ML17054A697

Summary of 840413 Meeting W/Util & S&W in Bethesda,Md Re Draft SER Open Items

ML17054A697
Person / Time
Site:	Nine Mile Point
Issue date:	05/03/1984
From:	Haughey M Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8405180030
Download: ML17054A697 (20)

Text

~4 Docket Ho. 50-410 FACILITY:

Nine Mile Point Nuclear Station, Unit 2

SUMMARY

OF RADIOLOGICAL ASSESSMENT BRANCH (RAB)

DRAFT SAFETY EVALUATION REPORT (DSER)

OPEN ITEM MEETING Distribution:

Docket Control LB82 Reading NRC PDR PRC System NSIC APPLICANT:

Niagara flohawk Power Corporation (NMPC)

OELD, Attorney ACRS (16)

E, Jordan N, Grace Region I On Friday, April 13, 1984, a meeting was held in the Bethesda, Maryland offices of the HRC to discuss RAB open items identified in the Nine Mile 2 DSER (Chapter 12).

Representatives from NMPC, Stone ff lfebster and the HRC were in

'ttendance (see Enclosur e 1).

At the meeting, the staff provided the attendees with a listing of the open items resulting from the RAB review.

A copy of this list is provided as Enclosure 2;

The three digit number in the margin refers to the open item number as listed in Chapter 1 of the DSER.

The 471 series number denotes the staff's Request for Additional Information reference.

The open items were discussed sequentially according to the list.

Pending further review of those items and based on this meeting and the docketed application, the status of each open item is as follows:

0 en Item No.

107 108 109 110ill 112 113 114 115 8405180030 840503 PDR ADQCK 05000410 PDR Status Resolved Resolved Remains open NMPC should include in FSAR a statement committing to Reg.

Guide 8.8 (ALARA).

Resolved Remains=open-Additional information to be provided by June 1984.

Remains open Additional information to be provided by June 30, 1984.

Resolved Resolved Confirmatory Awaiting revision of Section 12.3.1 OFFICE/

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IVl Dotfd't No. 50-410 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 Me 3 584 APPLICANT:

Niagara Mohawk Power Corporation (NMPC)

FACILITY:

Nine Mile Point Nuclear Station, Unit 2

SUMMARY

OF RADIOLOGICAL ASSESSMENT BRANCH (RAB)

DRAFT SAFETY EVALUATION REPORT (DSER)

OPEN ITEM MEETING On Friday, April 13, 1984, a meeting was held in the Bethesda, Maryland offices of the NRC to discuss RAB open items identified in the Nine Mile 2 DSER (Chapter 12).

Representatives from NMPC, Stone

& Webster and the NRC were in attendance (see Enclosure 1).

At the meeting, the staff provided the attendees with a listing of the open items resulting from the RAH review.

A copy of this list is provided as Enclosure 2.

The three digit number in the margin refers to the open item number as listed in Chapter 1 of the DSER.

The 471 series number denotes the staff's Request for Additional Information reference.

The open items were discussed sequentially according to the list.

Pending further review of these items and based on this meeting and the docketed application, the status of each open item is as follows:

0 en Item.No.

107 108 109 110ill 112 113 114 115 Status Resolved Resolved Remains open NMPC should include in FSAR a statement committing to Reg.

Guide 8.8 (ALARA)

Resolved Remains, open Additional information to be provided by June 1984.

Remains open-Additional information to be provided by June 30, 1984

'esolved Resol ved Confirmatory Awaiting revision of Section 12.3.1

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0 en Item No.

Status 116 117 118 119 120 121 Remains open--

Additional information to be provided by June 30, 1984.

Resolved Remains open--

Additional information to be provided by'une 30, =1984.

Remains open Additional information to be provided by June 30, 1984.

Remains open--

Additional information to be provided by September 30, 1984.

Applicant advised that due to late submitted date, item may be carried as open in the SER.

s I Confirmatory-NMPC indicated information has been provided in FSAR awaiting verification by NRC reviewer.

122 123 124 125 Resol ved ConfirmatoryPending review.

Following the discussion with RAB, Mr. John Lane of the Containment Systems Branch (CSB) discussed an item in Standard Review Plan Section 6.2.3 with NMPC.

Thb applicant sought staff guidance on the flexibilitythat has been used in MSIV leakage Technical Specifications.

Two methods of providing this flexibilitywere described to the staff:

1.

Slug flow method.

2.

Pressure decay method.

The staff agreed to verify the use of these techniques at other facilities and their possible application to Nine Mile-2.

Mary F. Haughey, Project Manager Licensing Branch No.

2 Division of Licensing

s';

Nine Mile Point 2-Mr. Gerald K. Rhode Senior Vice Presi dent Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202 CC Mr. Troy B. Conner, Jr.,

Esq.

Conner

& Wetterhahn Suite 1050 1747 Pennsylvania.Avenue, N.W.

Washington, O. C.

20006 Mr. Richard Goldsmith Syracuse Uni versi ty College of Law E. I. White Hall Campus

Syracuse, New York 13210 Mr. Jay Ounkleberger, Director Technological Oevel opment Progr ams New York State Energy Office Agency Building 2 Empire State Plaza

Albany, New Yorg 12223 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Oepartment 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 Coomission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

MEETING TITLE:

RADIOLOGICAL ASSESSMENT OPEN ITEMS Enclosure 1

APPLICANT:

FACILITY:

DATE:

Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station, Unit 2 Friday, April 13, 1984 Dave Wagner Charles Ader Richard Pinney Norm Rademacher Michael S. Stachnoff Brian Gutherman Frank C. Skopec 0.

D. T. Lynch, Jr.

Richard J.

Serbu AFFILIATION Project Mgr./DL/LB-2 Stone 8 Webster Stone 8 Webster NHPC Stone

& Webster Stone 5 Webster NRC/RAB NRC/RAB NRC/RAB

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Enclosure 2

NMP-2 LIST OF OPEN ITEMrS - NINE MILE POINT 2

Q3l.l i@i (1)

In response to staff's question F471.1 requesting justification for appli-cant's statement in Subsection 12.2.2.2.8 of the. FSAR stating that:

"Expected airborne radioactivity levels in normally occupied areas. are at or below ambient outside air concentration",

the applicant-indicated (in Amendment

5) that the response to the question will be provided by

.he fourth quarter of 1984.

(2)

In response to staff's question F471.3 requesting airborne radionuclide glt3 lbS (3)

Lo9 concentration in liquid radwaste handling area doe to pump leakaae, the.

applicant indicated (in Amendment

5) thai the.insormation will be provided by the first quarter of 1984.

0 In response to staff's question F471.4 requesting revision of Table 1.8-2,'o ensure a broad acceptance of Regulatory Guide 8.8, the applicant indi-cated (in Amendment

5) that the Table 1.8-2 was revised.

The applicant should state in which Amendment the table was submitted or the applicant should provide. the Table 1.8-2.

Q ff,g (to (4),In response to staff's question F471.9, requesting revision o

FSAR Sub-section 12.3.4.3, to comply with NUREG-0737, section I1.8.2, the applicant indicated (in Amendment

5) that the requested information will be provided by the third quarter 1984.

tel (5).

In response to staff's question F471.16, reouesting estimates of projected doses to individuals and post-accident dose rate maps for potentially occupied plant areas to comply with Section II.B.2 of NURfG-0737., the applicant indicated (in Amendment

5) that the information will be provided by the third quarter of 1984.

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In response to staff's question F471.17 requesting confirmation that the whole body dose of less than 3 and 18 3/4 rems to the whole body and extre-mities (in reference to Section 1.10, Unit 2 Response to Regulatory Issues Resulting rom TI'll) during the collection o

reactor water post accident sam,es, is based on pl essur zed reacto-ater radia.ion sources, the applicant indicated (in Amendment

5) that the requested information will be provided by the third quarter of 1984.

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(7)

In response to staff's question F471,19, requesting (a) description of post-accident access and shield design

review, (b) description of buildup of'ctivated corrosion products (crud) in various components and systems, and (c) description of post-accidert vital area monitors.:fhe applicant indicated (in Amendment

5) that the response will be provided by the third.quarter of 1984.,

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I QD t.2O Llt (8) l}uestion 471.20:

To comply fully with Section II.B.2, Shielding, of HUREG-0737 the folowino information and documentation should be pro-

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(a) Post-accident radiation doses to individuals for necessary occupancy P

times in vital areas and dose rate maps for potentially occupied areas; P.g (b) Assurance that personnel exposure will be within the guidelines of GDC-19 limits:

(c) Assurance

.hat personnel exposure in co"tinuous>y occupied areas (such as control

room, TSC, etc.) will be less than 15 mrem/hr (avera'ged over 30 days) following the accident.

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In'response to staff's question 471.12 requesti'ng estimate of inhalation

exposure, the applicant indicated (in Amendment

5) that the information will be provided by the second quarter 1984.

(1 0)

OS In response to staff's question 471.13 requesting estimate of ti-16 dos'e contribution at nearest point of plant boundary, the applicant indicated (in Amendment

5) that the information will be provided by second quarter 1984.'

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LtQ In response to staff's question 471.14, requesting estimate of doses at locations outside of plant structures, the applicant indicated (in Amendment

5) that the information will be provided by the third.quarter of 1984.

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The applicant has provided insufficient information on dose assessment, indicating in response to question F471.11 that the Man-Rem evaluation is in progress, and that the information i ill be provided by the fourth quarter o

1984.

(13) guestion 471.21:

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LXf (a) Fi.gure 13.1-9 shows tha. tne health physics and che;iistry functions L

at.HHP-2 are not separated into a Health Physics Section and Chemistry Section supervised by a Health Physics Supervisor and a Chemistry Supervisor as recommended by our positions in Section II.A.l of I

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Your. organization and Figure 13.1-9 shoul d be revi sed to reflect separate supervision of these distinct functio'nal areas.

(b) The applicant should provide qualifications in the form of a

resume for the Superintendent, Chemistry and Radiation Nanacement (RPY() to demonstrate that the RPY( meets the requirements o= Regulatory Guide 1.8 "Personnel Selection and Training."

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V '23 (c) The applicant should commit to using the criteria of ANSI 3.1, Oecember 1.979,'n selectina the individual temporarily filling the RPH's pos ition as outlined in NUREG-0731.

(d) The applicant should commit to train health physics technicians in ~

accordance with the criteria of ANSI/ANS 3.1-1978, which requires one year of related technical training and two years of experience, or ANSI I

18.1 which also requires such training and experience.

Additionally, radiochemistrv and radiation protection are separate specialties each requirina two years of working experience, as indicated in ARSE 18.1.

The applicant should commit to provide experience"'echnicians with appropriate qualifications and t'wo years of experience in each.spe-

cialtyy, chemistry and radiation protection, or should separate the functions into two distinct specialties in accordance with ANSI.18.1.

. (e)

To comply with the criteria of NUREG-0654, Table B-l and the II.A.d(2) of NUREG-0731, the applicant should commit to have at least one ANSI

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18.1 qualified health physics technician on the site at all timo's..

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