ML19330B551

Proposed Tech Specs 3.6.5 & 4.6.5 Changes for Subatmospheric Pressure Control Sys Steam Air Ejector

ML19330B551
Person / Time
Site:	North Anna
Issue date:	07/30/1980
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19330B550	List: ML19330B549 ML19330B551 ML19330B552 ML19354C335
References
NUDOCS 8008050018
Download: ML19330B551 (7)

Text

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ATTACHFENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGE E TH ANNA UNIT NO. 2 t

Es TABl.E 4.3-2 (Continued) 25 3C ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEfLLANCE REQUIREMENTS

CHANNEL MODES IN WHICH

' CilANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CllECK CALIBRATION TEST REQUIRED E

q 7. LOSS OF POWER

a. 4.16 kv Emergency Bus N.A. R M (2.) 1, 2, 3 Undervoltage (Loss of Veltage)

b. 4.16 kv Emergency Bus N. A.

Undervoltage (Degraded R M(2) 1, 2, 3 Voltage R.

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1 CONTAINMENT SYSTEMS 3/4.6.5 SU8 ATMOSPHERIC PRESSURE CONTROL SYSTEM STEAM JET AIR EJECTOR ,

LIMITING CONDITION FOR OPERATION 3.6.5.1 The inside and outside isolation valves in the steam jet air efector suction line shall be closed.

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

With the inside or outside isolation valve in the steam jet air ejector suction line not closed, restore the valve to the closed pcsition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in HOT SHUT 00Wil within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.5.1.1 The steam jet air ejector suction line outside isolation valve shall be determined to be in the closed position by a visual inspection prior to increasing the Reactor Coolant System temperature above 990nf and at least l once per 31 days thereafter if the valve is not locked, sealed r otherwise secured in the closed position. 200?F 4.6.5.1.2 The steam jet air ejector suction line inside isolation valve shall be determined to be in the closed position prior to increasing the Reactor Coolant System temperature above 950Sf.

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1 NORTH ANNA - UNIT 2 3/4 6-36 i l

4-11-80 6.0 ADMINISTRATIVE CONTROLS 3.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for overall facility operation.

2nd 05:P delegate in writing th: :ac;;;;ica to thi: rt;p.uibility :.'uring hi:

b:::::. In his obsence , the %sisknk Sunn Mcqe r- shan be respc>nsible L Overcdi fac3Lk) operation. During khe ds.coc e cS bchh ; the StaWn Mcm ge.c sh nb deleqake in occius the su<,cesg%n ic, L 6.2" ORGANIZATI0tr OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

a. Each on duty shift shall be composed of at least the minimum shift c.ew composition shown in Table 6.2-1.

( b. At least one licensed Operator shall be in the control room when fuel is in the reactor.

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c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

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

All CORE ALTERATIONS shall be 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.

f. A site Fire Brigade of at least 5 members shall be maintained onsite at all times.# The Fire Brigade shall not include the minimum shift crew shown in Table 6.2-1 or any personnel required for other essential functions during a fire emergency.

Fire Brigade coinposition may be less than the minimum requirement 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 Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirement.

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NORTH ANNA - UNIT 2 6-1

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11 00 ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-19/1 for comparable positions, except for the Supervisor-Health Physics who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING 6.4.1 The Station Manager is responsible for ensuring that retraining and replacement training programs for the facility staff are maintained and that such programs meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.5 REVIEW AND AUDIT 6.5.1 STATION NUCLEAR SAFETY AND OPERATING COMMITTEE (SNSOC)

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

COMPOSITION 6.5.1.2 The SNSOC shall be composed of the:

- Assiska Se home Chairman: Station Manaoer "

Vice-Chairman: -*Sup;rint:-d~t - Cper;tiera l Member: Superintendent - Maintenance Memb.r: Superintendent - Technical Services Member- hperMenden'. - Oper&ns l ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the SNSOC Chairman to serve on a temporary basis; however, no more than one alternate shall participate as a voting member in SNSOC activities at any one time.

i NORTH ANNA - UNIT 2- 6-6

5 11 SO ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The SNSOC shall meet at least once per calendar month and as convened by the SNSOC Chairman or his designated alternate.

QUORUM 6.5.1.5 A quorum of the SNSOC shall consist of the Chairman or Vice-Chairman and two members including alternates.

RESPONSIBILITIES 6.5.1.6'.The SNSOC shall be responsible for:

a. Review of 1) all procedures required by Specification 6.8.1 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety.

b. Review of all proposed tests and experiments that affect nuclear

( safety,

c. Review of all proposed changes to Appendix "A" Technical Specifications.

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

e. Investigation of all violations of the Technical Specifications including the oreparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Oirc:ter, Muc!: r +-

^;:r:t*:- and to the Chairman of the System Nuclear Safety and Operating Committee.

Mager, Nuc%r Opereas and tAadenance

f. Review of 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.

g. Review of facility operations to detect potential nuclear safety hazards.

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Station Nuclear Safety and Operating Committee.

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NORTH ANNA - UNIT 2 6-7 l

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