ML20133C382

Forwards Questions Resulting from Review of Westinghouse Advanced PWR,RESAR-SP/90,Module 11

ML20133C382
Person / Time
Site:	05000601
Issue date:	10/02/1985
From:	Thomas C Office of Nuclear Reactor Regulation
To:	Rahe E WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 8510070337
Download: ML20133C382 (7)

Text

October 20 1985 Docket No. STN 50-601 Pr. E. P. Pahe, Jr. , Manager fluclear Safety Department Westinghouse Electric Corporation Water Reactor Division, Fox 355 Pittsburgh, Pennsylvania 15230

SUBJECT:

WESTINGHOUSE ADVANCED PRESSURIZED PATER REACTOR (WAPWR),

RESAR-SP/90, REVIEW OF MODULE 11 We are continuing our review of the RESAR-SP/90 PDA Fodule 11 and have identified the need for additional information.

You are requested to provide your response to the questions identified in the enclosure within 30 days of the date of this letter. If additional information is needed, we will notify ycu promptly.

Sincerely, "The re:: r a; and/cr rce arening reqeiremena t=md in m mue' Orioinal signed by st:ectiewei a:a aa respan ents: Cecil 0. Thomas, Chief therefore, Of.13 cicerance is not Standardization and Special rmired under P. L 95-511." Pro.iects Branch Division of Licensing

Enclosure:

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'.....,o8 October 2, 1985 Docket No. STN 50-601 Mr. E. P. Rahe, Jr., Manager Nuclear Safety Department Westinghouse Electric Corporation Peter Peactor Division, Box 355 Pittsburgh, Pennsylvania 15230

SUBJECT:

WESTINGHOUSE ADVANCED PRESSURIZED WATER REACTOR (WAPWR),

I RESAR-SP/90, REVIEW OF MODULE 11 We are continuing our review of the RESAP-SP/90 PDA Module 11 and have identified the need for additional information.

You are requested to provide your response to the questions identified in the enclosure within 30 days of the date of this letter. If additional information is needed, we will notify you promptly.

I Sincerely, t I? . .. s. lr = = 2B 0, .} Q : = :

a:;ect it.'.si 2. a .c.. sespnnents:

therehre. Cf.13 cle:rance is not Cecil 0. Thomas, Chief required under P. L. SS 511." Standardization and Special Projects Branch Division of Licensing

Enclosure:

As stated

s, Et! CLOSURE i OVESTI0t!S RESULTING FROM REVIEW OF RESAR-SP/90, MODULE 11 i 471.1 In Podule 11. subsection 12.2.1.1, Sources for Full Power Operation, ,

second paragraph, item 4, the sentence: " Detailed angular distribution of radiation leakage (neutron and gama ray) from the reactor pressure for streaming analysis" is not clear. Please i

j clarify this statenent.

! 471.2 The subsection 12.2.1.1 Sources for Full Power Operation, the third paragraph refers to Table 12.2-1, which is not included in Module

! 11. Provide Table 12.2.-l.

l 471.3 The acceptance criteria in Standard Review Plan Section 12.2 " Radiation

! Sources," (NUREG-0800), require that (for PWR's designed for recycling of tritiated water) the tritium concentrations in the contained sources 1

! and airborne concentrations in the contained sources and airborne l concentrations in the regions specified in Item I.2 (of SRP 12.2) i

! should be based on primary coolant concentration of 3.5AAC1/gm. State j whether or not RESAR-SP/90 is in ccrpliance with this requirement.

i 471.4 State in subsection 12.2.1.3, Scurces for Design Basis Accident, whether or not the shielding desian for vital areas is based on radiation sources specified in NUREG-0737,Section II.B.2, and comit that the design dose rates for personnel in vital areas requiring l continuous or infrequent access, will be such that the guidelines of i

l GDC-19 will not be exceeded during the course of the accident.

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i 471.5 The last sentence in the second paragraph of subsection 12.2.1.3, Sources for Design Basis Accident, states that the integrated camma ray and beta particle source strengh for various time periods a

following the postulated accident are given in Table 12.2-19.

i Secify the location of the radiatien source.

471.6 State in subsection 12.3.1.1.1.2, Auxiliary Equipment, in Item D, whether or not purps containing high level radiation l sources are equipped with drain connections.

I

471.7 NUREG-0737,Section II.B.2, Shielding, specifies that areas requiring continuous occupancy should have less than 15 mrem /hr (averageover30 days). The control room and onsite technical i support center are areas where continuous occupany will be t

required.

1 Module 11, Subsection 12.3.1.2, Radiation Zoning and Access Control, 1

describes such areas. However, the onsite technical support center

, is not included.

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d Include the onsite technical support center in the areas requiring post accident continuous occupancy.

471.8 Module 11, subsection 12.3.4.1, Area Radiation Monitoring, second paragraph states that the design of the fuel pool racks precludes criticality under all pcstulated nornal and accident conditions.

Therefore, criticality monitors, as stated in 10 CFR 70.24 and Regulatory guide 8.12 are not needed.

i e You are reouired to request an exception to 10 CFR 70.24 on your fuel storage license from the Office of Nuclear Material Safety and Safeguards; state in this subsection whether the exception has been granted.

471.9 State whether or not the Containnent High Range Monitors A-11A and A-11B described in Section 17.3.4.1.8(H) are in corrpliance j with NUREG-0737, Item II.F.1.3, Containtnent High Range Radiation i

l Monitors.

471.10 In subsection 12.3.4.1.9, Range and Alarm Setpoints, in the third paragraph the statement regarding the " visual indication" of the area monitor reading in the control room is not clear.

I State whether or not area monitors are equipped with strip chart recorders located in the control room.

471.11 Subsection 12.4.1.1, Direct Radiation Dose Estimates, fourth i paragraph states that in 1982 the highest and lowest collective dose

• was about 1600 and 100 respectively. Indicate the units for the collective dose levels.

I 471.12 You should take a position regarding the conforrrance to applicable NRC Regulatory Guides as specified in NUREG-0800 Stnadard Review I Plan, in acceptance criteria of Section 12.1, 12.2, 12.3, 12.4 and i

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t 17.5. Each Pegclatory Guide should be addressed separately. The applicant shoule , tate whether he complies with the Regulatory Guide in full or in part. The, exceptions, if taken, should also be specified and alternative methods for complying with the Commission's regulations should be described.

471.13 Please provide following information reoufred by TMI Action Plan Iten II.B.2 on pape II.P.2-5 of NUREG-0737, " Clarification of TMI Action Plan Requirements":

1 (1) Specification of source tenns used in the evaluation; including I time after shutdown that was assumed for source terms in systems; i

(2) Specification of systems assumed in your analysis to contain high levels of radioactivity in a postaccident situation. If any of the systems listed in " Clarification," item 2, were excluded, explain why such systems are excluded from review; 4

i l" (3) Specification of areas where access is considere/ necessary for vital system operation after an accident (partielly answered, j refer to Question 471.7). If any of the areas listed in the

! " Clarification" section of II.B.2 were not considered to be areas requiring access after an accident, explain why they I

were excluded; (4) The projected doses to individuals for necessary occupancy times in vital areas and a dose rate map for potentially occupied areas, i

471.14 The compliance with NUREG-0737,Section III.D.3.3, Improved Inplant Iodine Instrumentation under Accident Cendition, requires that a low background counting laboratory is available. Please address this item.

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