IR 05000266/1977014
| ML20237B609 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/28/1977 |
| From: | Kohler J, Little W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20237B608 | List: |
| References | |
| 50-266-77-14, TAC-07711, TAC-08404, TAC-7711, TAC-8404, NUDOCS 8712160416 | |
| Download: ML20237B609 (5) | |
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U.S.-NUCLEAR REGULATORY COMMISSION-l OFFICE OF INSPECTION AND ENFORCEMENT RECION III Report No. 50-266/77-14 l
Docket No. 50-266 License No. DPR-24
. Licensee: Wisconsin Electric Power Company
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Wisconsin Michigan Power Company-231 West Michigan Milwaukee, WI 53201 Facility Name: Point Beach Nuclear Plant, Unit 1 Inspection At: Point Beach Site, Two Creeks, WI
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Inspected Conoucted: October 4, 5, 8, and 9, 1977 J
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Inspector:
J. E. Kohler
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I Accompanying Personnel:
K. A. Connaughton
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Approved by:
Lift 1 C
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Nuclear Support Section
Inspection Summary Inspection on October 4, 5, 8, and 9,1977 (Report No. 50-266/77-14)
Areas Inspected:
Rnutine, announced inspection of the performance of
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the 1977 Unit 1 corgainment integrated leak rate test and analysis of the CILRT test data.' The inspection involved 15 inspector-hours on-site by one NRC inspector.
Results:
No items of noncompliance or deviations were identified.
The preliminary results of the CILRT have been forwarded to NRC Headquarters for their review.
8712160416 771101 PDR ADOCK 05000266 h
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DETAILS 1.
Persons Contacted
- G. Reed, Manager, Nuclear Power Division
- F. Rhodes, Operations Superintendent c.
J. Greenwood, Assistant to Manager
- R. Mitchell, Reactor Operations
- T. Ross, Reactor Operations
- C. Gross, Cognizant Engineer for CILRT 2.
1977 Unit 1 CILRT (October 9-10, 1977)
The 1977 Unit 1 CILRT was performed during a twelve hour period between October 8 and 9,1977. At the conclusion of the test, the licensee measured a leakage rate at the 95% upper confidence level of approximately.02 w/o/ day. Technical Specifications and 10 CFR 50, Appendix J, require the containment to leak at a rate less than.4 w/o/ day at 60 psig and.212 w/o/ day at 30 psig.
The RIII office has no further questions regarding the results of the Unit 1 test and has forwarded to NRC Headquarters an infor-mation package containing pertinent information regarding the performance of the test.
3.
Acceptance Criteria Based on criteria set forth in 10 CFR 50, Appendix J, regarding acceptance' criteria for leakage rate measurements during per-
'formance of a reduced pressure CILRT, the following data is used to compute the allowable leak rate.
Pt = 30 psig Pa = 60 psig Ltm = (Peop).0824 w/o/ day Lam = (Peop).0235 w/o/ day Acceptance criteria for a reduced pressure CILRT at 30 psig:
75% Lt =.212 w/o/ day.
4.
Supplementary Leak Rate Test At the conclusion of the CIRLT, a supplementary test was performed in which an induced leak equivalent to.118 w/o/ day (2.51 cfm) was
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superimposed. The licensee measured approximately.16 w/o/ day at the conclusion of data'taking..This value is within the 25% Lt.
criteria stipulated by 10 'CFR 50, Appendix J, and is confirmatory of the' 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> measured CILRT value.
5.
Corporate Meeting of October 5, 1977
1 The inspection identified three areas in the preliminary CILRT procedure review that were at variance with either.10 CFR 50,
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Appendix J, or established NRC positions. The three items were discussed with the Plant Superintendent and the cognizant cor-porate engineer. The areas are summarized 'below:
i No procedural requirement for venting the primary system to a.
containment test pressure during the CILRT.
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NRC acceptance criteria for test acceptability utilizing the upper confidence level leakage rate disagreed with the licensee's acceptance criteria.
c.
The licensee's technical specifications (15.4.4, I.A.3.)
permit' subtraction of the results of Local Leak Rate Tests from the measured leakage rate during Type A tests.
Each of the licensee's positions are contrary to the NRC position statements in the enclosure to the memorandum from the NRC to the licensee dated October 4,1977.
6.
Point Beach 10 CFR 50, Appendix J, Exemption Correspondence The inspector reviewed the licensee's 10 CFR 50, Appendix J, exemption correspondence at the site. A letter to NRC dated December, 1975 stated a committment to vent the following lines to containment test pressure:
i Penetration No.
Line Description
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14A Nitrogen to Pressurizer Relief Tank 15, 16, 17, 18 Component Cooling Supplies and Returns for Reactor Coolant Pumps 28A, B, C Reactor Coolant System Sample Lines 32C Auxiliary Charging Line
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33A, B Instrument Air l
l 34B, C Steam Generator Sample Lines 50, 51 Steam Generator Blowdown Lines 30C Unit 1 Reactor Makeup Water to Pressurizer Relief Tank (PRT)
These lines were verified to be vented to containment during the CILRT.
7.
Lines Not Vented During CILRT As per NRC position memo sent to the licensee dated October 4, 1977, item No. 1, the licensee is being requested to identify lines not drained and vented to containment test pressure during the CILRT along with the results of as found and as left local leak - rate tests performed at 60 psig. These values along with the upper 95% confidence limit of the limit 1 CILRT will be transmitted to DOR for their review.
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8.
CILRT Valve Line Up During the CILRT, the inspector reviewed the valve lineup with respect to closed systems penetrating containment. The following penetrations were reviewed:
Penetration No.
Line Description 14A Nitrogen to Pressurizer Relief Tank 15, 16, 17, 18 Component Cooling Supplies and Returns for Reactor Coolant Pumps 28A, B, C Reactor Coolant System Sample Lines
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32C Auxiliary Charging Line 33A, B Instrument Air 34B, C Steam Generator Sample Lines 50, 51 Steam Generator B1rwdown Lines 30C Unit 1 Reactor Makeup Water to Pressurizer Relief Tank (PRT)
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It was noted during the review that some of the isolation valves in these lines were lined up for the test such that simulated post accident differential pressure may not have been experienced by the designated containment isolation valve. The requirement for the differential pressure is
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H oweve r,
S the lineup was as described in exemption correspondence dated December 1975. Consequently, the inspector has no questions regarding this lineup discrepancy, and the licensee information regarding isolation valves in question has been forwarded to NRC for review.
9.
Exit Int e rview The inspector met with the licensee and his representatives at the conclusion of the inspection and summarized the results of the inspection.
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