ML051400181

Technical Specifications, Issuance of Amendment Hydrogen Recombiners & Hydrogen Monitors

ML051400181
Person / Time
Site:	Braidwood
Issue date:	05/26/2005
From:	Dick G NRC/NRR/DLPM/LPD3
To:	Crane C Exelon Generation Co
Dick G F, NRR/DLPM, 415-3019
Shared Package
ML051400142	List: ML050950588 ML051400173 ML051400181
References
TAC MC4489, TAC MC4490, TAC MC4491, TAC MC4492
Download: ML051400181 (5)

Text

PAM Instrumentation 3 .3 .3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required b D .1 Restore one required 7 days Required Action A .1 channel to OPERABLE and referenced in status .

Table 3 .3 .3-1 .

E. One or more Functions E .1 Restore all but one 7 days with two or more required channel to required channels OPERABLE status .

inoperable .

F- ---------NOTE--------- F .1 Be in MODE 3 . 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Not applicable to Functions 11, 12, and AND 14 .

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F .2 Be in MODE 4 . 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Required Action and associated Completion Time of Condition D or E not met .

(continued)

BRAIDWOOD - UNITS 1 & 2 3 .3 .3 - 2 Amendment 137

PAM Instrumentation 3 .3 .3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G- _________NOTE_________ G .1 Initiate action in Immediately Only applicable to accordance with Functions 11, 12, and Specification 5 .6 .7 .

14 .

Required Action and associated Completion Time of Condition D or E not met .

SURVEILLANCE REQUIREMENTS

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NOTE -------------------------------------

SR 3 .3 .3 .1 and SR 3 .3 .3 .2 apply to each PAM instrumentation Function in Table 3 .3 .3-1 .

SURVEILLANCE FREQUENCY SR 3 .3 .3 .1 Perform CHANNEL CHECK for each required :31 days instrumentation channel that is normally energized .

SR 3 .3 .3 .2 ___________________NOTE-___________________

Radiation detectors for Function 11, Containment Area Radiation, are excluded .

Perform CHANNEL CALIBRATION . 18 months BRAIDWOOD - UNITS 1 & 2 3 .3 .3 - 3 Amendment 137

PAM Instrumentation 3 .3 .3 Table 3 .3 .3-1 (page 1 of 1)

Post Accident Monitoring Instrumentation APPLICABLE MODES OR OTHER SPECIFIED FUNCTION CONDITIONS REWIRED CHANNELS CONDITIONS

l. Reactor Coolant System (RCS) Pressure 1,2,3 2 B (Wide Range)

2. RCS Hot Leg Temperature (Wide Range) 1,2,3 2 B

3. RCS Cold Leg Temperature (Wide Range) 1,2,3 2 B

4. Steam Generator (SG) Water Level 1,2,3 1 D (Wide Range)(per SG)

5. SG Water Level (Narrow Range)(per SG) 1,2,3 1 D

6. Pressurizer Water Level (Narrow Range) 1,2,3 2 B

7. Containment Pressure (Wide Range) 1,2,3 2 B

8. Steam Line Pressure (per SG) 1,2,3 2 B

9. Refueling Water Storage Tank Water Level 1,2,3 2 B 10 . Containment Floor Water Level (Wide Range) 1,2,3 2 B 11 . Containment Area Radiation (High Range) 1,2,3 1 D 12 . Main Steam Line Radiation (per steam line) 1,2,3 1 D 13 . Core Exit Temperature (per core quadrant) 1,2,3 4 B 14 . Reactor Vessel Water Level 1,2,3 2 B BRAIDWOOD - UNITS 1 & 2 3 .3 .3 - 4 Amendment 137

3 .6 .8 3 .6 CONTAINMENT SYSTEMS 3 .6 .8 (Deleted)

BRAIDWOOD - UNITS 1 & 2 3 .6 .8-1 Amendment 137

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .6 Reactor Coolant System {RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates, and Power Operated Relief Valve (PORV) lift settings shall be established and documented in the PTLR for the following :

LCO 3 .4 .3, "RCS Pressure and Temperature (P/T) Limits," and LCO 3 .4 .12, "Low Temperature Overpressure Protection (LTOP)

System" ;

b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in NRC letters dated January 21, 1998, "Byron Station Units 1 and 2, and Braidwood Station, Units 1 and 2, Acceptance for Referencing of Pressure Temperature Limits Report," and August 8, 2001, "Issuance of Exemption from the requirements of 10 CFR 50 Part 60 and Appendix G for Byron Station, Units 1 and 2 and Braidwood Station, Units 1 and 2" ; and

c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto .

5 .6 .7 Post Accident Monitoring Report When a report is required by Condition C or G of LCO 3 .3 .3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days . The report shall outline the preplanned alternate method of monitoring, the cause of the inopera ility, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status .

BRAIDWOOD - UNITS 1 & 2 5 .6 - 5 Amendment 137