railway shall be mor.itored and the results submitted to the NRC Regional Administrator once every three years.

I l

SPECIAL REPORTS l

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

6.10 RECORD RET 6NTION l In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least

+he minimum period indicated.

SAN ONOFRE-UNIT 2 6-21 g ,' j -

e .

(

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 principal items of equipment related to nuclear safety,

c. All REPORTARLE OCCURRENCES submitted to the Commission.

d. Records of surveillance activities; inspections and calibrations requimd 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.

l

h. Records of annual physical inventory of all sealed source asterial

~

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 -

ande to systems and equipment described in the Final Safety Analysis -

Report.

b. Records of now and irradiated fuel inventory, fuel transfers e'ul assembly burnup histories.

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

d. Ra;:ords of gaseous and liquid radioactive material released to the j 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.

g. Records of training and qualification for current meat.ars of the f: unit staff.

1

-i.

l SAN ONOFRE-UNIT 2 6-22

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k 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. Reconis of reviews performed for changes made to procedures or 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 sne bers listed in Tables 3,7-4a and 3.7-4b including the data at which the service 1,1fe commences and associated installation and maintenance records.

a. Records cf secondary-water ' sampling and water quality.

6.11 RADIATION PROTECTION PROGRAM' Procedures for personnel radiation protection shall be prepared consister.t 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 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or "alars signal" required by

' paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in whir.h the intensity of radiation is graatar than 100 aren/hr but less than 1000 erwei/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)*. Ary individual or group cf individuals permitted to enter such areas shall be provided with or merampanied by one or more of the following

a. A radiation monitoring device which continuously indicates the radiation cose rate iri the area.

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

l

" 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 following approved plant radiation protection procedures for entry ints high radiation an as.

SAN ONOFRE-UNIT 2 6-23 . . . ,

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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 Exposurt 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 administrative control of the Shift Supervisor on duty and/or health physics supervision. {

Doors shall remain locked except during periods of access by personnel uncer an approved REP which shall specify the dose rate levels in the 1smediate work area and the maximum allowable stay time for individuals in that a'rea. For individual areas accessible to personnel with radiation levals such that a major portion of the body could receive in one hour a dose in' excess of 1000 mese** 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 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 cualified in' radiation protection procedures to provide positive exposure control over the activities within the ama.

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 l

Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:

! a. Sufficiently detailed information to totally suoport the rationale l for the change without benefit of additional or supplemental

! information; i b. A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; 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.

l

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

7

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

\. radioactive waste.

SAN ONOFRE-UNIT 2 6-24 Arnendment No. 4

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l Art:It,IST:.ATIVE CONTROLS

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6.14 0::5ITE 005E CALCULATICN N NUAL (00CM) 6.14.1 The CDCM shall be approve'd 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:

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 pa.ckage 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 rsiculations or setpoint tieterminations; 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 05RC.

6.15 MAJOR CHANGE 3 TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and solic) t 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 Peport for the period in which the evaluation was reviewed by the 05RC.

The discussion of each change 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 cascription of the eouipment, 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

's quantity of solid waste that differ from those previously -

predicted in the license application and acent.me..ts thereto; 6-25 AME:QMEtiT fio.15 SAN O!CFRE-UNIT 2 MAY 161981

(

ADMINISTRATIVE CONTROLS

a. An evaluation of the change which shows the expected maximum.

exposures to individual in the unrestricted area and to the general pplation that differ from those previously e1timated in the license application and amendments thereto;

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

g. An estimate of the exposure to plant operating personnel as s result of the change; and

h. Documentation of the fact that the change was reviewed and found acceptacle,by the OSRC.

2. Shall becosk effective upon review and. acceptance by the 0$RC.

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l SAN ONOFRE-UNIT 2 G-26 '!

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INSTRUMEKTAT10N RAD 10 ACTIVE LIQUID EFFLUENT MONITOR]NG INSTRUMENTATION LIMIT 2R3 CON?3 TION FOR ODERATION ,

3.3.3.8 The radioactive lievid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceedes. The alarm /

trip setpoints of these channels shall be determined in accordance with the

! 0FFSITE DOSE CALCULATION MANUAL (ODCM).

ADPLICABILITY: At all times."

ACTION:

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

b. With less than the minimum 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 OPERASLE status within 30 days, explain in the next Semi-

. annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

l l

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

SURVEILLANCE REQU]REMENTS l

l 4.3.3.8.1 Each radioactive liquid e7719ent monitoring instrumentation channel l shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE l CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the

! frequencies shown in Table 4.3-8.

4.3.3.6.2 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 j limits of Specification 3.11.1.1.

l l

! $5ee Special Test Exceptien 3.10.5.

1 i SAN ONOFRE-UNIT 2 3/4 3-E3

"* e 2 N51RUME NT AT10N

( Rt.CIDA*TIVE GASIOUS EFFLUENT MONITOR]N INSTRUMENT ATION LIMITIN CONDIT20N FOR 0*ERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarr./ trip setpoints of these channels shall be determined in accordance with the DDCM.

l ADPLICAPILITY: 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 affluents monitored by the affected channel or declare tne channel inoperable.

, b. With less than the minimum number of radioactive gaseous effluent

! monitoring instrumentation channels OSERABLE, take the ACTION shown in Table 3.3-13. Additionally, if tr e 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.

'INE'provisionsofSpecifications 3.0.3, 3.0.4, and 6.9.1.13b are not applicable.

SUF.VEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated CPERABLE by perfora.ance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frecuencies shown in Table 4.3-9.

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'See Special Test Exception 3.10.E I SAN ONDFRE-UNIT 2 3/4 3-6B l

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s. F.EAC OR CO3LaNT SYSTEw.

A ~IOfs: (Continued)

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

d. With the specific activity of the primary coolant greater than 1.0 r.icrecurie/ gram DOSE EQUIVALENT I-131 or g* eater than 100/I zicrocuries/ gram, perform the samcling and analysis recuire-i ments of item a a) of Table 4.4-4 until the specific activity c' the l primary coolant is restored to within its limits. A REPORTA5LE OCCURRENCE shall be prepared and submitted to the Commission pursuant to Specification 6.9.1. This report shall contain the results of the specific activity analyses together with the folloeing information:

1. Reactor power history starting AS hours 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the, first sample in which the limit was exceeded, and

5. Tne time duration when the specific activity of the primary coolant exceeded.1.0 microcuriefgram DOSE EQUIVALENT I-131.

SURVEILLANCE REQUIREMENT 5 I

i 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 l

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SAN ONOFRE-UNIT 2 3/4 4-24 c

I'

- ELECTRICAL POWER $YSTE".5

$URVEILLANCEREOUiREMENTS (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 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 simultanecusly, during shutdown, and verifying that the diesel generators accelerate to at least 900 rpe in less than cr equal to 10 seccads,

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 sodi m hypochlorite solution or the equivalent, and

2. Performing a pressure test of 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.B.1.1.3 ReDorts - All diesel generator failures,* valid or non-valid, shall be reported to the Commission pursuant to Specification 6.9.1. Reports of c

diesel generator failures shall include the informaticn recommenced in Regula-tory Position C.3.b of Regulatory Guide 1.106, 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 equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108. Revision 1 August 1977.

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l SAN ON3FRE-UNIT 2 3/4 8-6 ,,

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' j RADIDACTIVE EFFLUENTS DOSE I

LIMITING CONDITION FOR OPERATION 3.11.1.2' The dose or dose commitment to an indivioual 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 arem to the total body and to less than or equal to 5 ares to any organ, and

b. During any calendar year to less than or equal to 3 arem to the

. total body and to less than or equal to 10 ares to any organ.

APPLICABILITY: At all' times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Specif1 cation 6.9.1, prepare and subrit tc the Commission within 30 days, pursuant to Specification 6.9.2, a l Special Report which identifies the cause(s) for exc?eding the'11mit(s) and defines the corrective actions taken to reduce the releases and the 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.

I I

SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations. Caulative dose contributions from liquid effluents shall De seterzined in accordance with the CDCM at least once per 31 days.

1 I

{ SAN ONOFRE-UNIT 2 3/4 11-5

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3/a.12 RtOIDLOGICALENVIRONMENTALMONITORI03 3/4.12.1 MDNITORIN3 PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

p*PLICASILTTY: .At all times.

ACTION:

a. 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 Radiclogical Operating Report, a description of the reasons for not conducting the pr1pgram as required and the plans for preventing a recurrence.

t. With the level of radioactivity in an envirg sental sampling medium exceeding the reporting levels of Table 3.12-2 when averapec over any calendar quarter, in lieu of any other report required by Specification 6.9.1, prepare and subrit to the Commission 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:

cencentration (1) , concentratisn (2) + * * *> 1.0 limit level (1) limit level (2) -

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

and 3.11.2.3. This report is not required if the measured level *of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With fresh leafy vegetable samples or fleshy vegetable samples unavail-able from one or more of the sample locations required by Tab 1r. 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 which identifies the cause of the unavail-l a*111ty 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 free which the replacement semples were obtained are added to the environmental monitoring program as replacement locations.

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

i 5AN ON3FRE-UNIT 2 3/4 12-1 55 .' . . . .

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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 Conbrol 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 0FFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown in Figure 6.2-1.

MIT 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 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 Ir.ast one licensed Senior Reactor Operator shall be in the Contrcl Room area identified as such on Table 6.2-1.

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

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

, during this operation.

e .,

A site Fire Bgigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include the Shift Super-visor and the 2 other members of the mini us shift crew necessr_ry 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.

HOV i519B2

SAN ON0FRE-UNIT 3 6-1

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued)

f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perfo m safety-related functions; e.g. , senior reactor operators, reactor operators, 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 nomal 8-hour day, 40-hour week while the plant is operating.

However, in the event that unforesean problems require substantial amounts of overtinee to be used, or during extended periods of shut-down for refueling, major maintenance or major plant 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 <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

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

3) A break ~of at least eight hours should be allowed between work periods, including shift turnover time.

4) Except during extended shutdown periods, the use of overtime i

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

( Any deviation from the above guidelines shall be authorized by the ,

i Station Manager, his deputy, the Manager, Operations or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Station Manager or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

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, ' RADW ASTE SUPERVISOR l SUPERVISING l SUPEnveSOR OF 9 I NSSS ENGINE!R NUCLEAR PLANT SUPPORT , DOS 18aETRY i

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" SHIFT TECH.

2 SUPERylSOR

= GROUP SUPE ISO;ts SUPERvtSOR COO O A

' m SUPERVISOR

- COORD4NATORS FOREMAfe Et;*ERVISOR E " OF 3 CHEMISTRY SN6FT PERMONNEL i ~

i

1. AT TIME OF APPOlaf7 MENT TO TME POSITIOtt. SENIOR REACTOR OPERATOR LICENSE R l

2. SENIOR REACTOR UCENSE REQUIRED.3. CONTROL AND ASSISTANT CONTR

4. IIICLUDES FIRE PROTECTION. ,

l r

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' Figure 6.2-2 i

Unit organization San Onofre Nuclear Generating Station - Unit 3 g

$41 SAN ONOFRE-UNIT 3 6-4 i- - - - - - - - _ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _ _ _ _ _ _

= ,

1 Table 6.2-1 MINIMUM SHIFT CREW COMPOSITION WITH UNIT 2 IN MODE 5 OR 6 OR DE-FUELED POSITION NUleER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES.1, 2, 3 & 4 M00ES 5 & 6 55 l' 1*

SRO 1 None RO 2 l b

.a0 2 2 STA 1 None WITH UNIT 2 IN MODES 1, 2, 3 OR 4 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 8

SS 1 l(' None

~

SRO RO 2 1 D 1 A0 2 8 None STA 1 a/ Individual may fill the same position on Unit 2 bf One of the two required individuals may fill the same position on Unit 2.

i SS - Shift Supervisor with a Senior Reactor Operators License on Units 2 and 3 SRO - Individual with a Senior Reactor Operators License on Units 2 arc 3

! RO - Individual with a Reactor Operators License on Units 2 and 3

! AO - Auxiliary Operator STA -

Shift Technical Advisor l

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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew 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 Figure 6.2-3 while the unit is in MCDE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid SRO license shall be designated to assume l the Centrol 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 MODE 5 or 6, an individual with a valid SR0 or R0 license shall be designated to assume the Control Room command function.

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I ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

- FUNCTION

'l 6.2.3.1 The ISEG shall 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 . '

l- for improving plant safety.

COMPOSITION 6.2.J.2 The ISEG shall be composed of at least five dedicated full-time engineers. Each shall have a Bachelor's Degree in Engineering or Physical Science or equivalent and at least two years professional level experience in his field. Off-duty qualified Shift Technical Advisors may be used to fulfill this requirement.

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

• that these activities are perforised correctly and that human errors are reduced as much as practical.

AUTHdRITY 6.2.3.4 The ISEG shall make detailed recossandations for revised procedures, 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.A SHIFT TECHNICAL ADVISOR The Shift Te:hnical Mvisor shall provide technical support to the Shift Superviser 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. NI SAN ONOFRE-UNIT 3 6-7 . .

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l I

l ADMINISTRATIVE CONTROLS .

l 6.4 TRAINING I '

!. 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 L 6.5.1 ONSITE REVIEW COMMITTEE (0SRC) .

i FUNCTION r

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

l COMPOSITION l

6.5.1.2 The Onsita Review Committee shall be composed of the:

Chairman: Statior. Manager 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.

Member: - Manager, Maintenance Member: Supervising Engineer (NSSS, NSSS Support.

- Computer, or STA)

Member: 'SanDiegoGas&gectricRepresentative, ,

Senior Engineer ALTERNATES 6.5.1.3 All alternate members shall be appointed tr. writing by the OSRC Chairman to serve on a temporary basis; however, no more than two alternates l

, shall participate as voting members in 0$RC activities at any one time.

l l

(1}BS degree in Engineering or Physical Science plus at least four years pro-fossional level experience in his field. At least one of the four years experience shall t*e nuclear power plant experience."

my i51982 SAN ON0FRE-UNIT 3 6-8 ,

. o r

ADMINISTRATIVE CONTR0'.5 MEETING FREQUENCY 6.5.1.4 The 05RC shall meet at least once per calendar month and as convened

~by the OSRC Chairman or his designated alternate.

000 RUM 6.5.1.5 The minimum quorum of the O'SRC 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 4

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 reccamendations to prevent recurrence to the Nuclear Safety Group (hSG).

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

i c. Review of unit operations to detect potential nuclear safety hazards, f- 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 judgment concerning prolonged operation in i

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 ~

l 6.5.1.7 The Onsite Review Committee (OSRC) shall:

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

b. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 4

resolution of such disagreements pursuant to 6.1.1 above.

c 1 5 1982 SAN ON0FRE-UNIT 3 6-9

,.,e., .- , -. ..-r

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f L

1 ADMINISTRATIVE CONTROLS R

__ECORDS

-6.5.1.8 The Onsite Review Committee shall maintain written minutes uf each OSRC meeting that, at a minimum, document the results of all OSRC activities l . performed under the responsibility and authority provisions of these technical l specifications. Copies shall be provided to the Nuclear Safety Group.

6.5.2 TECHNICAL REVIEW AND CONTROL j 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.

i 6.5.2.2 Proposed changes to 1.he Appandix '"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-l 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.

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, the Manager, Technical, the Manager, Opera-tions, the Manager, Maintenance, the Deputy Station Manager or the Manager, l

Health Physics as previously designated by the Station Manager.

6.5.2.6 The station security program, and implementing procedures, shall be reviewed at least once per 12 months. Recommended change = shall be approved by the Station Manager and transmitted to the Managet of Nuclear Oper4tions and to the NSG.

NOV 1.5'1982 SAN ON0FRE-UNIT 3 6-10

o ADMINISTRATIVE CONTROLS i l

i i

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 i to the NSG.

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 radio-active material to the environs including the preparation and forwarding of i

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 Station Manager shall assure the performance of a review by a qualified individual / organization of changes to the PROCESS CONTR3L PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste 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 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 I

b. nuclear engineering

c. chemistry and radiochemistry ti. metallurgy

e. instrumentation and control

f. radiological. safety

g. mechanical and electrical engineering

h. quality assurance practices ,

NOV 1519e:

SAN ONOFRE-UNIT 3 6-11 c.

ADMINISTRATIVE CONTROLS COMPOSITION 5.5.3.2 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 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 NSG shall use specialists from other technical organizations to augment its expertise in the disciplines of 6.5.2.1. Such specialists shall meet l

the same qualification requirements as the NSG members.

j l CONSULTANTS L 6.5.3.3 Consultants shall be utilized as detersined by the NSG Supervisor to

! provide expert advice to the NSG.

Ef!EW 6.5.3.4 The NSG shall review:

l

a. The safety evaluations for 1) changes to procedures required by Specification 6.8, equipment or systems and 2) tests or, experiments s

completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not con:;titute 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.

l

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

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

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

i lica..re 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.

NOV 1 & 1982 SAN ONOFRE-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 encompass:

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

b. , The perfomance, training and qualifications of the entire unit

. staff at least once per 12 months.

c. The resuics 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 "B", 10 CFR 50, at least once per 24 months.

~

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

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

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

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

l AUTHORITY-l l

6.5.3.6 The h5G shall report to and advise the Manager, Nuclear Engineering

. and Safety on those areas of responsibility specified in Sections 6.5.3.4 and 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 ta the Station Manant and to the management positions responsible for the areas audited.

i MOV 15 BB2 SAN ONOFRE-UNIT 3 6-13 .

I L.. - _ _ _ . . ._ _ _ _ . _. _ _ _ _. _ _ _-__.. _ _ .- ~. . _ _ _ . _ _ _ _

(

ADMINISTRATIVE CONTROLS

6. 6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken.for REPORTABLE OCCURRENCES:

a. The Commission shall be'not'ified and/or a report submitted pursuant to the requirements of Specification 6.9.

b. Each REPORTA8LE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the OSRC and submitted to the NSG and the Manager of Nuclear Operations. ,

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

a. The NRC Operations Centar shall be notified by telephone es soon as possible and in all cases within one hour. The Nar.ager of Nuclear Operations and the NSG Chairman shall be notified wi?.hin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. A Safety Limit Violation Report shall be prepared. The report shall ,

be reviewed by the 0$RC. 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

.Consission, 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 Cosmiission.

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

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

i-l b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

l d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protectiori Program implementation.'

NOV i W2 '

SAN ONOFRE-UNIT 3 6-14

m ADMINISTRATIVE CONTROLS

g. PROCESS CONTROL PROGRAN implementation.*'

h. 0FFSITE DOSE CALCULATICM MANUAL 1aplenentation.

1. Quality Assurance Program for efflugt and environmental monitoring,  !

using the guidance in Regulatcry Guide 4.15 Rev.1. February 1979. l

~

' f. Modification of Core Ptstection Calculator (CPC) Addressable l Constants.

NOTE: Modification to the CPC addressable constants. based on information obtained through the Plant Computer - CPC data link shalt not be mad without prior' approval or 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) the Manager Operations (3) the Manager, Maintenance, (4) the Manager, Technical, or (5) the Manager. Health Physics as previously designated by tha 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.

c. The changa.is decw.e'nted, reviewed and approved by,the Station l

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

a. Primary Coolant Sources Outside Contairmwnt _

A program ts reduce leakage from those p'ortions of systems outside containment that could contain highly radioactive fluids during a j

serious transient or accident to as low as practical levels. The

- systems ' include the high pressure safety injection recirculation, the shutdown ecoling system, the reactor coolant sampling system

( .

(post-czcident samp11ag piping only), the contain.sent spray system,

' the radioactive waste gas system (por,t-accident sampling return l

pipittg only) and the liquid redweste systen (post-accident sampling l return piping only). The program shall include the following:

j l _(1) .Freventive maintenance and periodic visual inspection ,

l

' - requirements', and 1(11) Integrated leak test requirements for-each system at refueling cycle intervals or less.

• 5ee Specification 6.13.1 HOV 15 BB2 SAN ONOFFsE-UNIT 3 6-15 .

~

t.Li'J:;15TP.ATIVE CONTROLS -

c. In-Plant Radiatien lionitorino A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident condi t,i ons. Th'is program shall include the followihg:

(i) 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'measura the values 'of the criticai 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-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 Samoling 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. The program

• shall include the training of personnel, the procedures for sampting and analysis and the provisions for maintenance of sampling and analysis equipment.

. 6.9 REPORTING REQUIREMENTS __

ROUTINE REPORTS AND REPORTABl.E OCCURRENCES 1

6.9.1 In addition to the applicable reporting requirements uf Title 10, Code

.- of Federal Regulations, the following reports shall be submitted to the ~

NRC Regional Administrator unless otherwise noted.

• Not required to be implemented until Septecher I; 1953.

IM 2 9 Y

, ., j S A*! 0:.0FP.E-l.' NIT 3 6-16 A!smslT No. 5. l

- ADMINISTRATIVE CONTROLS i STARTUP REPORT

6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel

, supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the 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 i actions that were required to obtain satisfactory operation shall also be

! described. Any additional specific details required in license conditions 4

based on other commitments shall be included in this report.

6.9.1.3 Startup reports sha';1 be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of coensrcial power operation, or (3) 9 months following initial criticality, whichever is earliestr.. 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 months until all three events have ,

been completed.

l

! ANNUAL REPORTS

• 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year l

following initial criticality.

6.9.1.5 Reports esquired 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 menrem exposure according to work and job functions,** e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance l

(describe maintenance), waste processing, and refueling. The dose assignments

! to various duty functions any be estimated based on pocket dosimeter, TLD, or l film badge seasurements. 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.

~

" 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.

==

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

i NOV 15 382 SAN ON0FRE-WIT 3 6-17

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l ADMINISTRATIVE CONTROLS i

ANNUAL RADIOLOGICAL ENVIRONMENTAL DPERATING REPORT

• 6.S.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 followirig initial criticality.

6.9.1.7 The annual radiological environmental operating reports shall include sammaries, 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 hamful 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 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 3.12.3.

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REP 01T*

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 t

first report shall begin with the date of initial criticality.

l "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; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

g 15 s82 SAN ONOFRE-UNIT 3 6-18

1 ADMINISTRATIVE CONTROLS i

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 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 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 suomiary 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 determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (00CM).

The radioacti te 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 effluents are given in Regulatory Guide 1.109, Rev. 1.

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

a. Container volume,

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

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

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

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

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

NQ16 682 SAN ON0FRE-UNIT 3 6-19 1-,e- v.-- ---- --w--e - - - _ m - - - , . -,- ,.., , , - - - we.-w--- , ee m -, , - . - - - - - . - - - - - - - . - - - - - - - - - - - - - ----v-,--- ---,e-w.y--

l l

l l

l ADMINISTRATIVE CONTROLS l l

l The radioactive affluent release reports shall include unplanned releases from l the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.

The radioactive effluent releas , reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) t;,de 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 Director Office of ResouNe Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the

' Regional Administrator of the Regional Office of the Kic, no later than the 15th of each wonth following the calendar month covered by the report.

Any changes to the 0FFSITE DOSE CALCULATION MAKUAL 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 submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the Onsite Review Committee.

REPORTA8LE OCCURRENCES 6.9.1.11 The REPORTABLE 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 corrected 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Dy telephone and confined by telegraph, railgram, or facsimile transmission to the Regional Administrator of the Regional Office or his designate no later than the first working day following the event, with a written followup report within 14 days. The written followup report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the l

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

a. Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety system setting in the technical

(

specifications or failure to complete the required protective function.

NOV 151982 l SAN ON0FRE-UNIT 3 6-20 l

ADMINISTRATIVE CONTROLS

b. Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation 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 involving disagreement wi.th 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 in the Technical Specificatipns; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5% Ak/k; cr occurrence of any unplanned criticality,

e. Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system (s) used to cope with accidents analy:M)in the SAR.

f. Personnel error or procedural inadequ: y which prevents or could prevent, by itself, the fulfillment of che functional requirements of systems required to cope with accidents analyzed in the SAR.

g. Conditions arising froe natural or man-made evente that, as a direct result of the event, require unit shutdown, operation of safety systems, or other protective measures required by Technical Specifications.

h. Errors discovered in the transient or accident analyses or in the methods used for see5 analyses as described in the safety analysis report or in the bases for the Technical Specifications that have or could have pemitted reactor operation in a manner less conservative than assumed in the analyses.

1. Performance of structures, systems, or components that requires 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 discovery during unit life of conditions not specifically considered in the safety analysis report or T6chnical Specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

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.

k. Exceeding the limits in Specification 3.11.1.4 or 3.11.2.6 for the storage of radioactive materials in the listed tanks. The written follow-up report shall include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.

1. Failure of one or more pressurizer safety valves. .

e,y i 5 1982 SAN ONOFRE-UNIT 3 6-21

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ADMINISTRATIVE CONTROLS _

c THIRTY DAY WRITTEN REPORTS 6.9.1.13 The types of events listaa 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. Information provided on the licensee event report fom shall be supplemented, as needed, by additional narrative material 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 r 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 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 caterial 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 5pecial reports shall be submitted to the NRC Regional Administrator within the time period specified for each report.

6.10 RECORD RETENTION 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.

gy 151982 SAN ONOFRE-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 principal items of equipment related to nuclear safety,

c. All REPORTA8LE 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 invantory 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 I

assembly burnup histories.

l c. Records of radiation exposure for all individuals entering radiation i 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.

pvi51982 l

SAN ONOFRE-UNIT 3 6-23

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 sede to procedures or 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 srubbers listed in Tables 3.7-4a and 3.7-4b including the date at which the service life commences and associated installation and maintenance records.

a. Records of secondary water <ampling and water quality.

6.11 RADIATION PROTECTION PROGRAM e 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 HIGH RADIATION AREA 6.12.1- In li2u 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 ares /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. 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 alares when a preset integrated dose is received. Entry into such areas with this monitoring device i

may be made after the dose rate 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 following approved plant radiation protection procedures for entry into high radiation areas.

NOV 15 B82 6-24 SAN ONOFRE-UNIT 3 ,

• F l

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.

1 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 mres shall be provided with locked doors to <

prevent ur. authorized 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 arem*"

that are located within large areas, such as PWR containment, where no enclosure exists for purposes of lock 1ng, 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 specificatinn 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)

I 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 1

made. 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 confonsance of the solidified waste product to existing criteria for solid wastes; 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 OSP.C.

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

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

c 1 5 1982 SAN ON0FRE-UNIT 3 6-25

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ADMINISTRATIVE CONTROLS 6.14 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 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 infomation. 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 ny 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 solid) 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid):

l l

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. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

b. Suff.icient detailed infomation to totally support the reason

' for the change without benefit of additional or supplemental infomation;

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

l An evaluation of the change which shows the predicted releases

~

d.

[ of radioactive materials in liquid and gaseous effluents and/or l

I quantity of solid wasta that differ from those previously I predicted in the license application and amendments thereto; ,

i SAN ONOFRE-UNIT 3 6-26 1 .. ,, .

)

i

- 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 wp11 cation and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid 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 riant operating personnel as a result of the change; and

h. Documentation of the fact that , :hange was reviewed and found acceptable by the OSRC.

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

s HOV i 5 52 5AN ONOFRE-UNIT 3 6-27

f -

INSTRUMENTATION SADI0 ACTIVE LIOUID ENFLUENT MONITORING INSTRUMENTATION

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 alarm / trip setpoints i.et to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alare/

trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (00CM).

~ ~

APPLICABILITY: At all times.

ACTION: ,

4. 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 declat-e the channel inoperable.

(- th. With less than the minimum 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 l

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

l 4.3.3.8.2 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at least one circulating water pump shall be determined to be operating and providing dilution to the discharge structure inhenever dilution is required to meet the site radioactive effluent concentration -

limits of Specification 3.11.1.1.

L .

g0v 15 N l SAN ONOFRE-UNIT 3 3/4 3-64 L ,_

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.L INSTRUMENTATION -

RADI0 ACTIVE GASE005 TFFLUENT SONITORING INSTRl#tENTATION l 1

l LIMITING CONDITION FOR OPERAf!ON 1

-3.3.3.9 The radioactive gaseous effluent monitoring instrimientation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / 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 l* ACTION:

s. With a radioactive gaseous effluent monitoring instrumentation I channel alam/ trip setpoint 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 l 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 applicable.

SURVEILLANCE REQUIREMENTS

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

l

• Continuous monitoring and sampling of the containment purge exhaust directly from the purge stack shall be provided for the low and high volume (8-inch and 42-inch) containment purge prior to startup following the first refueling outage. Containment airborne monitor 3RT-7804-1 or 3RT-7807-2 and associated

, sampling media shall perform these functions prior to initial criticality.

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

l yy:151981 1 SAN ONOFRE-UNIT 3 3/4 3-69

l V REACTOR COOLANT SYSTEM i

ACTION: (Centinued)

ICDES 1, 2, 3, 4 and 5:

d. With the specific activity of the primary coolant greater than 1.0 microcurie / gram DOSE EQUIVALENT I-131 or greater than 100/E microcuries/ gram, perform the sampling and analysis require-ments of item 4 a) of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits. A REPORTABLE OCCURRENCE shall be prepared and submitted to the Commission pursuant to Specification 6.9.1. This report shall contain the results of the specific activity, analyses together with the following irformation:

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

2. Fuel burnup by core region, .

3. Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first

- sample in which the limit was exceeded,

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

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

I . .

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

l

( .

ytN i 5 m2 SAN ONOFRE-UNIT 3 3/4 4-25

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- ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) ,

13. Verifying that the automatic load sequence timer is OPERABLE i with the interval between each load block within f,105.of its design interval. l

. l

14. Verifying that lockout relay K23 prevents diesel ger,arator '

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 rpm in less than or equal to 10 seconds.

f. At least once per 10 years by:

1. Draining each fuel o'! storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution or the equivalent, :.nd

~

2. Performing .a pressure test of those portions of the diesel fuel

(- *

. oil system designed to Section III, sut,section ND of the ASME Code at a test pressure equi to 110 percent of the system design pressure.

. 4.8.1.1.3 Reoorts - All diesel generator failures, valid or non5 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 .

nimiber of failures in the last 100 valid tests (on a per nuclear unit basis) -

is greater than or equal to 7 the res. ort shall be supplemented to include the add' tional information recommended in Regulatory Position C.3.b of Regulatory

Guide 1.108. Revision 1, August 1977. -

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SAN ONOFRE-UNIT 3 3/4 g.6 Nk ,

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3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 9CNITORING PROGRAM

@ ITING CONDITION FOR OPERATION

3.12.1 The radiological environmental monitoring program shell be conducted l as specified in Table 3.12-1. '

APPLICABILITY: At all times.

ACTION:

i a. With the radiological environmental wonitoring 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 Con-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 Coenission within 30 days from the and 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 submittted if:

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

When radionuclides other than those in Table 3.12-2 are detected and i are the result of plant effluents, this esport 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 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 from 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 Commission within 30 days, pursuant to Specific-atton 6.S.2, a Special Report which identifies the cause of the unavail- _

ability of samples and identifies locations for obtaining replacement l . samples. The tacations from which samples were unavailable may then i be deleted from those required by Table 3.12-1, provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations.

(i d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

NOV i5 582

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SAN ONOFRE-UNIT 3 3/4 12-1

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4 9

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AITACHMENT C PROEOSED TECENICAL SPECIFICATIONS SAN ONOFRE NOCLEAR GENERATING STATION - UNITS 2 AND 3 4

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DEFINITIONS PURGE - PURGING 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 required to purify the confinement.

RATED THER E L POWER 1.24 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3390 left.

REACIOR TRIP SYSTEN RESPONSE TIME 1.25 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the 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 REPORPABLE EVENT shall be any of those conditions specified in 50.73 to 10 CFR Part 50.

SWJIDCE MARGIN 1.27 SHUTDOW MARGIN shall be the instantaneous amount of reactivity 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 assenbly of highest reactivity worth which is assumed to be fully withdrawn, and (2) no change in .

part length control element assembly position.

ScramRE - . -

1.28 The digital conputer SOFTWARE for the reactor protection system shall be the program codes including their associated data, documentation and procedures.

SOLIDIFICATION _ _

l l.29 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, imobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

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

SAN ONOFRE-INIT l

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ADMINISTRATIVE COtCROLS 6.1 RESPONSIBILITY 6.1.1 % e Station Manager shall be responsible for overall unit operation and shall delegate in writing tt.e succession to this responsibility during his absence.

6.1.2 2e Shift Superintendent (or during his absence from the Control Room Area, a designated 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 reissued to all site / station personnel on an annual basis.

5.2 ORGANIZATION 0FFSITS 6.2.1 W e offsite organization for unit management and technical support shall be as shown in Figure 6.2-1. .

UNIT STAFF 6.2.2 W e 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 conposition shown in Table 6.2-1.

t l 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 l

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.

I c. A health physics te&nician# shall be on site when fuel is in the reactor.

l

. d. All OORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator l

Limited to Fuel Sandling who has no other concurrent responsibilities during this operation.

e. A site Fire Bgigade of at least 5 members shall be maintained onsite at all times.' W e Fire Brigade shall not include the Shift l

Superintendent and the 2 other rembers of the minimum shift crew

! necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

l

1. 2e 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to ac-Aate unexpected absence provided inmediate action is taken to fill the required positions.

SAN ONOFRE-UNIT

%9

O I Chairman of the Board '-

l ,

Executive t Vice President l l

Senior i

Vice President Vice President Vice President Vice President (Engineering Vice President & Site Manager (Nuclear Englaser- Vice Prootdent and (Power Supply) (Nuclear ing, Safety and (Fuel Supply)

Construction) Generation Site) Licensing) i Managw, oygear '

Manager, Mana,or, Engineering -

Nuclear --

Nuclear Design erst n Licensing Engineering Manager, Opmat'ene nd

,y, ,,agered "*"*"6 Quality M.a-e -i a ,., ;;- -

..e.,ance N.uc,

.e,lear 1

I Manager. Nuclear Manager. -

Budgets and -

Safety c=,

co. cent,ei o,e. ,

~~~~~~ ~ ~~

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• i Manage '

s.n one,r, ,e Unite 2 & 3 Ta h %

Station on Sue wrweing

"* ' Manager 58te Staff C m t se ISE M MmemWWM M MMMMMMMmmmmmemWWW6 FIGUnE s.2-t OFFSITE ORGANIZATION SAN ONOFRE NUCLEAR GENERATING STATION

I St tion Canager R _

Deputy Station Manager i

l I Manager, Manager, Manager,

Station Emergency Compliance Station Security i Preparedness I

I I I I Manager, Manager, Manacer, Manager, Health Physics Technicat Operations Maintenance I

, Health Physics Supervising Plant ' Supervisor of

{

Supervisor -

Engineer, NSSS Superintendent -

Maintenance Unite 2 & 3 Support Unite 2 & 3 Engineering i I Radwaste 8 Supervisor

"

• 8"P'"IN

~

, Supervisor Computer's shitt l&C i

Superintendents of Plant

Coordination k Supervising I I Supervisor of Dosimetry Engineer, NSSS Conteog a -

Nucleat Maintenance Md* Engineering Room Coordinators Units 2 & 3 Supervisors Health Physics Supervising -l j

l -) -

Engineering -

Engineer, 8

l

- Contractor l Macagement j ; Supervisor STA Operators i Suoervisor of Plant 8. At t'** ol apposat**al to th* Po** hon. s nsor Reactor Operator Chemistry Lic *a" '**"'as

2. Senior Reactor License required.

l 3. Control end Assistant Control Operatorc ere hold sro ot Reactor Operstor Licensee.

4. Includes fire protection.

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

Table 6.2-1 MINIMUM SHIFT CREW CDMPOSITION WITH UNIT 3 IN MODE 5 OR 6 OR DE-FUELF.D POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION ,

MODES 1, 2, 3 & 4 MODES 5 & 6' SS la la

, CRG(SRO) I lbne 2 1

E AO 2 2b STA 1 None WITH UNIT 3 IN MODES 1, 2, 3 OR 4 POSITION NUMBER OF INDIVIDUALS REQUIRED '

0 FILL POSITION MODES 1, 2, 3 & 4 EDES 5 & 6 SS la la CHS(SRO) la Ibne RO 2b i AO 2D 1 l STA la Hone g Individual may fill the same position on Unit 3 g One of the two required individuals may fill the same position on Unit 3.

SS - Shift Superintendent with a Senior Reactor Operators License on Units 2 and 3

. CRS(SRO) - Oontrol Room Supervisor (Individual with a Senior Reactor Operators License on Units 2 and 3)

RO - Individual with a Reactor Operators License on Units 2 and 3 AO - Auxiliary Operator STA -

Chift Technical Advisor Except for the Shift Superintendent, the Shift Crew Cor: position 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to ac,- r -hte unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift Crew Conposition 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 A ea shown in Figure 6.2-3 while the unit is in MODE 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 conmand function. During any absence of the Shift Superintendent from the Control Room Area shown in Figure 6.2-3 while the unit is in M DE 5 or 6, an individual with a valid SRO or RO license shall be designated to assume the Control Room conmands function.

SAN ONOFRE-UNIT 2

1 . .

Table 6.2-1

- MINIMUM SHIFT CREW CDMPOSITION WITH UNIT 2 IN MODE 5 OR 6 OR DE-FUELED POSITION NUMBER OF INDIVIDUALS REQUIRED 'IO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 SS la la 1 None CPS (SRO) 1 RO 2 2 2b AD 1 None STA WITH UNIT 2 IN MODES 1, 2, 3 OR 4 POSITION NUMBER OF INDIVIDUALS PEQUIRED TO FILL POSITION

! ODES 1, 2, 3 & 4 PODES 5 & 6 SS la la la, None CRS(SRO) 2b 1 RO 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.

SS - Shift Superintendent with a Senior Reactor Operators License on Units 2 and 3 l CRS(SRO) - Control Room Supervisor (Individual with a Senior Reactor Operators License on Units 2 and 3)

,- RO - Individual with a Reactor Operators License on Units 2 and 3 l AO - Auxiliary Operator i STA - Shift Technical Advisor Except for the Shift Superintendent, the Shift Crew Conposition 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to acconnodate unexpected absence of on-duty shift crew menbers provided innediate action is taken to restore the Shift Crew Cbnposition to within the minimum requirements of Table 6.2-1. This provision i 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 ICDE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Oontrol Room conmand function. During any absence of l the Shift Superintendent from the Control Room Area shown in Figure 6.2-3 i

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 connands function.

SAN ONOFRE-UNIT 3 a

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ADMINISTRA"IVE COfCROLS _,

6.2.3 INDEPENDDTr SAFETY ENGINEERI!C GROUP (ISEG1 Fuw:21oN 6.2,3.3 2 e ISEG shall function to exanine plant operating characteristics, NRC issuances, industry advisories, Licensee Svent Reports and other sources of plant design and operating experience information which may indicate areas for improving plant safety.

COMPOSITION 6.2.3.2 he ISPG shall be conposed of at least five dedicated full-tirae engineers. Eack shall have a Bachelor's Degree in Engineering or Physical Science or equivalent and at least two years professional level experience in his field. Off-duty qualified Shift Technical Mvisors may be used to fulfill this requirement.

RESPONSIBILITIES, 6.2.3.3 2 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 much as practical.

I A!JITDRITY y

~

6.2. 3'. 4 2e ISEG shall make detailed recomendations for revised procedures, l

l . equipment modifications, maintenance activities, operations activities or other neans of inproving plant safet.y to the Supervisor, Nuclear Safety Group.

RECORDS 6.2.3.5 Records of activities performed by the ISEG shall be prepared, I

maintained, and forwarded each calendar conth to the NSG Supervisor.

l j

6.2.4 SHIFT TECHNICAL ADVISOR 1

W e Shift Technical Advisor shall provide technical support to the Shift l l I Superintendent in the areas of thermal hydraulics, reactor engineering and

~.

plant analysis,with regard to the safe operation of the unit. S e Shift Tedinical Mvisor 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 QUALIFICATION 6.3.1 Each menber of the unit staff shall meet or exceed the mininum qualifications of ANSI N18.1-1971 for conparable positions, except for the Health Physics Manager who shall meet or exceed the qualifications of l

Mgulatory Glide 1.8, September 1975.

• Not responsible for sign-off function.

SAN OtOFRE-UNIT l

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ADMINISTRATIVE O'NTROLS 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 recomendations of Sections 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CPR 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 PEVIEW AND AUDIT 6.5.1 ONSITE REVIEW COMMITTEE (OSRC)

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

COMPOSITION 6.5.1.2 %e Onsite. Review Corsnittee shall be conposed of the:

i Chairman: Station Manager Member: Deputy Station Manager Member: Manager, Operations ,

Member: Manager, Technical Member: Plant Superintendent SOtGS Units 2 and 3 Member: Supervisor of IEC Member: Manager, Health Physics Member: Supervisor of Chemistry Menber: Manager, Maintenance Member: Supervising Engineer (NSSS, NSSS Support, Conputer, or STA)

Member: San Diego Gas & ric Representative, Senior Engineer ALTERNATES _

6.5.1.3 All alternate menbers shall be appointed in writing by the OSRC 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.

(1)BS degree in Engineering or Physical Science plus at least four years professional level experience in his field. At least one of the four j

years experience shall be nuclear power plant experience.

SAN ONOFRE-UNIT

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ADMINISTRAME COtGtOLS '-

n' MEETING FRBocB? JC 6.5.1.4 2e OSRC shEll meet at.least once per calendar month and as convened by the OSRC Chairman or his designated alternate.

M 6.5.1.5 te minimum quorum of the GERC necessary for the performance of the OSRC responsibility and. authority provisions of these' Technical Specifications shall consist of the Chairmanor'nis desi,gnated alternate and four menbers including alternates. ,

RESPONSIBILITIES 6.5.1.6 Se Onsite Review Comittee shall be respoqsible for:

. a. InvestigationofallvioiationsoftheTechnicalSpecifications including the preparation and forwarding of reports covering evaluation and recorspendations to prevent recurrence to the Nuclear Safety Group (NSG). s

b. Review of all REPORTABLE EVENTS.

c. Review of unit operat ons to detect potential nuclear safety hazards,

d. Performance of special reviews, investigations or analyses and reports thereen as requested by the Station Manager or the'NSG Supervisor ~. ,

l _

e. Review and documentation of judgenent concerning prolonged operation f

in bypass, channel trip, arx1/or repair of defective protection channels of process variables placed in bypass since the last OSRC meeting.

j

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

AMDRIW _ . _ _

6.5.1.7 %e Onsite Review Comittee (OSRC) 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NSG Supervisor and Vice President and Site Manager, Nuclear Generation Site of disagreement between the OSRC and the Station Manager; PtNever, the

-Station Marwjer shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

SAN ONOPRE 3JNIT l

i

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ADMINISTRATIVE CDtCROLS

. RECERDS 6.5.1.8 2e Onsite Review Connittee shall maintain written minutes of each

' OSRC meeting that, at a minimum, 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 COM'ROL ACTIVITIES 6.5.2.1 2 e 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 raiewed by an individual / group other than the individua]/ group which prepared the procedure, or changes thereto, but who may be from the same organization as the individual / group whim 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. S e preparation of each

proposed Te&nical Specifications change shall be reviewed by an individual / group other than the individaal/ group which prepared the proposed

.&ange, but who may be from the same organization as the individual / group l

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 i 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 implacentation 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 / site supervisory staff, previously designated by the Station Manager to perform such reviews.

- Ea& such review shall include a determination of whether or not additional, crosswlisciplinary, 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 PSAR or Technical Specifications shall be reviewed by the Station Manager, or menbers of the station / site management staff previously designated by the Station Manager, l

SAN ONDPRE-UNIT L

I L2

ADMINISTRATIVE CONTROLS ACTIVITIES (Continued) 6.5.2.6 The station security progran and implementing procedures, shall be reviewed in accordance with 10 CFR 73.55(g)(4). Recommended 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). Recommended changes to the emergency plan or its implementing proceoures 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 qualifted 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 radweste treatment systems. The Manager, Nuclear Safety shall assure the performance of such a review of changes to the 00CM.

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 s

e. instrumentation and control l f. radiological safety

g. mechanical and electrical engineering

h. quality assurance practices SAN ONOFRE-UNIT y-, , .-g--, c. --------p,- = + w - - w~rr-----,,-ri---vemww,ee- ..-.v.1 ---*.*.e--.. *----.- - , - -r--=- - - = -e e-*-=-r--*-

ADMINISTRATIVE C0fEPOLS CDMPOSITION ,

6.5.3.2 NSG shall consist of a Supervisor and at least three staff specialists. L e Supervisor shall have a Bachelor's Degree in Engineering or

'- Physical Science and a minima of 6 years of professional level managerial experience 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 members. <

CONSULTANTS 6.5.3.3 (bnsultants shall be utilized as determined by the NSG Supervisor to l

provide expert advice to the NSG.

REVIEW 1

6.5.3.4 The NSG shall review:

I

a. The safety evaluations for 1) changes to procedures required by Specification 6.8, equipnent or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

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

c. Proposed tests or experiments whidi involve an unreviewed safety question r.s defined in Section 50.59, 10 CFR.

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

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

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

f

g. All REPOIEABLE EVENTS.

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

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

! SAN ONOFRE-UNIT i

- -=- i w w---- s- - - - + + - - -

ADMINISTRATIVE CDtmt0LS AUDIT ,

6.5.3.5 Audits of unit activities shall be performed under the cognizance of -

the NSG. Dese audits shall enconpass:

a. S e conformance of unit operation to provisions contained within the

'It&nical Specifications and applicable license conditions at least once per 12 months.

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

l

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

d. Se performance of activities required by the Operational Quality t

Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, l

at least once per 24 months.

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

! Generation Site.

f. W e 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 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.

Atm ORITY l

6.5.3.6 .Se NSG shall report to and advise the Manager, Nuclear Safety on those areas of responsibility specified in Sections 5.5.3.4 and 6.5.3.5.

RECCEtDS _ _ _

6.5.3.7 Records of NSG activities shall be prepared and maintained. Report l

of reviews and audits shall be distributed monthly to the Station Manager and l

to the management positions responsible for the areas audited.

l

. SAN ONOFRE-UNIT

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ADMINISTRATIVE CXXMM 6.6 REPORTABLE EVENT ACTION 6.6.1 *2 e following actions shall be taken for REPORTABLE EVENTS:

a. We Cennission 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 % e following actions shall be taken in the event a Safety Limit is violated:

a. @ e NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. h e Vice President and Site Manager, Nuclear Generation Site and the NSG Supervisor shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. A Safety Limit Violation Report shall be prepared. % e report shall be reviewed by the OSRC. W is report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility couponents, systems or structures, and (3) corrective action taken to prevent recurrence.

c. h e Safety Limit Violation Report snall 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 Occmission.

6.8 PROCEDURES AND PROGRAMS

. 6.8.1 Written procedures shall be established, inplementad and maintained covering the activities referenced below:

a. B e applicable procedures reu . w ded 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 inplementation.

e. Emergency Plan inplementation.

I SAN ONOFRE-UNIT

--y,- - -- w - -- - - yy

ADMINIS"RATIVE COtCROLS

f. Fire Protection Program implementation.

g. PROCESS C0tCROL PROGRAM i@lementation.*

h. OFFSITE DOSE CAI4GLATION 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.

'See Specification 6.13.1

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

6.8.2 Each i @lementing 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 i @lementation and shall be reviewed periodically as set forth in administrative procedures.

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

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

b. The change is approved by two menbers of the station / site management staff, at leact one of whom holds a Senior Reactor Operator's License on the unit affected.

c. W e. change is documented, reviewed and approved by responsible j management as delineated in 6.8.2 above within 14 days of l i@lementation.

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 l serious transient or accident to as low as practical levels. The systems include the high pressure safety injection recirculation, the shutdown cooling system, the reactor coolant sampling system (post-accident sa@ ling piping only), the containment spray system, the radioactive waste gas systen (post-accident sampling return

. SAN ONOFRE-UNIT l .

l .

l

ADMINISTRATIVE CDtCROLS piping only) and the liquid radwaste system (post-accident sampling return piping only). h e program shall include the following:  :

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

l' b. In-Plant Radiation Monitoring i

A program which will ensure the capability to accurately determine the l airborne iodine concentration in vital areas under accident conditions.

h is program shall include the following:

(i) Training of personnel, l

(ii) Procedures for monitoring, and (iii) Provisions for maintenance of sa g ling and analysis equipment.

i-

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

(i) Identification of a sa mling 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 sa gling points, including monitoring the discharge of the condensate pu g s fer evidence of condenser in-leakage,

! (iv) Procedures for the recording and management of data, (v) 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 Samplinq _

1 l

A program whid will ensure the capability to obtain and analyze reactor l

coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. We program shall include the craining of personnel, the procedures for sa gling and analysis and the provisions for maintenance of sag ling and analysis equipment.

SAN ONOFRE-UNIT l

[

l

~

l

ADMINISTRATIVE C0tTTROLS J

6.9 REPORTING REQUIREMDTTS ROLTfINE REPORTS

- 6.9.1 In addition to the applicable vporting requirements of Title 10, Code of Federal Regulations, the following reports shall be suNaitted to the NRC Regional Administrator unless otherwise noted.

STARTUP REPORP 6.9.1.1 A sumary 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 differene 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 h 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.

l 6.9.1.3 Startup reports shall be submitted within (1) 90 days following coupletion of the startup test program, (2) 90 days following resunption or comencement of comercial power operation, or (3) 9 months following initial criticality, whidiever is earliest. If the Startup Report does not cover all  ;

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

- and resunption or comencement of comercial operation) supplementary reports shall be submitted at least every three months until all three events have been conpleted.

. ANNUAL REPORPS*

6.9.1.4 Annual reports covering the activities of the unit as described below I

f 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 number of station, utility, and other personnel (including contractors) receiving exposures gredter 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. W e submittal l should combine those sections that are comon to all units at the station.

• • Wis tabulation supplements the requirements of 10 CFR 20.407.

SAN ONDPRE-UNIT i

i ADMINISTRATIVE CONTROLS 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 badge measurements. Small exposures totalling less than 20 percent of the individual total dose need not be accounted for. 1 In the aggregate, at least 80 percent of the total whole body dose received j from external sources should be assigned to specific major work functions.

^""LIAL RADIOLDAICAL 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 Kay 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 radiclogical 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 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 the site reference point; and the results of licensee participation in the Interlaboratory l Comparison Program, raquired by Specification 3.12.3.

l SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

• f' 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 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; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

SAN ONOFRE-UNIT

. . . ,_...m..__

, . . ~ . . , _ _ _ . - _ - . . . _ _ _ _ _ - _ , - _ . _ . _ _ . - _ _ _ . , m - _ .-

ADMINISTRATIVE 00tTfROLS 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 frm Light-Water-Cooled Nuclear Power Plants,' Revision 1, June 1974, with data sumarized on a l 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. mis annual sumary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atnospheric stability, and precipitation (if measured) on magnetic tape, or in the form of stability. B is same report shall include an ,

I assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar s year. Bis 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. m e assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

S e radioactive effluent release report to be submitted 90 days after l 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.

4 2e radioactive effluents release shall include the following information for each type of solid waste shipped offsite during the report period:

a. Container volume,

b. 'Ibtal curie quantity (specify whether determined by measurement or estinate),

c. Principal radionuclides (specify whether determined by measurement

. or estimate),

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

SAN ONOFRE-UNIT

)

O

_ - , - - - . . - - , _ _ , - - - - , - . . - . - , . - w---e- - , - ..*W,.. m,2-, ._.,.--i,,w,,w - , ,y-,_.,...y, - --- , , --- m ai , , , . , -- e-- , -- -,.e. . - - -

ADMINISTRATIVE COtCROLS

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

f. Solidificatiion agent (e.g., cement, urea fornaldehyde).

The radioactive effluent release reports shall include unplanned releases frora the site to unrestricted areas of radioactive naterials in gaseous and liquid effluents on a quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS C0tCROL PROGRAM (PCP) made during the reporting period.

i l- MCtmILY OPERATING REPOR:'

6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all d allenges 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 Cbunission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

Any danges to the OFFSITE DOSE CALCULATION 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 danges to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the change was made effective.

HAZARDOUS CARGO TRAFFIC REPORP

' 6.9.1.11 Hazardous cargo traffic on Interstate 5 (I-5) and the ATESF railway .

- shall be nonitored and the results submitted to the NRC Regional Administrator '

once every three years.

EMERGENCY CORE COOLING SYSTEM OUTAGE REPORT __

6.9.1.12 An annual report shall be submitted to the Director, Office of Nuclear Reactor Regulation, Division of Licensing, detailing cumulative outage time for ECC systems and couponuts. The report should contain the (1) ECC system or couponent involved; (1) cause of outages (3) duration of outage; and (4) corrective actions taken. Proposed changes to inprove the availability of the ECCS equipment, if needed, shall also be dir*W. Reports covering ECCS outages during the previous calendar year shall be submitted prior to April 1 -

of each 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 9

.-3.. .

~ - , , - . , - . - ,-, , . _ __..,,,,,% ,- , ,.,.m _ ,,__ 3,, , _ . -,.- - _ _ -,m._.-___ , _ _ , _ - - ,-, , , , _ _ _ _ _ _ , _ _ , _ -

+ - - - - _ _

I 3DMINISTRF.TIVE CDimtOLS j RECCED RETEtEION , ,

6.10 In addition to the applicable record retention requirements of Title 10, Oode of Federal Regulations, the following records shall be retained for at -

least the minimum period indicated.

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

c. All REPORTABLE EVEICS submitted to the Comatission.

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

e. Remrds of dianges made to the procedures required by Specification 6.8.1.

f. Records of radioactive shipnents.

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. R w rds of new and irradiated fuel inventory, fuel transfers and assenbly 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 those unit components identified in Table 5.7.1.

f. Records of reactor tests and experiments.

SAN ONOFRE-UNIT

- .r-~ - , , - - . - - - - ,-- . - .-- , - ----,.,, - , - - ,--- - e.~., . , . -- - - - ,- ,,_ - - , , - + - ~-- - - - - - ,. -- r ---

ADMINISTRA1T/E 03CROLS

g. Records of training and qualification for current members of the unit staff.' 1

h. Records of in-service inspections perforland pursuant to these -

Technical Specifications.

1. Records of Quality Assurance activities required by the 04 Manual.

j. Records of reviews performed for changes nede to procedures or equipnent 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 ccs:mences and associated installation and naintenance records.

m. Records of secondary water sanpling and water quality.

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 HIGH RADIATION 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 100mrenVhr but less than 1000 mren/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 I enter such areas shall be provided with or amrtied by one or more of the

{ following:

a. A radiation monitoring device which continuously indicates the i radiation dose rate in the area.

I I b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated l

' 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 them.

• Dealth 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 l-

= .

ADMINISTRATIVE CONTROLS l l

I

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitorirg device who is-responsible for providing positive control over the activities 4

within the' area and shall perform periodic radiation surveillance at

! the frequency specified by the facility Health Physicist in the I 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 mrem 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 areas, such as PWR containment, where ro 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 i

procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP)

I 6.13.1 - The PCP shall be approved by the Commission prior to implementation.#

L 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 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 solidified waste product to existing criteria for solid wastes; and

c. Documentation of the fact that the change has been ieviewed and l

found acceptable pursuant to 6.5.2.9 L

i 2. Shall become effective approval by the' Manager, Health Physics.

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

l

1. The PCP shall be submitted and approved prior to shipment of " wet" solid '

j radioactive waste.

SAN ONOFRE-UNIT i

(.

-e n ADMINISTRATIVE CONTROLS 6.14 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 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 00CM 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 effective upon approval of the. Manager, Nuclear Safety.

6.15 RAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous l 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 l for the period in which the change was made effective pursuant to 6.5.2. The discussion of each change shall contain:

l

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 ressoa 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 those previously predicted in the license application and amendments thereto; SAN ONOFRE-UNIT l

a .

ADMINISTRATIVE CONTROLS

e. An evaluation of the change which shows the expected neximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated ,

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. 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 Technical.

e T

\ l l

l SAN ONOFRE-UNIT

, - , , . , - - - . - - , , - , . , - , - - . , - - - - - . - , ~ , . - - . - - - . . - . - - - - - - - - , - - --- - - - - - - n

-o .

3N57RU".!NTAT10N '

RA*10ACT]VE L100!D EFFLUiN7 Moti!70R]NG ]N$1ROMiWiAT}DN L1w?i2 C 0002T20ti FOR De[ RAT]Dri 3.3.3.8 The radioactive 11evid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERA 5LE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeces. The alarm /

trip setecints of thest channels shall be sete*cined in accoraance with th:

OFFSITI DO5E CALCUtAT3DN MANUAL (DD H).

A* PLICA *1LITY: At all times.*

ACT]DN:

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

channel inoperable.

b. With less than the r.inimut nue.ber of radioactive liquid effluent etnitoring instrumentation channels OPERAELE, take the ACTION shown in Table 3.3-12. Additionally, if the inoperable instruments are net returnet te OPEP.A5LE status within 30 days, explain in the next seri-annual Racioactive Effluent Release Report why the inoperability was -

net correctec in a tipely manner.

c. The provisions of Specifications 3.0.3, 3.0.4, are not applicable.

i SURVEILLANCE REOL'IREMEKT5 l

L 4.3.3.8.1. Each radioactive liquid effluent monitoring instrumentation channel shall be demonstratec OPERABLE by perforr.ance of the CMANNEL CHECK, SOURCE CMECK, CHANNEL CAL 1BRATION and CMANhEL FUNCTIONAL TEST operations at the frecuencies shown in Table 4.3-8. '

4.3.3.8.2 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at least one circulating water pump shall be determir.et to b4 cperating 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.

1

'See speciai Test Inception 3.20.5.

l

&&N DNOFRE-UNIT 2 3/4 3-f3

INSTRUMENTATION f

RADIDACTIVE LIQUID EiFLUENT IONITORING INSTRLMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instroentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alorn/

trip setpoints of these channels shall be determined in accordance with the OFF5ITE 805E CALCULATION IENUAL (00CM).

E LICABILTTY: At all times.

E:

a. With a radioactive liquid effluent monitoring instrumentation -

channel alarm / trip setpoint less conservative than required by the above specification, imediately suspend the release of radioactive liquid ef fluents sonitored by the affected channel or declare the chaniel inoperable.

h. With less than the minimum neber of radioactive liquid effluent monitoring instroentation channels OPERABLE, take the ACT]DN 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 previsions of Specifications 3.0.3, 3.0.4, are not applicable.

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

4.3.3.8.3 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at least one circulating water pump shall be detarained ta be operatin0 and providing dilution to the discharge structure

'whenever diletten is required to meet the site endloactive effluent concentration limita of Specification 3.11.1.1.

pi5W W ONOFRE-UNIT 3 , 3f,3,,,

l

- . _. . . . _ _ _ _ _ __ _ _ _ _ _ _ . _ _ _ _ . . . _ . _ . _ _ _ _ . _ - ~ . _ _ _ _ _ . . - . . _ _ _ - . _ ~ . _ _ _

n ,

I l

1 1kSTRUMiWTAT10N RC10A*T!vi GA5E005 EFFLU!O MON 7TDRIN3 7NSTRp!!G AT10N L1**I 1N3 CDGDITION F08 D ERAT I 10N 3.J.3.9 Tee radioactive gaseous ef fluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERA 8LE with their alarz/ trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not enreeded. The ,

elarm/trip setpoints of these chennels shall be seterrined in accordance with 1 1

t%e ODCM. l A**LICAEILITY: 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 suspene the release of radioactive gaseous affluents monitored by the af fected channel or declare the - -

channel ineperable.

b. With less than the minimum number of radicactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Aceitiona11y. if the inoperable instruments are not returned to OPERAELE status within 30 ceys, explain the next Seri-annual Radioactive Effluent Release Report why the inoperability was not correctec in a timely manner.

c. The provisions of Specifications 3.0.3, 3.0.4, are not applicable.

SUFNEILLaNCE REQUIREMENTS 4.3.3.9 Each radioactiva gaseous effluent monitoring instrumentation channel shall be eemonstrated OPER45LI by performance of the CHANNEL CHECK, SOURCE CHECK, CHANN!L CAL 18 RAT]DN and CHANNEL FUNCTIONAL TEST operations at the frecuencies shown in Table 4.3-9. '

l

• See Special Test Exception 3.20.!

SAN DNDFRE-UNIT 2 3/4 3-68

e ,,

INSTRUPENTATION AADI0 ACTIVE GASEQU5 TFFLUENT WNITORING INSTRLMENTATION l

LIMIT!NG CONDITION FOR OPERATION l l

3.3.3.9 The radioactive gaseous effluent monitoring instroentation 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 exceedad. The t

alam/ trip setpoints of these channels shall be determined in accordance with the 00CM.*

APPLICA97LITY: As shown in Table 3.3-13 ACTION:

~

a. With a radioactive gaseous effluent monitoring instrumentation ~

channel alam/ trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel er declare the channel inoperable.

b.

• With less than the minieur. neber of radioactive gaseous effluent aonitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Additionally, if the inoperable instroents 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 are not applicable.

SURVE!LLANCE REQUIREMENTS I

'4.3.3.9 Each radioactive gaseous offluent monitoring instroentation channe!

! shall be demonstrated OPERA 8LE by perfomance of the CHANNEL CHECK, SOURCE i CNECK, CHANNEL CAL 184AT30N and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.

t " Continuous monitoring and samp11ag of the contalment purge exhaust directly from the purge stack shall be provided for the low ar=1 high volume (8-inch and 42-inch) containment purge prior to startup follering the first refueling outage. Containment airborne monitor 3RT-7804-1 or 3RT-7807-2 and associated sampling media shall perfere these functions prior to initial criticality.

From initial criticality to the startup following the first refueling outage 4

contalment airborne monitar 3RT-7504-1 and associated sampling media shall perfem the above required functions.

SAN ONOFRE-UNIT 3 3/4 3-se

n' -

F.EA:~04 CO3 tant 5'5T5" A:~10:,: (Continued) 1 l

. I MODES 1, 2..) 4 an" 5:

s. With th6 specific activity of the prima *y coolant greater than 1.0 ricro:urie/ gram DOSE EQUIVALENT 1-131 or creater than

- 100/I si:rocuries/ gram, perfort the sat: ling and analysis recaire-ments of item a a) of Table 4.4-4 until the spe:ific a:tivity cf the prir.ary coolant is restored to witnin its limits. A SPECIAL REPORT sball 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 followina information:

1. Rea: tor power history starting 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> prior to the first sample in which the limit was exceeded,

2. Fuel burnup by core region,

3. Clean up flow history starting 48 h urs prior to the first sae;1e in which the limit was exceeded, 4 Histcry of de gassing operation, if any, starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in w'.ich the limit was excetoed, ang

5. The time curation when the spe:ific activity of the prima y coolant exceteen 1.0 microcurie /graz DOSE EQUIVALENT 1-131.

SURV!1LL AN*E REQJ;s,ggggt5 <

4.4.7 The specific activity of the primary coclant shall be setermined to be within the lirits by performance of the sarpling and ar.alysis prograr of Table 4.4-4 5AN ONOFRE-UN]i 2 3/4 4 24

4 ,,

REACTOR COOLANT $YSTEM )

d: (Continued)

• l 800ES 1, 2, 3, 4 sed 5: l

d. With the specific activity of the primary coolant greater than 1.0 oferocurie/ gram DOSE EQUIVALENT I-131 or greater than 100/T sierocuries/ gram, perfore the sampling and analysis require-ments of item 4 a) of Table 4.4-4 until 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 information:

1. Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first . ,

sample in which the limit was exceeded,

2. Fuel burnup by core region,

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

4. History of de gassing operation, if any, starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded, and I 5. The time duration when the specific activity of the primary coolant exceeded 1.0 microcurie / gram DOSE EQUIVALENT I-131.

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SURVEILLANCE REQUIREMENTS

\

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

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l ytN 15 52 SAN ONCFRE-UNIT 3 3/4 4-25 l

ELfCTR3 CAL P0/it 5YSTfatS SURVIILLAN*f RE00f'Rttli C 5 (Continued)

13. Verifying that the automatic load sequence timer is CPERABLE with the interval between each lead block within : 105 of its design interval.

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

r

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 eiesel generators accelerate to at least 300 rps in less than or equal to 10 seconds.

f. At least once per 10 years by: , ,

1. Draining each fuel oil sto age tank, temoving the accumulated sediment and cleaning the tank using a sodist hypcchlorite solution of the equivalent, and

2. Perforting a pressure test of those portions of the diesel fuel oil systet designed to Section III, subsection 8C of the ASP.I Code at a test pressure equal to 110 percent of the syster design pressure.

4. 8.1.1. 3 Rese*ts - All diesel generator failu es, valid or non-valid, shall be reported to toe Coseission pursuant tc 5pecification 6.9.1.10. Reports of ciesel generator f ailures shall incluse the information recospensed in Regula-tory Position C.3.b of Regulatory Guise 1.106, Revision 1. August 1977. If the numer 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 recommended in Regulatory Position C.3.6 of Regulatory Guide 1.108 Revision 1, August 1977.

SAN ONOFRE-UNIT 2 3/4 8-6

- _ . . - . ~ , , _ _ _ . . _ _ . _ . . . _ _ . ___..._,_...._,m,____,-, . . _ . _ _ _ . . _ . _ . . _ _ , _ _ _ _ _ . . , . , m._,.-_.._ - . . . , -.,___

ELECTRICALPOUERSYSTEMS SURVEILLANCE REQUIREMENTS (Continued) ,

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13. Werifying that the avtamatic load sequence timer is OPERABLE with the interval between each load block within f,15 of its design interval.

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

e. At least once par 10 years or after any modifications'which esuld 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. Perforeing a pressure test o'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 Reoorts - All diesel generator failures, valid or non-valid, shall l .

be reported to the Comission pursuant to Specification 6.9.1.10. Reports of l

diesel generator failures shall include the infomation recommended in Regula-tary Position C.3.6 of Regulatory Guide 1.108 Revision 1 August 1977. If the

aumber of failures in the last 100 valid tests (on a per nuclear unit basis) is greater than or equal to 7, the report shall be supplemented to include the additional infomation recommended in Regulatory Position C.3.b of Regulatory Guide 1.108 Revision 1 August 1977.

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p 151181 l .

SAN ONDFRE-UNIT 3 3/4 8-6 l l l l

?  :

RCIDACTIVE FFLUENTS 1 1

E.ll 1 j

LIMITI C C0C TTION FOR 0*ERATION l

3.11.1.2 The dose or sose commitment to an individual fres radioactive asterials in lievic effluents released, fror each reactor unit, *ros the site (see Figure 5.1-4) shall be limited:  ;

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 sees to any organ, and

b. During any calendar year to less than or equal to 3 oves to the total body and to less than or equal to 10 area to any organ.

A*PLICABILITY: At all' times.

ACTION: . .

' a. With the calculated dose fror the release of radioactive materials in liquid effluents exceeding any of the above lisits, in lieu of any other report recairac by Specification 6.9.1, prepace and subrit te the Coerission within 30 days, pursuant to Specification 6.9.2, a special Report which identifies the cause(s) for exceeding the limit (s) aN: defines the corrective actions taken to reduce the releases and tne pmposed actions to be taken to assure that subsequent releases will be in compliance with Specification 3.U.1.2

b. The provisions of specifications 3.0.3,'3.5.4 are not applicable.

i SURVf!LLANOT RE007t!M!WT5 4.11.1.2 Dose Calculations. Caulative dose contributions free liquid effluents shall se seterrined in accordance with the ODCM at least once per 31 days.

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SAN ONOFRE-UNIT 2 3/4 u-5 t

3- ~

3/4.12 RC70LOCICAL tWv!RDWICAL MDN!TOUC 3/4.12.1 SCW7T0FIC DRD;; RAM

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L1MITIMCONDITIONFOROPERAT10b

~3 .12.1 Tne radiologicA1 enviremental monitoring progras shall be conducted sa specifim.1 in Tacle 3.12-1.

APPLf0MILTH: At all. times.

ACTI'ON:

a. With the radiolegical environmental sonitoring progree not being conducted as specified in Taale 3.12-1, in lieu of any other report required by Specification 6.3.1, prepare and submit to the Cee-mission, in the Annval Radiclogical Operating Report, a description of the reasons for not conducting the progras as required and the plans for preventing a recurrence. . ,

b. With the level of radioactivity in an environmental sampling medium x

exceeding the reporting . levels of Table 3.12-2 when averapet over any calencar quarter, in lieu of any other report required by Specification 6.9.1, p spare and subeit to the Coerission within 30 days from the end'of the affected calendar evarter 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 subritted if:

concentration (1) , concentration (2) + "*> 1.0 p liest level 0) limit level (2) -

l .

l Vaen rasienudlides other than those in Table 3.12-2 are setectas and

,are the result cf plant effluents, this report shall be subeitted if the potential annual sose to an individual is equal to or greater ther: the calendar year limits of Ipecifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not mquired if the measured level'of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environsental Operating Report.

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c. With frel.h leafy vegetable samples or fleshy vegetable samples unavail-

! able free one er soft of the sample locations required by Table 3.12-1, in lieu taf any other report nauired by 5pecification 6.9.1, prepare ane subtit to the Cameission within 20 days, pursuant to Specific-ation 6.9.2, a Special Report which identifies the cause of the unavail-ability of saeples and identifies locations for obtaining replacement aamples. The locations from which se.~.ples were unavailable may then

l. be seleted from those required by Table 3.12-1, provided the locations l free which the replacement samples were obtained are added.to the

environmental monitoring program as replaconent locations.

d. The provisions rf Specifications 3.0.3 and 3.0.4 are not applicable.

l SAN OCFRI-UNIT 2 3/4 22-1 FU .* . .

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, - _ . - . . . _ _ , , . . - , _ - _ . _ - . - . . _ _ - . . _ _ _ . ~ - . .- . _ _ - _ - . _ - _ - _ _ . _ _ _ _ _ _ . - - _ _ _ _ _ - _ - - - _ _ -

4 3/4.12 RADIOLOGICALENVIRONMENTALMONITORI$G 3/4.12.1 90NITL, RING 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.

1 i ACTION:

a. With the radiological environmental sonitoring 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 Coa-sission, in the Annuat 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 end of the affected calender 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 '

i .

medium, this report shall be submitted if:

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

l Wen radionuclides other than those in Table 3.12-2 are detected and l are the result of plant effluents, this report shall be submitted if l' the potential annual dose to an individual is equal to or greater than the calendar year liette of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the seesured 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-l able free one er more of the sample locations required by Table 3.12-1, in lieu of any other report required by Specification 6.9.1, prepare end submit to the Commission within 30 days, pursuant to Specific-atton 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 free which samples were unavailable may then be deleted from those required by Table 3.12-1, provided the locations from which the mplacement samples were obtaihed are add:d to the environmental monitoring progras as replacement locations.

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

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