ML20206A044

Proposed Tech Spec Pages 2-8,3/4 3-39,3/4 4-28,3/4 6-23,6-4 & 6-13 Re Instrumentation,Rcs,Containment Isolation Valves, Unit Organization & Administrative Controls

ML20206A044
Person / Time
Site:	Braidwood
Issue date:	04/02/1987
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20205T726	List: ML20205T722 ML20206A044
References
RTR-NUREG-1223 NUDOCS 8704070398
Download: ML20206A044 (6)

Text

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TABLE 2.2-1 (Continued)

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y TABLE NOTATIONS (Continued) ~

8 NOTE 1: (Continued)

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= Time constant utilized in the measured T avg lag compensator, to = 0 s, T' 5 588.4 F (Nominal T avg t RATED THERMAL POWER),

2' K3 = 0.00134, ro P = Pressurizer pressure, psig, P' = 2235 psig (Nominal RCS operating pressure),

L o Plact S transform operator, s 2, and f t(AI) is a function of the indicated difference between top and bottom detectors of the T power-range neutron ion chambers; with gains to be selected based on measured instrument oo response during plant STARTUP tests such that:

(i) for qt - Ob between -m% and +10%, f (AI) = 0, where qt and qb are percent 3

RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + 9b is total THERMAL POWER in percent of RATED THERMAL POWER; (ii) for each percent that the magnitude of qt 9bexceeds +10%, the AT Trip Setpoint shall be automatically reduced by 2.0% of its value at RATED THERMAL POWER.

NOTE 2: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 3.9% of aT span. ,

8704070398 870402 PDR ADOCK 05000456 P PDR

1 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT OPERATIONS LIMITING CONDITION FOR OPERATION 3.3.3.1* The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall be OPERABLE with their Alarm / Trip Setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a. With a radiation monitoring channel Alarm / Trip Setpoint for plant operations exceeding the value shown in Table 3.3-6, adjust the Setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

b. With one or more radiation monitoring channels for plant operations inoperable, take the ACTION shown in Table 3.3-6.

! c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and DIGITAL CHANNEL OPERATIONAL TEST for the MODES and at the frequencies shown in Table 4.3-3.

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• Control Room isolation not required prior t 4a44e4 criticality on Cycle 1. I J

BRAIDWOOD - UNITS 1 & 2 3/4 3- I j

REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION ACTION (Continued)

MODES 1, 2, 3, 4, and 5:

With the specific activity of the reactor coolant greater than 1 microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microCuries per gram of gross radioactivity, perform the sampling and analysis requirements of Item 4.a) of Table 4.4-4 until the specific activity of the reactor coolant is restored to within its limits. Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days with a copy to the Director, Nuclear Reactor Regulation. Attention: Chief, h O p t_ - A "crfor = c Branch, and Chief, Accident Evaluation Branc @ U.S. Nuclear Regulatory Commission, Washington, D.C. , 20555. This report shall contain the results of the specific activity analyses together with the following information:

I

a. Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded:

b. Results of: (1) the last isotopic analysis for radiciodine performed prior to exceeding the limit, (2) analysis while limit was exceeded, and (3) one analysis after the radiciodine was reduced to less than the limit, including for each isotopic analysis, the date and time of sampling and the radioiodine concentration; I

c. Clean up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded,

d. History of degassing operation , if any,, starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded, and

e. The time duration when the specific activity of the primary coolant exceeded 1 microcurie per gram DOSE EQUIVALENT I-131.

@ea.c.kc S y s+ em s SURVEILLANCE REOUIREMENTS l l

1 4.4.8 The specific activity of the reactor coolant shall be determined to be '

within the limits by performance of the sampling and analysis program of Table 4.4-4.

I BRAIDWOOD - UNITS 1 & 2 3/4 4-28 i

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TABLE 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES MAXIMUM PENETRATION VALVE NO. FUNCTION ISOLATION TIME (SEC)

9. Manual (Continued) 99 FW0150*,# Feedwater N.A.

100 FWO15A*,# Feedwater N.A.

101 FW0158*,# Feedwater_ N.A.

102 FWO15C*,# Feedwater N.A.

10. Check 28 CV8113 RCP Seal Water Return N.A.

37 CV8348* RCS Loop Fill N.A.

6 W0007A Chilled Water N.A.

4 10 W0007B Chilled Water N.A.

1 21 CC9534 RCP Mtr Brng Return N.A.

24 CC9518 RCP Thermal Barrier Return N.A.

25 CC9486 RCP Cooling Wtr Supply N.A.

1 C5008A Containment Spray N.A.

16 CS008B Containment Spray N.A.

39 IA091 Instrument Air N.A.

30 WM191 Make-Up Demin N.A.

52 PR032 Process Radiation N.A.

AL PR002G Process Radiation N.A.

AL PR002H Process Radiation N.A.

l 12 PS231A Hydrogen Monitor N.A.

1. 31 PS231B Hydrogen Monitor N.A.

l 27 RY8047 PRT Nitrogen N.A.

44 RY8046 PRT Make-Up N.A.

26 SI8815* Safety Injection N.A.

50 SI8818A* Safety Injection N.A.

50 SI88180* Safety Injection N.A.

51 SI8818B* Safety Injection N.A.

51 SI8818C* Safety Injection N.A.

59 905A* Safety Injection N.A. j 59 " I C. -- Safety Injection N.A.

60 SI8819A* Safety Injection N.A.

60 SI8819B* Safety Injection N.A.

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l ADMINISTRATIVE CONTROLS ONSITE (Continued) j

3) Review of all proposed changes to the Technical Specifications;

4) Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety;

5) Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Assistant Vice President and General Manager Nuclear Stations and to the Superintendent of the Offsite Review and Investigative Function;

6) Review of all REPORTABLE EVENTS;

7) Performance of special reviews and investigations and reports thereon as requested by the Superintendent of the Offsite Review nd Investigative Function; Review of the Station Securi y Plan and implementing procedures and submittal of recommended x -

n -- u- - . .ma c--- g u 7 =;hanges g St;t$; to the Assi"h pgc

t ir: o-f C o r po ca +e- S e c.un t-

9) Review of the Emer an and station implementing procedures and submittal of recommended changes to the Assistant Vice President and General Manager Nuclear Stations;

10) Review of Unit operations to detect potential hazards to nuclear safety;

11) Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering. evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Assistant Vice President and General Manager Nuclear Stations and the Superintendent of the Offsite Review and Investigative Function; and

12) Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL, and the Radwaste Treatment Systems.

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c. Authority The Technical Staff Supervisor is responsible to the Station Manager and shall make recommendations in a timely manner in all areas of review, investigation, and quality control phases of plant mainte- .

nance, operation, and administrative procedures relating to facility j operations and shall have the authority to request the action neces- l sary to ensure compliance with rules, regulations, and procedures when in.his opinion such action is necessary. The Station Manager shall follow such recommendations or select a course of action that <

1 BP,AIDWOOD - UNITS 1 & 2 6-13 l l

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