ML19330A729
| ML19330A729 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/16/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Clayton F ALABAMA POWER CO. |
| References | |
| NUDOCS 8007290202 | |
| Download: ML19330A729 (9) | |
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WL I R 1980
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Docket File JBoegli NRC PDR CPatel
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Docket No. 50-364 DEisenhut NS!f b,..-
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RTedesco ASchwencer
= Mig Mr. F. L. Clayton, J r.
LKintner
";g Senior Vice President MService Alabama Power C'omany I&E (3)
Post Office Box 2641 JMcMillen Birmin:; ham, Alabama 35291
Dear Mr. Clayton:
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SUBJECT:
REQUEST FOR ADDITI0fiAL INFORMATIO:i FOR FARLEY 2 OPERATING LICE!iSE I:=E ~~
APPLICATION
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As a result of our continuing review of the operating license application for t" 1 =
the Jcseph M. Farley Nuclear Plant Unit 2, we have developed the enclosed l7.
request fcr additional information and position.
5 Please provide the information requested in the enclosure.
Our review schedule M
is based on the assumption that the additional information will be available
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f er our review by the dates indicated in the enclosure.
If you cannot meet h:{
these dates, please inform us within seven (7) days after receipt of this letter 50 that we may revise our scheduling.
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Sincerely, 5 -...
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Orig!n:I signed t:y
[ [.(,If Robert L. Tedesco, Assistant Director for Licensing Division of Licensing
Enclosure:
Request for Additional Infor.r.ation
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Mr. F. L. Clayton, Jr.
Senior Vice President Alabama Power Company Post Office Box 2641 Birmingham, Alabama 35291 cc: Mr. Alan R. Barton Executive Vice President I
Alabama Power Ccapany Post Office Box 2641 Birmingham, Alabama 35291 Mr. Ruble A. Thomas Vice President Southern Conpany Services, Inc.
Post Office Box 2625 Birmingham, Alabama 35202 4
Mr. George F. Trowbridge Shaw, Pittman, Potts and Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 Mr. W. Bradford NRC Resident Inspector Post Office Box 1814 Dothan, Alabama 36302 I-v-
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION JOSEPH M. FARLEY NUCLEAR PLANT UNIT 2 DOCKET N0. 50-364 Our review of your " Response to the TMI-2 Action Plan" submitted June 20, 1980 has resulted in the need for additional information.
Requests and pages are numbered sequentially.
The alpha numeric item designations correspond to the items in the TMI-2 Action Plan. The following requests are included in this enclosure.
RJ. quest No.
Date Requested 1(a),4,5 July 18,1980 1(b),2,3,6,7 August 1,1980 1.
Additional Accident Monitoring Instrumentation (Effluent)
Action Plan II.F.1 (a)
Before fuel loading, an interim method is required when the high range noble gas effluent monitors are not yet installed and operable.
You should describe the interim method, addressing item 2.1.Sb enclosed in our ietter dated November 9, 1979, Paces 31 to 36, prnviding all information required in 1.A.1.a and 1.A.1.b for noble gas effluents and 2.A.1 and 2.A.2 for particulate and radiciodine effluents.
Your response should contain a descriptive summary of the interim procedures and methods for quantifying high level accidental radioactivity releas's e
to meet the requirement in the Action Plan liUREG-0660, Appendix A, Table A.1, Item (17) for II.F.1(a)..
(b)
.By January 1, 1981, complete the installation of the high range noble gas monitors II.F.1(f) and provide all the information required in Item 2.1.8b, Sections 1.B and 2.B given in our fiovember 9, 1979 letter.
Your response should contain calculationab methods for converting in-strument readings to release rates based on exhaust air flow and radio-nuclide spectrum distribution, correction for background radiation, and procedures for dissemination of information.
Clarify your intent to meet the January 1,1981 requirements for the atmospheric steam relief /
safety valves and main condenser air ejector release monitoring.
See flVREG-0694 "TMI Related Requirements for New Operating Licenses",
June 1980.
1.
i
'2.
Primary Coolant Sources Outside Containment Action Plan III.D.1.1 Before full power operation, provide the frequency of leak inspection and the criteria that will be used for determining acceptable leakage limits for each system (or subsystem) to which yuu refer in Items C and D on Page 88 and 89 of your response.
3.
Post Accident Sampling Action Plan II.B.3 Before full power operation prior to January 1, 1981, provide a descriptive summary of the interim procedures for obtaining, handling and analyzing the reactor coolant a'nd the containment atmosphere.
By January 1, 1981, provide a description and final system design of the new post accident sampling panel, and modifications to the sampie handling and counting f acilities to achieve analysis within the time specifieo in item 2.1.Sa given in the November 9, 1979 letter. See NUREG-0694 "THI Related kequirments for New Operating Licenses", June 1980.
4 Your " Response to TMI-2 Action Plan" does not explicitly respond to Part 4,
" Dated Requirements" of NUREG-G 0694 "TMI-Related Requirements for New Operating Licenses" and'does not respond at all to Item I.A.2.1, "Immediate Upgrading of Operator and Senior Operator Training and Qualification," Item I.A.2.3 " Admin-istration of Training Programs for Licensed Operators," and Item I.A.3.1.
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" Revised Scope and Criteria for' Licensing Exams."
i e
Provide an explicit response to Part 4 of NUREG-0694, giving a description i
of the program, status of the progran, and statement of intent to neet the I
required completion date for the program.
References to other portions of.
your response will be acceptable.
5.
In order to conclude that you meet the requirements for Item II.D.1, " Relief-and Safety Valve Test Requirements," we need the fcllowing commitments.
(1) The applicant has stated that they will participate in the EPRI/NSAC i
program and has referenced the proposed EPRI program (" Program Plan for the Performance Verification of PWR Safety / Relief Valves and f
Systems," dated December 13,1979) for the performance testing of PWR relief and safety valves.
(2) The applicant has committed to monitor the EPRI program to provide assurance that:
(a) it will be applicable to his specific plant's design and (b) it will provide sufficient information to qualify the specific I
plant's reactor coolant system relief and safety valves and
-associated piping and supports under expected operating conditions for design basis transients and accidents.
(3) The _ applicant has committed to submit' to NRC by July 1,1981 the following information with respect to his ' plant:
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(a) Evidence supported by test of safety and relief valve function-ability for expected operating and accident (non-ATWS) conditions.
The testing should demonstrate that the valves will open and reclose under the expected flow conditions.
(b) Since it is not planned to test all valves on all plants, each application must submit a correlation, or other evidence, to substantiate that the valves tested in the EPRI program demonstrate functionability of as installed primary relief and' safety valves.
This correlation must show that the test conditions used are equivalent to expected operating and accident conditions as prescribed in the FSAR.
The effect of as built relief and safety valve discharge piping on valve operability must also be accounted for, if it is different than the generic test loop piping.
(c) Test data including criteria for success and failure of valves tested must be provided for review and evaluation. This test data should include data which would permit plant specific evaluation of discharge piping and supports which are not tested directly.
(4) The applicants has committed to submit by January 1,1982 evidence supported by test to qualify the specific plants block valves under expected operating conditions for desian basis transients and accidents.
Your June 20, 1980 " Response to TMI-2 Action Plan" provides a satisfactory commitment to " Item (1) above.
Provide your commitment to Items (2), (3) and (4) above."
6.
Your response to Item II.F.1 " Additional Accident Monitoring Instrumentation" provides a description of high-range radiation monitors for containment atmosphere but does not give their location.
Provide the location of the monitors on plant layout drawings. Tt.e monitors should be located in a manner so as to provide a reasonable assessment of area radiation conditions inside containment. Monitors should not be placed in areas which are protected by massive shielding.
7.
Your response to Item II.B.2, " Plant Shielding" describes the source terms used in evaluating shielding but does not adequately -
'ess all the requirements.
Provide a summary of the shielding design review required by our letter dated November 9,1979, implementing the Lessons Learned Item 2.1.6.b of NUREG-0578, and provide a description of the results of this review.
Include in your description:
a.
source terms us j in the evaluation (NUREG-0578 specified that source terms in Regulatory Guide 1.3,1.4 and 1.7 be used).
b.
systeir.s assumed to contain high levefs of radioactivity in a post-accident situation including, but not limited to, residual heat removal, safety injection, CVCS, demineralizers, charging systems, reactor coolant filter, seal water filters sample lines, liquid radwaste systems, gaseous radwaste systems, ano standby gas treatment systems.
If any of these systems or others that could contain high radioactivity were excluded, explain why such
I i
_6 systems were excluded.
You should verify that field run piping and indirect radiation (such as snine over shield walls) were included in the analysis.
c.- specify areas where access was considered necessary for vital system operation after an accident. Your evaluation of areas to determine the necessary vital areas should include but not be limited to, consideration of the control room, Technical Support Center, Operational Support Center, recombiner hookup and control l'
l stations, hydrogen purge control stations, containment isolation l
reset control area, sampling and samply analysis areas, manual ECCS alignment area, motor control centers, instrument panels, emergency power supplies, security center and radwaste control panels.
If any of these areas were not considered areas where access was necessary after an accident, explain why such areas were excluded.
d.-
designation of the codes used for analysis, such as ORIGEN, IS0 SHIELD, QUAD or others.
e.
the projected doses to individuals for necessary occupancy time in vital areas.
f.
a brief description of the proposed plant modifications resulting from the des.ign review and confirmation that these modifications l
l will. be. complete by January 1,1981.
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