ML20004C679

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Proposed Tech Specs Re Containment Internal Pressure,Release Rate of Radioactive Matl,Decay Tank,Fuel Insp Program & Definition of Term Operable
ML20004C679
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 05/29/1981
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20004C678 List:
References
NUDOCS 8106040487
Download: ML20004C679 (10)


Text

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Jp ATTACHMENT 1 Zion-Station Units'1 and-2 Proposed Technical Specification-Changes The following pages'have been. revised:

6 219 225a

'235 247 251 275a 283 292A i

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8,106040

G.

Quadr:7nt Power Tilt K.

Operable The quadrant power tilt per unit is A system, subsystem, train, component or device shall defined as the ratio of the maximus; upper be OPERABLE or have OPERABILITY when it is capable of excore detector current to the average of the performing its specified function (s). All necessary upper excore detector currents or the ratio attendant instrumentation, controls, normal (Normal of the maximum lower excore detector current AC Off-Site or Reserve. AC Off-Site) and emergency to the average of the lower excore detector (Standby AC On-Site) AC electrical power source,.

currents whichever is greater.

If one excore cooling or seal water, lubrication or other auxiliary detector is out of service, the three in-equipment that are required for the system, subsystem, service units are used in computing the average.

train, component, or device to perform its function (s) shall also be capable of performing their related H.

Rated Thermal Power support function (s).

A steady-state reactor core output of 3250 The operability requirement for both normal'and emergency AC power supplies does not apply to AC MWt per unit.

instrument buses and associated instruments.

Operability as it pertains to the Auxiliary Electrical I.

Reactor Pressure Power System requires Normal AC Off-Site, Reserve AC The pressure in the steam space of a pressurizer.

Off-Site and Standby AC On-Site power. (See Section 3.15).

J.

Refuelino Outage L.

Operating When Refueling Outage is used to designate a surveillance interval per unit the surveillance Performing the i ' *nded functions in the intended will be performed during the refueling. outage manner.

or up to six months before the refueling outage.

When a refueling outage occurs within 8 months M.

Operating Cycle of the previous refueling outage for a unit, the surveillance testing need not be performed. The The interval between the end of one major refueling maximum interval between surveillance tests is outage and the end of the next subsequent major 20 months per unit.

refueling outage per unit.

N.

Surveillance lit-rval See Specification 4.0.2, page 27a for description of the surveillance intervals.

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.10.4 4.10.4 If changes in the inward deformation' greater than 0.25 inches occur,

.an investigation will be made to determine the cause and corrective action.

If no corrective action is necessary during the duration of the program described, the program shall be discontinued.

5.

If the containment internal press-5.

The containment pressure shall ure exceeds 1.0 psig or the inter-be verified once a shift.

nal vacuum exceeds 1.5 psig, the

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condition shall be corrected immediately or the, reactor shall be brought to the hot shutdown condition within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

6.

If the containment ambient temp-6.

The containment temperature shall erature exceeds 1200F or is less be verified once a shift.

0 than 65 F the condition shall be corrected immediately or the reactor shall be brought to the hot shut-down condition within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

7.

The provisions of Specification 3.0 3 7.

Not Applicable.

are not applicable to Specification 3.10.

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a LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT j

3.11 4.11 8.

When the release rate of radioactive 8.

Not Applicable.

materials, excluding tritium and dissolved gases, exceed 2.5 curies / unit i

during any calendar quarter, the licensee shall notify the. Director, Directorate of Licensing,within 30 days, I

identifying the causes and describing the proposed program of action to reduce such release rates.

9.

The provisions of Specification 3.0 3 9.

Not Applicable, are not applicable to Specification 3.11.

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l 225 a

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l LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT i

3.12.

4.

The maximum activity to be con-4.12, 4.

Prior to isolating a tank for tained in one gas decay tank decay the tank will be sampled shall not exceed 22,000 curies.

per Table 4.12-2 and total-(Equivalent to Xe-133).

activity determined.

5.

When the annual projected release 5.

Records.

rate of radioactive materials in gaseous wastes, averaged over-A. Facility records of iodine i

a calendar quarter exceeds twice and particulate releases with the annual objectives, the licensee half-lives greater that eight-shall. notify the Director, days shall be maintained on Directorate of Licensing within 30 the basis of all the iodine days, identifying the causes and sampling devices and particulate describing the proposed program filter analyses.

of action to reduce such release rates.

B. Records shall be maintained and.

reports of the sampling and analysis results shall be submitted in accordance with Section (Plant Reporting Require,

ments) 6 of these Specifications.

6.

The provisions of Specification 3.0 3 6.

Not Applicable, are not applicable to Specification 3.12.

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-l LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT

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3.13.8 A fuel inspection program shall be esta-4.13.8 Inspection of the fuel will include.

i blished to provide such information as can the following items

be determined from inspections performed on the discharged fuel.

This program

'l shall include the removal and examination of any special test assemblies.

A.

Results of tests,for failed fuel.

B.

Results of on-site visual examin-ations on lead burnup, special test assemblies and those typical of various discharge exposures.

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C.

Results of off-site examinations, if performed, including extent of~

-fuel densification, fission gas.

generation, clad creepdown characteristics, etc.

9. The provisions of Specification 3.0 3
9. Not Applicable.

are not applicable to Specification 3.13.

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. LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT

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3.14.1 4.14.1 The monitor shall.be recalibrated if the results are outside this span.

B.

Instrumentation may be taken D.

The instrumentation of. Table out of service for short 4.12-2 shall be calibrated periods of time for testing; every six months.

This however, the requirements of calibration procedure shall 3.14.1.C will apply.

consist of an initial electronic calibration and then a veri-fication of the calibration, using two known sources of radiation fields.

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When any of the instrumentation listed C.

Not Applicable.

C.

in table 4.14-1 is out of service, manual surveys or " grab" sampling shall be done once each shift.

D.

Radiation sensitive instrumentation D.

Other radiation instrumentation and laboratory equipment not listed and laboratory equipment shall be in Table 4.14-1 or elsewhere in the calibrated at regular intervals.

Technical Specifications shall be The Radiation Protection Depart-operable on an "as needed basis."

ment supervisor shall determine these intervals based on cperating requirements and experience.

2. The provisions of Specification 3.o.3
2. Not Applicable.

are not applicable to Specification 3.14.

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT a

3.16 3.16 2.

Within a 5-mile radius, enumeration 2.

Not Applicable.

i by using referenced information from county agricultural agents or other reliable sources.

If it is learned from this census that an-imals-are present at a location which yields a calculated thyroid dose greater than from previously sampled animals, the new loca-tion shall be added to the surveillance program as soon as practicable.The sampling location having the lowest calculated dose may then be dropped from the sur-veillance program at the end of the grazing season during which the census was conducted.

Also, any location from which milk can no longer be obtained may be dropped from the surveillance program after notifying the NRC in writing that milk-producing animals are no longer present at that location.

The provisions of Spdcification 3.0 3 3.

Not Applicable.

3.

are not applicable to Specification 3.16.

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7.

LIMITING CONDITION FOR OPERATION SURVAILLANCE REQUIREMENT 3.17.2 Aircraft Fire Detection 4.17.2 Aircraft Fire Detection Applicability i

Applicability Applies to the testing of the aircraft Applies to the testing of the aircrafti fire detectors installed on diesel fire detectors installed on diesel generator and switchgear intakes, Aux.

generator and switchgear intakes, Aux.

Bldg. intakes and cribhouse.

Bldg. intakes and cribhouse.

Objective Objective To verify that the control circuit To verify that the control circuit will trip the corresponding fan and will trip the corresponding fan and close the corresponding damper.

close the correcponding damphr.

Specification Specification 1.

The aircraft fire detection system 1.

Surveillance on the Aircraft Fire shall be operational,-

or the failed Detection system shall be as components shall be placed in the follows:

accident mode.

a.

Each air. compressor shall be verified operational once a month.

b.

Each fire detection circuit shall be tested every six months by simulating a signal equiva-lent to a fire condition and fan t

trip and associated damper closure verfied to occur within j

2 seconds.

2.

Th provisions of Specification 3.0.3' 2.

Not Applicable.

are not applicable to Specification 3.17.2.

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7 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT - 3.19 4.19 2.

Instrumenta-;on may be taken out of 2.

The instrumentation in Table 4.19-1 service for short periods of time for shall be calibrated initially electron-testing; however, the requirements of ically..

The calibration shall be 3.19.3 will apply.

verified during refueling operations using the following methods.

A.

For RTPR18, at least two different levels of radiation shall be used.

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B.

For RTPR21 at least two known concentrations of radio-active materials shall be used.

3.

When the instruments in Table 4.19-1 3.

An iodine analysis of the.. reactor are out of service, a radioactive iodine coolant system shall be done once analysis of the reactor coolant system per shift on a unit whose failed fuel shall be done on the unit whose detec-instrumentation is inoperable.

tors are inoperable.

4.

The provisions of Specification 3.0 3 4.

Not Applicable.

are not applicable to Specification 3.19.

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292A

1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.21 4.21 6.

Penetration Fire Barriers 6.

Penetration Fire Barriers A.

All penetration fire barriers pro-A.

Each of the safety related tecting safety related areas shall penetration fire barriers shall be functional at all times.

be verified to be functional by a visual inspection.

L 1.

At least once per 18 months, and 2.

Prior to declaring a penetra-tion fire barrier functional following repairs or.mainte-nance.

f B.

With one or more of the above re-j quired penetration fire ba'rriers not intact a continuous fire watch shall be established on at least one side of the affected penetra-tion within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

If an oper-able fire detector is located in the area, an hourly inspection of the penetration fire barrier may be performed rather than establishing a continuous fire watch.

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7.

The provisions of Specifications 3.0. 3 7.

Not Applicable.

are not applicable to Specification 3.21.

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