ML19345E628
| ML19345E628 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/22/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| References | |
| NUDOCS 8102050326 | |
| Download: ML19345E628 (12) | |
Text
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/pa '"%g'4 UNITED STATES
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'i NUCLEAR REGULATORY COMMISSION t
WASHINGTON. D. C. 20555 k
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11N 2 2 1981 U
Docket Nos. 50-440 and 50-441
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M Mr. Dalwyn R. Davidson, Vice Presiden+
[.5 The Cleveland Electric Illuminattag Company
~S 55 Public Square P. O. Box 5000 a
E 3
Cleveland, Ohio 44101
Dear Mr. Davidson:
SUBJECT:
ACCEPTANCE REVIEW FOR THE PERRY NUCLEAR POWER LANT, UNITS 1 AND 2 On h r.c 20, 1980, you tendered an application for operating licenses for the Perry Nuclear Power Plant, Units 1 and 2.
Your application included the General Information Section and an Environmental Report - Operating License Stage (ER). Your Final Safety Analysis Report (FSAR) was received on September 12, 1980. Your Physical Security Plan and other proprietary infor-mation is scheduled to be supplied in January,1981.
We have conpleted our review of the General Information Section and the Final Safety Analysis Report of your tendered application and have concluded that they are sufficiently cocplete to permit us to initiate our safety revi ew. The acceptance review of your Environmental Report - Operating License Stage is scheduled to be completed in April,1981.
Accordingly, your filing of the application should include three (3) originals signed under oath or affirmation by a duly authorized officer of your organi-zation.
In addition, your filing should include fifteen (15) copies of the General Information Section and forty (40) copies of the Final Safety Analysis As required by Section 50.30 of 10 CFR Part 50, you should retain an Report.
additional ten (10) copies of the General Information Section and thirty (30) copies of the Final Safety Analysis Report for direct-distribution in accordance with Enclosure 1 to this letter and further instructions which might be provided later.
Within 10 days after filing, you mst provide an affidavit that distri-bution has been made in accordance with this enclosure. All subsequent amendments to the Final Safety Analysis Report will require sixty -(60) copies for distribu-tion.
Our conclusion that the FSAR is sufficiently complete is based on our evaluation of all the information filed taken as a whole, with the realization that sub-stantive deficiencies may exist that need to be corrected during the review.
810 2 05 0 3W w
Mr. Dalwyn R. Davidson The Perry FSAR addresses the requirements set forth in NUREG-0694 entitled "TMI Related Requirements for New Operating Licenses." On October 28,1980, the Commission approved a " Clarification of TMI Action Plan Requirements," new contained in NUREG-0737, which supersedes F AEG-0694. Enclosed for your information and use is a copy of NUREG-0737 (Enclosure 2). The Perry FSAR should be amended to satisify the modified and added requirements contained in NUREG-0737.
On October 9,1980, the Comission published a notice of proposed rulemaking entitled " Plan to Require Licensees and Applicants to Document Deviations From the Standard Review Plan." 45 Federal Register 67099. As proposed, Cleveland Electric Illuminating would be required to identify and justify, prior to the issuance of the Perry 1 and 2 operating licenses, all deviations in the FSAR from all acceptance criteria contained in the forthcoming revision of the Standard Review Plan. We will keep you informed as to the status and content of these requirements.
You will be advised of key milestones of the review as soon as a schedule is developed. During the course of our preliminary review of your FSAR, the enclosed " Request for Additional Information" (Enclosure 3) was generated.
These sections should be co@leted as soon as possible for our mutual benefit during the ensuing detailed technical-review period. We will prepare the schedule based on the assumption that the outstanding items in each of the inco@lete sections are received within six weeks from the docketing date.
If this milestone cannot be met, it may be necessary for us to revise our review schedule.
If during the course of our review, you should believe there is a need to appeal a staff position because of disagreement, this need should be brought to the staff's attention as early as possible so that the appropriate meeting can be l
arranged on a timely basis. A written request is not necessary and all such l
requests should be initiated through our staff project manager assigned to the l
review of your application, Dean Houston. This procedure is an informal one, designed to allow opportunity for. applicants to discuss with management, areas I
of disagreement in the case review.
Sincerely, hfis n ut, Dire'ctor arre 4
Division of Licensing Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosures:
See next page
e O
JAN 0 J 331 Mr. Dalwyn R. Davidson Vice President, Engineering The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101 cc: Gerald Charnoff, Esq.
Shaw, Pittman, Potts & Trowbridge 1800 M Street, N. U.
Washington, D. C.
20036 Donald H. Hauser, Esq.
Cleveland Electric Illuminating Company P. 0. Box 5000 Cleveland, Ohio 44101 U. S. Nuclear Regulatory Commission Resident Inspector's Office Parmly at Center Road Perry, Ohio 44081 4
6 ENCLOSURE I FEDERAL, SIATE AND LOCAL OFFICIALS FOR PERRY APPLICATION, SAR AND AETDMENTS THERETO
- Federal, Federal Activities Branch U.S. Environmental Protection Agency Region V Office 230 South Dearborn Street Chicago, Illinois 60604 State Official Ohio Department of Health Attn: Radiological Health Program Director P.O. Box 118 Columbus, Ohio 43216 Local Officials Honorable Laurenre Logan, Mayor Village of Perry 4203 Harper Street Perry, Ohio 44081 Honorable Robert V. Orosr, Mayor Village of North Perry North Perry Village Hall 4778 Lockwood Road North Perry Village, Ohio 44081 Mr. H. R. Adama, Chairman Perry Township Board of Trustees 4169 Main Street Perry, Ohio 44081 i
National Laboratnev 1
Mr. R. Zussman i
Division of Environmental Impact Studies Argonne National Laboratory 9700 South Cass Avenue Argonne, Illinois 60439 Mr. Maylin Dittmore, L-97 (3AR and Amendments Thereto) l Lawrence Livermore National Laboratory
.P.O. Box 808 Livermore, California 94550 Mr. Merv Bampton
- ( Two sets of SAR and Amendments -
Pacific Northwest Laboratory Thereto)
P.O. Box 999 Richland, Washington 99352
6 Perry 1 and 2 Request for Additional Infor=ation 100.01 In Table 1.3-3, Item 7 specify or cualify tne missing values (1.3.1.3) of tne flow rates.
450.01 Per Regulatory Guide 1.70, verify tnat tne plant property lines (2.1.1) and tne site boundary lines are identical. If not laoel tne-7 property lines in tne FSAR figures (e.g., Figure 2.1-2).
450.02 Per Regulatory guide 1.70, address tne bases upon wnicn it nas (2.1.2.1) been determined tnat tne autnority required by paragrapn 100.3(a) of 10 CFR Part 100 to control all activities in tne exclusion area extends into tne Laxe Erie portion of tne exclusion area.
450.03 Per Regulatory Guide 1.70, orovide an estimate of tne time (2.1.2.2) required to evacuate persons from the exclusion area that are.
related to activities not associated with PNPP Unit 1.
In particular consider tne Laxe Erie portion of tne exclusion area and tne PNPP Unit 2 construction area.
450.0'.
Per Regulatory Guide 1.70, provide a taole of population (2.1.3.4) distrioution witnin tne low population zone whicn includes estimates of peak daily, as well as seasonal transient, population.witnin tne zone.
240.01 Per Regulatory Guide 1.70, discuss tne extent'to wnicn tne (2.4.3) guidance given in Apoendix A of Regulatory Guide-l.59 nas.been followed; if not followed, describe the specific alternate approaches used..
230.01 Per Regulatory Guide 1.70 discuss tne probability of exceeding (2.5.2.7).
'tne OBE during tne operatino life of the plant.
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231.01 Per Regulatory Guide 1.70, discuss tne need and proposed (2.5.4.5) measures for foundation protection and treatment after exc0vation. Include a discussion of auality control and quality assurance programs related to foundation excavation, and subseouent protection and treatment. Discuss tne measures to be used to mor,1 tor foundation rebound and heave.
231.0?
Per Regulatory Guide 1.70, di:cass tne ground water monitoring (2.5.4.6) program during the life of tne plant to assess the potential for subsidence.
410.01 Per Regulatory Guide 1.70, discuss missiles due to (3.5 1.2) gravitational effects and secondary missiles.
450.05 In Table 2.2-3, pipelines designated as numbers 5 and 7 (2.2.2.3) are listed as 20 inches in size. In Figure 2.2-3, a boxed caption for pipeline No. 7' states." construction zone for 16" gas line." The caption in Figure 2.2-3 appears to be inconsistent with the size of the relocated pipe. Provide the correct pipe size in Figure 2.2-3.
440.01 Section 3.5.1.6, Aircraf t Hazards, states "Tne prooability. tnat (3.5.1.6) an aircraft failure in tne vicinity of the site would result-in a plant failure is extremely: low. Based upon.tnis extremely low probaoilit:,, the Perry design does not consider aircraft impact". Provide justification for tnis statement in terms of information'recuested in Section 3 5.1.6 of Regulatory Guide 1..
Revision 3 and tne acceptance criteria
_given in tne Standard Review Plan for.Section 3.5.1.5.
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410.02 Per Regulatory Guide 1.70 demonstrate tnat the safety related (3.5.2) structures, systems and components listed in Tables 3.5-5, 3.5-6 and 3.5-7 are adequately protected against missile strikes.
210.01 ine review of Section 3.6.2.5 cannot be completed until af ter (3.5.2.5) tne analytical results are available. Provide tnese results or a senedule for suomittal of the results.
220.01 As per Regulatory Guide 1.70, discuss tne criteria and cases (3.7.2.3) used to determine wnetner a component or structure snould be analyzed as part of a system analysis or independently as a subsystem.
220.02 As per Regulatory Guide 1.70, provide a sunnary of tne results-l (3.7.3.14) of the dynamic seismic analysis.
220.03 As per Regulatory Guide 1.70, discuss tne extent to wnicn you (3 8.3, comply witn ACI-349. Proposed ACI Standard: Code Reauirements 3,8.4, and for Nuclear Safety Related Concrete Structures.
3.8.5) 220.04 As per. Regulatory Guide l.70, provide tne general.arrangementf (3.8.5.1) ofstne snear keys.
210.02 Tne review of tnis section cannot be completed uniti after tne (3.9) information to be supplied later in Table 3.9-3 is availaole.
Eitner supply this information or provide a senedule.for submittal of the information.
210.03 Expand Table 3.9-2 to include the type of information contained (3.9.1.1) in' Table 3.'9-1.
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210.04 The title of Section 3.9.2.1.1.3 is onsistent with the text with the exception that RCIC piping is *ot discussed. Provide (3,9.2.1.1.3) clarification including a discussien of ts; ting of RCIC piping.
210.05 Section 3.9.2.2 snould orovide.the results of tests and
( 3.9.2.2 )
analyses to ensure tne proper implementation of tne criteria accepted in tne construction permit review and to demonstrate adeauate seismic aualification. Review of this section cannot be completed until all of the results of these tests and analyses are supplied. Eitner supply tnis information or provide a schedule for submittal of the information. Also, Subsection 3.9.2.2.2.13 snould be corrected since it references nonexisting Section 3.9.3.2.6 for test and analysis results.
210.06 Review of tnis section cannot be completed until after test (3.9.3.2) program information pertinent to assurance of operaoility nas oeen provided. Eitner provide program results or a scnedule for submittal of this information.
210.07 Review of this section cannot be completed until after the (3.10) information identified as "later"-in Tables 3.10-1 and 3.10-2 is submitted. Eitner provide tnis information or a scnedule for submittal of tnis information.
210.08 As per Regulatory Guide 1.70, provide the metnods and (3.10.21 procedures used to ensure structural and functional integrity of tne eauipment after several occurrences of the operating casis eartnauake.
420.01,270.01 430.01 Review of-tnis section cannot be completed until after.tne (3.11) information' identified as "later" in Tacles 3.11-9, 3.11-10, 3.11-11 and 3.11-12 is suomitted. Either provide tnis ~
information or a senedule for submittal of tnis information.
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I 420.02,270.02 t30.02 As per Regulatory Guide 1.70, botn tne normgl and accicent (3.11.1) conditions, including nonseismic vioration, snould ce explicitly defined for eacn item of ecuipment. Inis information is not presented for nonseismic vibrations.
Eitner present tnis information or provide justification for not including it in Section 3.11.1.
220.05 Appendix 3A states " Based on tr.e large acceleratien of tne (App. 3A) steel containment vessel due to SRV loads, a fix is Deing designed in order to cualify containment-mounted equipment".
Since tne fix is being designed and some sections of tne FSAR need to De updated to account for tne fix, identify FSAR content to be upcated, provide a senedule for tne update, and discuss tne significance of tne fix sucn as tne effect on analytical results currently in the FSAR, the utilization of codes and standards, loads and load combinations, cualification of ecuipment, etc.
440.02 Per the requirements of Regulatory Guide 1.70, provide or (5.2.5.1) refer tnce a discussion of RCIC design witn respect to General Desigt Criteria 34, 55, 56, and 57.
480.01 Per tne reouirements of Regulatory Guide 1.70. provide or (6.2.1.3) reference a discussion of core reflood model, description of.
long term cooling model and a single failure analysis.
i 1
430.03 Indicate or reference performance requirements 'under normal, i
l (10.2.1) upset, emergency.and faulted conditions.
t 430.04-Identify tne design codes wnicn are'to be applied.
(10.2.1) i l
251.01
- Specify or reference tne material chemical analysis of tne
~(10.2.3.1) disc and rotor forgings.
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251.02 List or reference tne mecnanical properties of tne disc (10.2.3.1) material.
251.03 Specify tne values for the FATT and minimum operating (10.2.3.2) temperatures.
251.04 Provide or reference values for the stress-rupture properties (10.2.3.3) of the hign oressure rotor material and describe the method of obtaining tnese properties.
251.05 Provide a summary discussion or reference the anticipated (10.2.4) operating concentration of radioactive contaminants in the system and tne attendant radiation levels associated witn the turbine components.
2 430.05 Indicate the length of time tne condenser may operate witn (10.4.1) degraded conditions witnout affecting condensate /feedwater-quality for safe operation.
410.03 Discuss and provide a subsection on system safety evaluation, (10.4.6) tests and inspections, and instrumentation applications.
410.04 Indicate inservice inspection requirements.
( 10.4. 7.2.2 )
460.01 Tabulate the maximum and expected dry, solid waste inputs in (11.4.2.2.2) terms of type, source, volume, and isotopic and curie content.
460.02 Indicate or clarify provisions for emergency power supplies for (11.5.2) each monitor.
460.03 For those locations subject to routine sampling, provide (11.5.2).
expected flow, composition and concentration (possibly in Taoles 11.5-4 tnrougn 11.5.8)..
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470.01 Indicate whether tne apolicaole guidelines of ANSI N ?37 nave
( 12.2.1 )
Deen followed.
471.01 Indicate wnetner tne guidance of Regulatory Guide 1.69 nas (12.3.?)
been followed.
471.02 Indicate wnether the guidance provided by Regulatory Guide 1.97 (12.3.4) nas been followed.
i 471.03 State tne specific condition or reason, based on tne referenced (12.3.4.1.1) analysis of Section 9.1.2, wny a criticality alarm system is not provided for tne storage area for new fuel.
471.04 Indicate now the requirements of 10 CFR Part 19 will be met.
(12.5.3) 471.03 Indicate whetner tne requirements of Regulatory Guides 8.2, (12.5.3),
8.7, 8.8, 8.9, 3.10, 8.13, 1.8, 1.16, 1.33 and 1.39 will De followed.
260.01 Provide a senedule for comoleting all cognizant activities (13.1.1.1) described in this section.
P 260.02 Summarize (indicate) tne degree to wnicn activities have oeen (13.1.1.1.1.1) accomplisned.
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260.03 Provide resumes or indicate proper reference pertaining to_tne (13.1.3.2) aualifications of tne initici appointees to plant positions.
Tne cited reference (Appendix 13A) does not appear to contain resumes.
610.01 In tnose appropriate sections that provide a syllabis of (13.2) training courses, indicate tnose areas wnere plant management training is intended (see Table 13.2-1).
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810.01 In ADpendix 13A, provide plots snowing ground-level doses for
( 13.3) stationary individuals, for botn wnole oody and tnyroid, resulting from tne most serious DBA. For specific requirements refer to Regulatory Guide 1.70, Revision 3.
810.02 Indicate tne revision number of Regulatory Guide 1.101 (13.3) used.
640.01 Specifically address the plans pertaining to approval of test (14.2.5) data at eacn power test plateau, during power ascension testing, before increasi,g power levra.
640.02 Provide the schedule, relative to the fuel loading date. for (14.2.11) conducting eacn major phase of the test program.
640.03 Provide the secuential test scnedule for testing individual (14.2.11) plant structures, systems and components.
640.04 Identify eacn test required to be completed before initial fuel-(14.2.11) loading.
450.06 Provide the secuence of events.
(15.7.1.3.2.1) i i
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1.