ML20092G962

Forwards marked-up Draft Tech Specs Re Radiation Monitoring Instrumentation for Plant Operations Surveillance Requirements & Accident Monitoring Instrumentation

ML20092G962
Person / Time
Site:	Catawba
Issue date:	06/20/1984
From:	Tucker H DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8406250310
Download: ML20092G962 (5)

Text

. 4 Dunn POWEIt Goxvm P.O. HOX 03180 CHAHLOTTE, N.C. 28242 IIAL 15. TUCKER TELEPHOME

• • m Parassent (704) 073-4NH ptsE LRAE rpOD00TMMs June 20, 1984

'Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief ,

Licensing Branch No. 4 Re: Catawba Nuclear Station, Unit 1 Docket No. 50-413 Draft Technical Specifications

Dear Mr. Denton:

{

Based on the telephone conversation between Mr. Fred Anderson of your staff and representatives of Duke Power Company, attached are changes to the Catawba Draft Technical Specifications.

Very truly yours, M k ,/ ---w Hal B. Tucker RWO/php Attachment-cc: Mr. James P. O'Reilly. Palmetto Alliance Regional Administrator 21351 Devine Street U. S. Nuclear Regulatory Commission Columbia, South Carolina 29205 Region II 101 Marietta Street, NW, Suite 2900 Mr. Jesse L. Riley Atlanta, Georgia 30323 Carolina Environmental Study Group 854 Henley Place NRC Resident Inspector Charlotte, North Carolina 28207 Catawba Nuclear Station Mr. Robert Guild, Esq.

Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412 8406250310 840620 PDR ADOCK 05000-A I o

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TABLE 3.3-6 (Continued)

TABLE NOTATIONS With fuel in the fuel storage pool areas. ~

With irradiated fuel in the fuel storage pool areas.

Trip Setpoint concentration value (pCi/ml) is to be established such that the actual submersion dose rate would not exceed 2 mR/h in the containment building. The Setpoint value may be increased up to the equivalent limits of Specification 3.11.2.1 in accordance with the metha logy and parameters in the ODCM during containment purge or ventgr;;id:d t e Setpoint value 4ee+

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determined sample analysis performed prior to each release in accordance with l%Table t .11-2pu). b;,;),,} fajfa) . SQ; 4y a u.. a ACTION STATEMENTS ACTION 30 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge and exhaust valves are maintained closed.

ACTION 31 - With the number of operable channels one less than the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> isolate the affected Control Room Ventilation System intake from outside air with recirculating flow through the HEPA filters and charcoal adsorbers.

ACTION 32 - With less than the Minimum Channels OPERABLE requirement, opera-tion may continue for up to 30 days provided an appropriste portable continuous monitor with the same Alarm Setpoint is provided in the fuel storage pool area. Restore the inoperable monitors to OPERABLE status within 30 days or suspend all operations involving fuel movement in the fuel building.

ACTION 33 - Must satisfy the ACTION requirement for Specification 3.4.6.1.

ACTION 34 - With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, operation may continue provided the Fuel Handling Ventilation Exhaust System is operating and discharging through the HEPA filters and charcoal adsorbers.

Otherwise, suspend all operations involving fuel movement in the fuel building.

ACTION 35 - With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, operatio1 may continue provided the Auxiliary Building Filtered Ventilation Exhaust System is operating and discharging through the HEPA filter and charcoal adsorbers.

ACTION 36 - With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, operation may continue for up to 30 days provid'ed that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for radioactivity (gross gamma) at a lower limit of detection of no more than 10 7 pCi/ml.

CATAWBA - UNIT 1 3/4 3-53

!Un 8 SM

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

TABLE 4.3-3 9

f RADIATION MONITORING INSTRUMENTATION FOR PLANT 1 5 OPERATIONS SURVEILLANCE REQUIREMENTS ANALOG  ;

5[ CHANNEL MODES FOR WHICH q CHANNEL CHANNEL OPERATIONAL SURVEILLANCE  !

g FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED

1. Containment '

a. Containment Atmosphere - High i

Gaseous Radioactivity (Low '

Range - EMF-39) S R M All i

b. Reactor Coolant System S R M 1,2,3,4 ,

1 Leakage Detection (Low Range - EMF-38 and i Low Range - EMF-39)  !

[ 2. Fuel Storage Pool Areas y a. High Gaseous Radioactivity g (Low Range - EMF-42)

S R M **

't; y y ,

b. Criticality-Radiation Level S R M

• 2E:n (Fuel Bridge - Low Range.- ~1 l EMF-15) ,M

3. Control Room Air Intake Radiation Level - S R M All t

liigh Gaseous Radioactivity -

(Low Range - EMF-43 % & B)

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4. Auxiliary Building Ventilation High Gaseous Radioactivity S R M All (Low Range - EMF-41 M )

5. Component Cooling Water System S R M All (EMF-46 A&B)

TABLE NOTATIONS 1

• With fuel in the fuel storage pool area.

• • With irradiated fuel in the fuel storage pool areas.

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

_ ~ _ . _ . . _ . .

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INSTRUMENTATION y ACCIDENT MONITORING INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION i

3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10  !

shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With the number of OPERABLE accident monitoring instrumentation channels less than the Total Number of Chanaels shown in l Table 3.3-10, restore the inoperable channel (s) to OPERABLE '

status within 7 days, or be in at leastdiOT SHUT 00WNwithin the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. / --

b. With the number of OPERABLE acci ent

-Nh area channels except the unit vent- gh range Dg;gonitAinf;nstrumptatio m nftor, the steam relief valve exhaust rad ation me i or, th ontainment atmosphere-high range radiatio mo ~ r, an he reactor coolant radiation level less than the Minimum Channels OPERABLE requirements

" of Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTOOWN within the next, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c. Wit umber of OPERABLE Channels for the unit vent- A J';;nmjnitor,orthesteamreliefvalveexhaustra /

monito p ol' the containment atmosphere-high range radiation monitor, or the reactor coolant radiation level less than required by the .

Minimum Channels OPERABLE requirements, initiate t.t pr;p'; .xd Art alternate method of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and either restore the inoperable channel (s) to OPERABLE status within 7 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days that

" provides actions taken, cause of the inoperability, and the plans and schedule for restoring the channels to OPERABLE status.

d. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.

w CATAWBA - UNIT 1 3/4 3-65

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TABLE 3.3-10 (Continued)

O y

ACCIDENT MONITORING INSTRUMENTATION E

5 TOTAL MINIMUM e '

NO. OF CHANNELS c INSTRUMENT ,

CHANNELS 5 ~

OPERABLE

~

15. In Core Thermoc 16 4/ core quhdrant 2/ core quadrant

16. Unit Vent - 1 R Am ge h Monitor (EMF-54) , N.A. 1 or-17.

Steam Relief Valve Exhaust Radiation Monitor (EMF-26, 27, A)29) N.A. 1//_;. ' t .._ v

18. Containment Area - High Range Radiation Monitor (EMF-53 N.A.

B) 1

19. Reactor Vessel Water Level 2 1

20. Reactor Coolant Radiation Level (EMF-48) N.A. 1 Y

0 TABLE NOTATIONS Z

• Not applicable if the associated block valve is in the closed position. M ,

T

• • Not applicable if the associated block valve is in the closed position and power is removed.

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