ML19354C335

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Proposed Tech Specs 3.6.5 & 4.6.5 Changes for Subatmospheric Pressure Control Sys Steam Air Ejector
ML19354C335
Person / Time
Site: North Anna Dominion icon.png
Issue date: 07/30/1980
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19330B550 List:
References
NUDOCS 8008050016
Download: ML19354C335 (7)
v • d • e


Text

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ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE NORTH ANNA UNIT NO. 1 8008050 w OI6

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53 TABLE 4.3-2 (Continued) 5! '

3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

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CllANNEL H0 DES IN WillCil c CilANNEL CllANNEL FUNCTIONAL SURVEILLANCE 2j FUNCTIONAL UNIT CllECK CALIBRATION TEST REQUIRE 0

5. TURBINE TRIP AND FEEDWATER ISOLATION
a. Steam Generator Water S R H 1, 2, 3 Level--liigh-liigh 3g 6. AUXILIARY FEEDWATER PUMPS
a. Steam Generator Water S R H 1, 2, 3, 4 Level--Low-Low

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b. S.I. See 1 above (all S.I. Surveillance Requirements)
c. Station Blackout N.A. R N.A. 1, 2, 3, 4
d. Main feedwater Pump Tr,ip s fl. A. N.A. R 1, 2
7. LOSS OF POWER 4.16 KV Emergency Bus
a. Loss of Voltage N.A. R M(2) 1, 2, 3

[ b. Degraded Voltage N.A. R N(2) 1, 2, 3

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2 % 77 CdNTAINMENTSYSTEMS 3/4.6.5 SUBATMOSPHERIC 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 ejector suction line shall be closed.

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

ACTION:

With the inside or outside isolation valve in the steam jet air ejector suction line not closed, restore the valve to the closed position 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 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. .

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SURVEILLANCE REQUIREMENTS 4.6.5.1.1 The steam jet air ejector suction line outside isolation valve shall be detennined to be in the closed cosition by a visual inspecticn prior to increasing the Reactor Coolant System temperature above 9564 and at least once per 31 days thereafter if the valve is l  !

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not lockedh sealed or othenvise secured in the closed position. '

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l 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 increas-ing the Reactor Coolant System. temperature above 4604. l 4 2005 F.

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l l,NORTHANNA-UNIT 1 3/A 6-37 l

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  • Ih k %# # 4 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for overall facility l operation.:nd :h:l' d:1;;;t: ' uriting th: :::::::icn to thi: ,]

rc: pn;ibility during hi: :h:nce. In his obsence, the Assistant Mkn .

Monager shc.t! be respondo',e br e ]

overan haa operahin. Dunc$w,ne obsence y

es of 6th , ee %6 Manc.3 c shau debate in wrmg We success i 6.2 ORGANIZATION Ns resp N b E:7

. OFFSITE l

.l 6.2.1 The offsite organization for facility management and technical l 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 crew 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.
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. I

d. An individual qualified in radiation protection procedures shall be on site whei fuel is in the reactor.
e. 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 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.

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' Fire Brigade composition 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 1 ,

absence of Fire Brigade members provided immediate action is taken to [ ,

restore the Fire Brigade to within the minimum requirement. q  ;

NORTH ANNA - UNIT 1 6-1 ,  ?::nient '!:.15

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.. o e ,n nn ADMINISTRATIVE CONTROLS 6.3 iaCILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Supervisor-Health Physics who shall meet or exceed the qualifica-tions of Regulatory Guide 1.8, September 1975.

r 6.4' TRAINING A o

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

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f 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 Nanager l on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The SNSOC shall be composed of the:

AssMont when Amoec Chairman: Station Manager Vice-Chairman: S4 ;cint:ndent 0.::nti ce l Member: Superintendent - Maintenance Member: Superintendent - Technical Services Member : bpennierde nt - Opemuns l

ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the i SNSOC Chairman to serve on a temporary basis; however, no more than one  !

alternate shall participate as a voting member in SMSOC activities at l any one time. l NORTH ANNA - UNIT 1 6-5 fund::nt Mc. "

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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- hg Chairman and two members including alternates. y Resp 0NSIBILITIES

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) ar.y other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety.

L. 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 ecoipment that affect nuclear safety.
e. Investigation of all violations of the Technical Specifications including.the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the

-* Oir;;t;r, Nu;I;;r 0;;r;ti;;; and to the Chairman of the l System Nuclear Safety and Operating Committee.

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

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NORTH ANNA - UNIT 1 6-6 b* l 1

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