ML18101A712
| ML18101A712 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/04/1995 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18101A711 | List: |
| References | |
| NUDOCS 9505220181 | |
| Download: ML18101A712 (3) | |
Text
ATTACHMENT 2 TECHNICAL SPECIFICATION PAGE WITH PEN AND INK CHANGES LICENSE AMENDMENT APPLICATION ONE-TIME EXTENSION OF SURVEILLANCE REQUIREMENT INTERVAL SALEM GENERATING STATION UNIT NO. 1 FACILITY OPERATING LICENSE DPR-70 LR-N95056 DOCKET NO. 50-272 LCR 95-06 The following Technical Specification for Facility Operating License No. DPR-70 is affected by this License Amendment Request:
Technical Specification 4.6.1.2.a
<-9-5052201B1-950504 - -~ -~
PDR ADOCK-05000272 P
PDR 3/4 6-2
I CONTAWM::NT SYST:'.MS C01\\TA!!*:~1:'.NT LEAKAGE LIMITING CONDITION FOR OP~RATJON
- 3. 6. 1. 2
- a.
- b.
Containment lea~age rat~s shall be limited to:
An overall integrated leakage rate of< L, 0.10 percent by weight of the containment*air per 24 hour~ at design pressure, (47.0 psig).
A combined leakage rate of~ 0.60 La for all penetrations and valves subject to Type Band C tests"as identified in Table 3.6-1, when pressurized to Pa.
APPLICABILITY:
MOOES.1, 2, 3 and 4 *
. !.CT ION:
~~ith either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or (b) with the measured combined leakage rate for all penetrationsaand valves subject to Tyr~s B and C tests exceeding 0.60 La' restore the leakage rate(s) to within the limit(s) prior to increasing the Reactor Coolant Syst~~ temperature above 200°F.
4.6.1.2 The containment leakage rates shall be demonstrated at ~he following t.est schedule and shall be determined in conforliiance with the criteria specified in Appendix J of 10 CFR SO using the methods and provisions of ANS! N45.4-1972:
- a.
Three Type A tes:s (Overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown at desi~n pressure {47~0 psig) dur~ng each 10-year servic~ period.* The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.
e second inservice Integrated Leak Rate Test shall be perfocned at the fifth refuelirg outage, out no later than May, 1984.
3/4 6-2 Amendment No. 54
INSERT The fifth inservice Integrated Leak Rate Test shall be performed prior to or during the twelfth refueling outage, but no later than November 30, 1995.