ML19338G075
| ML19338G075 | |
| Person / Time | |
|---|---|
| Site: | 05000054 |
| Issue date: | 10/20/1980 |
| From: | UNION CARBIDE CORP. |
| To: | |
| Shared Package | |
| ML19338G070 | List: |
| References | |
| NUDOCS 8010280412 | |
| Download: ML19338G075 (6) | |
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4.0 SURVEILLANCE REQUIREMENTS 4.1 General Tne requirements listed oelow generally prescribe tests or inspections to verify periodically tnat tne performance of [
required systems is in accordance witn specifications given aoove in Sections 2 and 3. In all instances wnere tne specified l 3
frequency is annual, tne interval between tests is not to exceed i 14 . montns; wnen semiannual, tne interval snould not exceed 7 I montns; wnen montnly, the interval snall not exceed 6 weeks; wnen weecly, tne interval sna11 not exceed 10 days; and wnen
- daily, tne interval snall not exceed 3 days, i
4.2 Safety Cnannel Calioration A cnannel calibration of eacn safety cnannel snall oe performed annually (see Sect. 3.2.3).
4.3 Reactivity Surveillance (1) Tne reactivity wortn of eacn control rod (including tne regulating rod) and tne snut-down margin snall oe determined wnenever operation requires a reevaluation of core physics parameters, or annually, wnicnever occurs first. The rod worth will be determined using the reactivity-period or rod-crop metnods.
(2) The reactivity wortn of an experiment shall be estimated, or measured at low power, before conducting the experiment.
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(3) Baron /Caroide roos snall oe gauged quarterly and any i . dimensional cnanges reported promptly to tne Commission.
Silver / Indium / Cadmium control rods snall De gauged annually, or, in tne case of newly installed rods, at the
, end of the first six montns. If any Ag/In/Cd rod snould oe found not be meet tne acceptance criteria it snall be removed from service. In addition, all otner rods manufactured of the same baten sna11 oe inspected.
i 4.4 Control and Safety System Surveillance (1) Tne scram time snall be measured annually. If a control rod is removed from the core temporarily, or if a new rod is installed, its scram time snall be measured before '
reactor operation. If _ tne oridge is moved, tne scram time
- will be measured oefore subsequent reactor operation.
, (2) A cnannel test of eacn measuring cnannel in tne reactor safety system snall oe performed montnly or prior to eacn reactor operating period wnicnever occurs first unless tne preceding snut-down period is 8 nours or less. A cnannel test before startup is, nowever, required on any cnannel receiving maintenance during tne snut-down period.
(3) A cnannel cneck of eacn measuring cnannel (except for tne pool level) in tne reactor safety system shall oe performed daily wner. tne reactor is in operation.
4.5 Radiation Monitoring System (1) Tne excursion, stack, and area monitors snall be calibrated annually.
) (2) 'Tne excursion, ~stacx, and area monitors shall receive _ a cnannel test montnly.
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- 3. The excursion, stack, and area monitors snall receive a enannel cnecK and a setpoint verification daily during reactor operating periods.
4.6 Engineered Safety Features 4.6.1 Excursion Monitor: see aoove 4.5.
4.6.2 Emergency Generator (1) The aoility of tne emergency generator to start, to run normally, and to generate 440 VAC snall be cnecked weekly.
(2) Tne generator snall be tested for its aoility to accept, via tne automatic transfer switen, tne reactor electrical load once every six montns. A commercial power outage and subsequent pickup of load oy tne emergency generator will count as a successful load test.
4.6.3 Containment (1) Tne efficiency of tne cnarcoal filters and of tne aosolute filters in tne emergency exnaust system shall oe measured annually and tne flow rate .erified.
(2) Tne operaoility of tne evacuation alarm and containment isolation system snall be tested, and negative pressure verified, semiannually. A utility power outage may oe used to-initiate sucn tests.
4.7 Reactor Fuel (1) Upon receipt from tne fuel vendor, all . fuel elements shall De visually inspected and the accompanying quality. control documents checked for compliance with specifications.
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(2) Each new fuel element will be inspected for damage and flow costructions prior to insertion into the core, i
4.8 Sealed Sources Tne antimony-oeryllium sealed source snall be leak tested in accordance witn tne procedures described in tne application for license amendment dated Maren 21, 1963, except tnat the frequency of leak testing will be in accordance witn 10 CFR Part 34.25(b). The strontium-90 sealed source shall be tested for leakage and/or contamination semiannually.
- 4. ') Pool Water (1) The pH and specific resistance of the pool water Snall be determined eacn week.
(2) An analysis of tne pool water for radioactive material snail be done at montnly intervals. Inis analysis is to include SD-124 as an indicator of Sb-8e neutron source integrity.
(3) Activity of the pool water will be maasured weekly, 4.10 Core Spray The core spray in tne reactor operating position shall oe tested for operaoility samiannually.
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d 6.1.3 Staffing
- a. Tne minimum staffing wnen the reactor is not secured snall oe:
- 1. A licensed Reactor Operator in tne control room.
- 2. A second licensed reactor operator present at tne reactor facility. Unexpected aosence for two nours is acceptacle provided imediate action is taken to obtain a replacement.
- 3. A licensed Senior Reactor Operator snail oe readily available on call.
- 4. A memoer of tne operating snall snall be designated by Level 2 management as Knowledgeable 'a radiation control.
i 0. Events requiring tne presence of a Senior Operator:
- 1. All fuel-element or control-rod alterations witnin the reactor core region.
- 2. Relocations of any experiments witn reactivity wortn greater tnan or equal to one dollar.
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- 3. Recovery from unplanned or unscneduled shutdowns unless tney are of a type excluded by tne Level 2 autnority.
Sucn exclusions snall oe posted in tne control room or placed in tne appropriate procedures. Furtnermore, tne presence of a senior operator at the f acility snall not be required during recovery from unplanne'd or unscneduled snutdora or significant reduction in power in instances wnicn result from:
(1) Electrical power interruptions from internal or external f ailures exclusive of power supply f ailures of tne reactor instrumentation, control and safety systems; i
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, . . . . c (2) False signals wnicn, in tne opinion of tne Senior Operator, were properly verified to be f alse and to nave resulted from monitoring, experimental, or control equipment, or from personnel inadvertence; and (3) Intentional snutdowns made by tne Reactor Operator i wnicn are not related to tne safety of tne reactor.
Provided tnat prior to tne initiation of sucr. recovery, tne Senior Operator snall be notified of tne shutdown or power reduction, and shall determine that tne shutdown was caused oy one of tne enumerated occurrences, and snali determine tnat nis presence at tne facility during recovery is not required.
6.1.4 Selection and Training of Personnel Tne selection, training, and requalification of personnel snall meet or exceed tne requirements of ANS-15.4/N 380 and Appendix A of 10 CFR Part 55 and oe in accordance witn tne requalification plan approved by the Commission.
6.1.5 Review and Audit Tne independent review and audit of reactor facility operations snall be performed oy tne Nuclear Safeguards Committee.
6.1.5.1 Comoosition and Qualifications The_ Nuclear Safeguards Committee snall be composed of a minimum of 5 memoers. Tne memoers shall collectively provide a broad spectrum of expertise in tne appropriate reactor l tecnnology. Memoers and alternates shall be appointed by and report to tne Level 1 autnority. They may include I
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