ML18037A037
| ML18037A037 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/14/1984 |
| From: | Haughey M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8409240343 | |
| Download: ML18037A037 (16) | |
Text
Docket No; 50-410 ct.-p q,t. lo,'.
APPLICANT:
-FACILITY:
SUBJECT:
Niagara Mohawk Power Corporation (NMPC)
Nine Mile Point Unit 2 (NMP-2)
SUMMARY
OF MEETINGS i<1TH NMPC CONCERNING OPEN ITEMS FROM THE DRAFT SER On July 11 and 12, 1984 the NRC staff met with representatives from NMPC and Stone and t.'ebster Engineering Corporation (SHEC) to discuss open items in the draft SER.
A summary of each of the items discussed is included in Enclosure l.
Enclosure 2 contains a lis't of meeting attendees for all or part of the meetings.
,ning~~(
LB;"',2/DL/PM MHaughey/lb 9)I~j<4 LB82/DL/BC ASchwencer 9/( /84
Enclosures:
As stated cc:
See next page Mary F. Haughey, Project Manager Licensing Branch No.
2 Division of Licensing Distribution:
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LB82 Reading Bordenick, OELD ASchwencer MHaughey EHylton FWitt JRead JLee JLane FLiederbach
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.Enclosure 1
Ch i 1~El i
(F.
H.-79 Post-accident sampling
'person-motion study (exposure while taking samples)-to be submitted shortly (including update of table II.B.3)
'EPP-9 to be submitted in August, 1984
'NHPC should provide for grab samples of hydrogen, oxygen and fission gas products.
'NHPC should include range (cc/kg) for measuring radioisotopes
~ as well as hydrogen and oxygen.
Accident Evaluation (J.
Reed)
NMPC was requested to document the maximum. leakage from the Hain Steam Isolation Valves (MSIV)
.'Secondary containment drawdown time may be revised by NHPC
'NMPC to submit revised fuel handling calculations (August 20, 1984)
Effluent Treatment (J.
Lee)
TllK
" HH~gH-range noble gas monitor (II.F.I)
'The system at NMP-2 will compensate for various isotopic 'conditions ea4.7 I"99 101 8102 0'103 Leakage integrity from systems outside containment (III.D.l.1)
'NMPC will provide the leakage program 4 months prior to fuel load.
Committment to provide program at that time may allow this item to become confirmatory.
-NHPC to include quality group classification D in table 3.2. 1 of FSAR.
.r'"
Parameters used for. calculating liquid and gaseous source terms
-Sufficient information appears to be in FSAR already
-Both NHPC and GE ran separate source term programs.
NHPC used the higher (more conservative) number in each case from the two sets.
Assessment of the capability of liquid and gaseous radwaste systems for keeping the levels of radioactivity in efficients ALARA.
-This issue will be covered in the
- DES, NRC action.
Charcoal absorber tank failure
-NMPC to add reference to section 15.7 of the FSAR to ASME Section eleven
."104 8
105 Process control program for the solid radwaste system and compliance with 10 CFR 61
-NtLPC to provide a committment to this program
-A commitment to provide this program in an acceptable time frame may allow these items to become confirmatory.
Containment
~S stems (J.
Lane) 0 177 Automatic actuation of containment spray within ten minutes of a LOCA signal.
(same as 8187)
-NMPC does not have automatic spray
-NRC draft SER states credit cannot be taken for manual operation for 30 minutes
-Nl1PC/SMEC claimed other plants with manual operation do not incl<e feedwater in the analysis to allow them to go to 30 minutes.
-NRC to review the basis for 30 minutes and whether feedwater flow needs to be considered in the analysis.
P.178 8179 8180 8181 r',182 Results of containment spray drop efficiency determination
-NMPC to correct figure reference Thermal mixi'ng performance of RHR suction and discharge lines
-NMPC to submit response as discussed.
(480.18)
Ability of suction strainer to limit debris from blocking primary system flowpaths
-NRC to review response to 480. 14 Fiberglass insulation debris in downcomer vents and RHR intake
-Host fiborous insullation at NNP-2 is. encapsulized in stainless steel sheeting.
Secondary containment functional design (a) Neglect of heat loads in secondary containment drawdown loads
-NMPC to check heat loads on equipment that is tripped to see if these loads are in fact negligible.
(b)
-drawdown time needs
.to be verified simulating conditions at the time of a LOCA ( 1/4 gage water within 90 sec.)
(c) bypass leakage path barries
-NtlPC should provide a breakdown from Table 6.2-56 identifying which lines have water, air, or nitrogen seals.
In addition Nt<PC should provide a sample calculation for each type of seal demonstrating how the leakage criteria is determined.
r".183
-;.'184 P,185 8186 Containment isolation NMPC should provide the previously requested sketches of the closed loop systems.
Containment purge NMPC should provide a commitment to periodic leak testing of the containment isolation valves and debris screens on the containment vent and purge lines Combustible gas control
'Pnewmatically operated valves in containment all use nitrogen (FSAR 9.3.3)
'NMPC will include the oxygen generation rate in table 1.63 Containment leak testing
'NMPC will provide a commitment to meet 10 CFR50 Appendix J in the containment leak testing.
8187 same as 177 Procedures Review (F. Liederbach) 8133 Evaluation and development of procedures for transients (I.C.l)
,. 'NRC to review the June 29, 1984 letter from NMPC on PGP bl34 Upgraded. emergency operating procedures
'NMPC should provide commitments and procedures to assure this concern will be adequately covered.
Confirmatory issue 16 - I.C.7 and I.C.8
'Sufficient information has been provided in the FSAR.
/f70
-As of the date of the meeting insufficient information has been submitted on the PSI/ISI programs for these issues to be considered confirmatory
-Additional submittals are expected August 1984, April 1985 and November 1985.
Preservice-and inservice ~testin (N.
Hum, J.
Cook) vn ~
p b
d yi i
i p
i d<<ig and inservice inspection of Class 2 and 3 components
-NHPC to verify that there is no ODID cladding on the large bore (over 12 in.) piping in the recirculation lines.
-Ultrasonic procedures should be provided for the reactor vessel,
- piping, and bolting
-Isometrics should be provided.
-In response to question 250.2 the UT methodology should be provided.
Reactor
~S stems (K. Desai)
Method used to'determine minimum required ADS SRV's
-NHPC should submit analysis with the plant specific analysis to be submitted later.
NRC will consider making this a confirmatory issue based on a commitment from NMPC to submit analysis later.
F7168 fi169 8170 8171 k 172 Analysis justifying leak detection setpoints for isolation RCIC.
-NMPC should clarify response.
.,Interlocking of LPCI/LPCS injection valves and pressure setpoints
-GE has verified that the new design does not affect the accident analysis.
Pl ant-speci fic LOCA analysi s and.
Maximum hydrogen generation from cladding reaction
-These issues will.be considered confirmatory based on a commitment from NMPC to submit later.
Method of determining the limited transcent event and justification for violating the HCPR limit
-NMPC should provide additional information on methods used to identify this event
-NMPC to verify the plant-specific analysis will not change the evaluation of the worst-case transient.
-.";173 Operation with partial feedwater heating
-NHPC believes this should be.a technical specification item
tl74
-.'175 Reporting of SV and RV failures and challenges (II.K.3.3)
-Response submitted in Amendment II appears sufficient ADS actuation (II.K.18)
-Response is not yet available from NhlPC.
J
Enclosure 2
List of Attendees at July ll and 12, 1984 meetings NRC N. Haughey F. Mitt J.
Read J.
Lee J.
Lane F. Liederbach N.
Hum K. Desai INEL J.
Cook Nt1PC f'f. Rademacher R. Abbott SWEC N. Stocknoff
T
Nine Mile Point 2
Mr. B. G: Nooten Execu t', ve D iree tor',
Nucl ear Operati ons Ni agara Mohawk Power Corporation 300 Erie Boulevard Wes t
- Syracuse, New York 13202 CC:
Mr. Troy B. Conner, Jr.,
Esq.
Conner E 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, Hew York
'12223 Ezra I. Bialik Assistant Attorney General Environmental Protection=.Bureau Hew York State Department of Law
.2 World Trade Center New York; Hew York 10047 Resident Inspector Hine 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 Wes.t
- Syracuse, He'w York
.13202 Jay M. Gutierrez, 'Esq.
U.
S. Nuclear Regulatory Commission Reoion I
631 Park Avenue King of Prussa, Pennsylvania 19406 Norman Rademacher, Licensing Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202
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