ML030350491
| ML030350491 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/05/2002 |
| From: | NRC/NRR/DLPM/LPD1 |
| To: | |
| References | |
| TAC MB2815, TAC MB2816 | |
| Download: ML030350491 (3) | |
Text
ADMINISTRATIVE CONTROLS (vi)
A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.
- d.
Backup Method for Determining Subcooling Margin A program which will ensure the capability to accurately monitor the Reactor Coolant System Subcooling Margin.
This program shall include the following:
(i)
Training of personnel, and (ii)
Procedures for monitoring
- e.
Deleted 6.8.4.f.
Primary Containment Leakage Rate Testing Program A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10CFR50.54(o) and 10CFR50, Appendix J, Option B, as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program', dated September 1995.
The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 47.0 psig.
The maximum allowable containment leakage rate, L,, at P,, shall be 0.1% of primary containment air weight per day.
Leakage Rate Acceptance Criteria are:
- a.
Primary containment leakage rate acceptance criterion is less than or equal to 1.0 L..
During the first unit startup SALEM -
UNIT 1 6-19 Amendment No. 254 I
ADMINISTRATIVE CONTROLS (vi)
A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.
- d.
Backup Method for Determining Subcooling Margin A program which will ensure the capability to accurately monitor the Reactor Coolant System Subcooling Margin.
This program shall include the following:
Wi)
Training of personnel, and (ii)
Procedures for monitoring
- e.
Deleted 6.8.4.f.
Primary Containment Leakage Rate Testing Program A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10CFR50.54(o) and 10CFR50, Appendix J, Option B, as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, aPerformance-Based Containment Leak-Test Program', dated September 1995, as modified by the following exception:
- a.
NEI 94-01-1995, Section 9.2.3: The first Type A test performed after March 24, 1992 shall be performed no later than March 24, 2007.
The peak calculated containment internal pressure for the design basis loss of coolant accident, P,, is 47.0 psig.
The maximum allowable containment leakage rate, La, at P., shall be 0.1%
of primary containment air weight per day.
Leakage Rate Acceptance Criteria are:
- a.
Primary containment leakage rate acceptance criterion is less than or equal to 1.0 La.
During the first unit startup following testing in accordance with this program, the leakage rate SALEM - UNIT 2 6-19 Amendment No. 235
18 (b)
Reactor Coolant System Vents (Section 22.3. II.B.1)
PSE&G shall submit procedural guidelines for and a description of the reactor coolant system vents by July 1, 1981.
The reactor coolant system vents shall be installed no later than July 1, 1982.
(c)
Plant Shielding (Section 22.3. II.B.2)
PSE&G shall complete modifications to assure adequate access to vital areas and protection of safety equipment following an accident resulting in a degraded core not later than January 1, 1982.
(d)
Deleted (e)
Relief. Safety and Block Valve Test Reauirements (Section 22.3. II.D.1)
PSE&G shall qualify the reactor coolant system relief, safety and block valves under expected operating conditions for design basis transients and accidents in accordance with the plant-specific requirements and schedules established in NUREG-0737, "Clarification of TMI Action Plan Requirements.0 (f) Auxiliary Feedwater Initiation and Indication (Section 22.3. II.E.1.2)
PSE&G shall upgrade, as necessary, automatic initiation of the auxiliary feedwater system and indication of auxiliary feedwater flow to each steam generator to safety grade quality no later than July 1, 1981.
Amendment No. 2351 I