ML20079S218
| ML20079S218 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/21/1994 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20079S216 | List: |
| References | |
| NUDOCS 9410270024 | |
| Download: ML20079S218 (2) | |
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.q PY-CEI/NRR-1651 L Attachment 2 Page 1 of 2 CONTAINMENT SYSTEMS BASES 3/a.6.1 CONTAINMENT (Continued) l kepace(JM M5 7 en Tay 2./2 3/4.6.1.2 CONTAINMENT LEAKAGE (Continued) l The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J to 10 CFR 50 with the exception of exemptions granted for testing the airlocks af ter each opening.-
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and the containment leakage rate given in Specifications 3.6.1.1 and 3.6.1.2.
The specification makes allowances for the fact that there may be long periods of time when the air locks will be in a closed and secured position during reactor operation. Only one closed door in each air lock is required to main-tain the integrity of the containment.
The air supply to the containment air lock and seal system is the service and instrument air system. The system consists of two 100% capacity air compressors per unit and can be cross-connected. This system is redundant and extremely reliable and provides system pressure indication in the control room.
3/4.6.1.4 MSIV LEAKAGE CONTROL SYSTEM Calculated doses resulting from the maximum leakage allowance for the main steam line isolation valves in the postulated LOCA situations would be a small fraction of the 10 CFR 100 guidelines, provided the main steam line system from the isolation valves up to and including the turbine condenser remains intact. Operating experience has indicated that degradation has occasionally occurred in the leak tightness of the MSIV's such that the l specified leakage requirements have not always been maintained continuously. ,
The requirement for the leakage control system will reduce the untreated I leakage from the MSIV's when isolation of the primary system and containment is required.
1 3/4.6.1.5 CONTAINMENT STRUCTURAL INTEGRITY l l
This limitation ensures that the structural. integrity of the containment will be maintained comparable to the original design standards for the life of the unit. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 15 psig in the event of a LOCA. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.
I PERRY - UNIT 1 B 3/4 6-2 Amendment No. 19 9410270024 941021 PDR ADOCK 05000440 P PDR
l '
PY-CEI/NRR-1651L Attachment 2 Page 2 of 2 Bases: Insert A The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J to 10 CFR 50 with the exception of the exemptions i listed below. Additionally, Bechtel Topical Report BN-TOP-1 may be utilized for ILRTs with a duration of less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in accordance with section 7.6 of ANSI N45.4-1972 (Reference 1).
1 a) Section III.D.2(b)(ii) - The air lock seal leakage test of Section III.D.2(b)(iii) of Appendix J may be substituted (following normal air lock door opening) for the full-pressure test provided that no maintenance has l been performed that vould affect the air locks sealing capability (Reference '
l 2).
l b) Sections III.A.1(d), III.A.5(b)(2), and III.B.3 and III.C.3 - The main steam lines between the inboard and outboard MSIVs (including the volume up to the outboard MSIV before seat drain line valves) are not required to be vented and drained for Type A testing, and the main steam line isolation valve leak rates are exempted from inclusion in the overall integrated primary containment leak rate and the combined local leak rate (Reference 3).
1 c) Section III.D.1(a) - The third Type A test for each 10-year service period is not required to be conducted when the plant is shutdown for the 10-year plant inservice inspection (Reference I:).
d) Section III.D.3 - Type C local leak rate testing may oe performed at other convenient intervals in addition to shutdown during refueling, but at intervals no greater than 2 years (Reference 3).
I References (1) Letter from NRC (B.J. Youngblood) to CEI (M.R. Edelman), " Performance of the Preoperational Containment Integrated Leak Rate Test - Perry Nuclear Power Plant, Unit 1," dated June 10, 1985.
(2) PNPP Safety Evaluation Report Supplement 7, Section 6.2.6 " containment Leakage Testing," November 1985.
(3 through 5) [ Exemption approval letter (s) from the NRC.]
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