ML17054B230
| ML17054B230 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/23/1984 |
| From: | Haughey M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8412050345 | |
| Download: ML17054B230 (14) | |
Text
Docket No:
50-410'PPLICANT:
Niagara Mohawk Power Corporation (NMPC) 1 FACILITY:
Nine Mile Point Unit 2 (NMP-2)
SUBJECT'UMMARY OF MEETING WITH NMPC CONCERNING CONTAINMENT SYSTEMS ISSUES FOR NINE MILE POINT 2 On November 14, 1984 the NRC staff met with representatives of NMPC and Stone and Webster Engineering Corporation (SWEC) to discuss concerns in the area of containment systems for NMP-2.
Four major areas of concern were identified (a) Steam Bypass, (b) Conformance to 10 CFR 50 Appendix J, (c) Secondary Containment Bypass and (d) Containment Isolation.
A detailed summary of each of the four issues discussed is contained in Enclosure 1.
A list of meeting attendees is included in Enclosure 2.
cc:
J.
Lane J. Kudrick E. Weinkam J.
Read
~6CQQX 6$ggQQ ~ g Mary F. Haughey, Project Manager Licensing Branch No.
2 Division of Licensing
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Docket No:
50-410 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
~+ 83 1984 APPLICANT:
Niagara Mohawk Power Corporation (NMPC)
FACILITY:
Nine Mile Point Unit 2 (NMP-2)
SUBJECT:
SUMMARY
OF MEETING WITH NMPC CONCERNING CONTAINMENT SYSTEMS ISSUES FOR NINE MILE POINT 2 On November 14, 1984 the NRC staff met with representatives of NMPC and Stone and Webster Engineering Corporation (SWEC) to discuss concerns in the area of containment systems for NMP-2.
Four major areas of concern were identified (a)
Steam Bypass, (b) Conformance to 10 CFR 50 Appendix J, (c) Secondary Containment Bypass and (d) Containment Isolation.
A detailed summary of each of the four issues discussed is contained in Enclosure 1.
A list of meeting attendees is included in Enclosure 2.
cc:
J.
Lane J. Kudrick E. -Weinkam J.
Read Mary F. Haogaey, project Manager Licensing Branch No.
2 Division of Licensing
1
Nine Mile Point 2 Mr. B. G. Hooten Executive Director, Nuclear Operations Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 CC:
Mr. Troy B. Conner, Jr.,
Esq.
Conner 8 Wetterhahn Suite 1050 1747 Pennsylvania
- Avenue, N.W.
Washington, D.C.
20006 Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus
- Syracuse, New York 12223 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector Nine Mile Point Nuclear Power Station P. 0.
Box 99
- Lycoming, New York 13093 Mr. John W. Keib, Esq.
Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Jay M. Gutierrez, Esq.
U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Norman Rademacher, Licensing Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202
Enclosure I Summary of Issues Discussed at November 14, 1984 Meeting on Containment Systems at Nine Mile.Point Unit 2.
Steam B
ass NMPC stated that 107 seconds were required to establish flow to the containment spray.
Total operator action would take on the order of 4 to 5 minutes including valve stroke time.
The assumptions made in the analysis were discussed.
Additional information is necessary as follows:
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a) verification of 50% efficiency b) justification for not including sensitivity of steaming effect from downcomers.
(c) method used relative to heat transfer (d) condition of wetwell air space (e) heat transfer coefficient at superheated state (f
8% rebate, drywell and suppression pool NMPC was also requested to identify where in the FSAR they included their commitment to test the steam bypass system once every refueling outage.
B ass from Secondar Containment Additional bypass paths from secondary containment were identified as the MSIV and Feedwater R>ICU and drain lines.
NHPC believes the mainsteam line failure assumed in their analysis is bounding over the feedwater line.
NMPC is to provide the details of the analysis and the details of the leakage characteristics to demonstrate reasoning behind the statement that the mainsteam line ailure is bounding.
NMPC took credit for the decay in containment pressure over time in their leakage analysis rather than analyzing at peak pressure.
NHPC was requested to provide a tabulation of assumptions used in this analysis and a discussion on the assump-tions on temperature.
In addition NMPC was told that a method for verifying leakage vs. pressure was necessary if NMP-2 was to take credit for pressure vs.
time.
NMPC has identified the post-accident monitoring system as a potential bypass leakage path.
The HSIV has been identified as a concern both in the areas of containment systems and accident evaluation.
NMPC identified and discussed alternate methods of leakage testing.
NMPC was told that while taking credit for delay in the piping runs and dilution in the vertical runs is acceptable, taking credit for plateout is not acceptable.
20 scfh is the NHPC target MSIV leakage for the Technical Specifications.
NRC requested future submittals concerning the MSIV leakage be explicit.
4I
Containment Isolation Although Feedwater (FW) check valves were not included in the letter on isolation valves they will not be deleted from the FSAR table.
For the RCIC/RHR head spray the isolation valves noted are check valves, inboard and outboard.
The motor operated valve (MOV) in the line needs to be added to the table of isolation valves and verification is needed that the MOV in the line will not be overridden.
Penetration Z-38 A and B; Recirculation pump seal cooling:
NMP-2 does not have a
MOV in this line to backup the check valves used for inboard and outboard isolation.
Both NMPC and NRC will review other projects to determine how isolation of this line has been taken care of in the past.
Penetration Z-99D, Hydraulic Unit to Recirc.:
A second valve is needed in this line.
NMPC is still reviewing leak testing on the Mainsteam (MS) drain line (penetration 93A, B, C, 8( D)
Penetration Z-36, 37, 34 E 5 F - valve will be locked closed.
Penetration 2 Isolation valve table needs to be completed.
Penetration Z-90, RCIC turbine exhaust vacuum breaker, signals F
8 H combine for closure.
Test lines with only a single isolation valve and a screwed-on cap need an acceptable second isolation.
NMPC needs to identify the lines where a screwed-on cap was considered the second isolation barrier and inform the NRC what alternate means of isolation will be used.
Conformance to 10 CFR A endix J NMPC needs to provide justification for reverse flow testing.
NMPC stated it will be coming in shortly.
TIP System (a)
Type C testing of the ball valve -
NMPC believes the disassembly of the valve and breaking of the nitrogen purge will degrade the valve.
NMPC stated that they believe other Mark II plants do test this valve.
This valve falls under Appendix J type valves and therefore needs to be tested.
(b) sheer valve test -
NMPC also believes this valve should not be tested.
4
II.E.4.2 FSAR response needs to be updated to 'show that the purge valve control modifications have been completed.
NNPC intends to request an exemption for recirculation flow control'alves.
The mainsteam valves will be tested at PA.
Airlocks will be tested every 6 months.
Hydrogen recombiner valves will be Type A tested open and Type C tested closed.
FSAR Table 6.2-85 needs clarification for PA and PT.
NNPC stated that their intent to limit purging to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> will be in the Technical Specifications.
Enclosure 2
ATTENDEES November 14, 1984 Meeting on Containment Systems Issues for Nine Mile Point 2
NRC M. Haughey J.
Lane J. Kudrick J.
Read E. Weinkam P. Salminen NMPC J.
R. Spadafore N. Rademacher D. Hill P. Mazzaferro SHEC H. B.
R. H.
M. K.
G.
R.
V. B.
M. S.
Thickman Pinney Allen Mikula Patel Stocknoff
"l