ML20008F118

Forwards SEP Topic V-5 Evaluation Re RCPB Leakage Detection. Requests Response within 30 Days If as-built Facility Differs from Licensing Basis Assumed in Topic Assessment. Evaluation Will Be Basic Input to Safety Assessment

ML20008F118
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/10/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Counsil W CONNECTICUT YANKEE ATOMIC POWER CO.
References
TASK-05-05, TASK-5-5, TASK-RR LSO5-81-03-010, LSO5-81-3-10, NUDOCS 8103120300
Download: ML20008F118 (5)

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3 March 10, 1981 19*

Docket No. 50-213

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LS05-81-03-010 Oc gif-Jgy ' h h d$Q fir. W. G. Counsil, Vice President g v,g r_-

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Dear Mr. Counsil:

RE: SEP TOPIC V-5, REACTOR COOLANT PRESSURE EOUNDARY LEAKAGE DETECTION

!!ADDAM NECK NUCLEAR PCWER PLANT Enclosed i' a copy of our evaluaton of SEP Topic V-5 for the Haddam ileck Nuclear Pcwer Plant. This assessment compares your facility, as described in Docket No. 50-213, with the criteria currently used by the regulatory staff for licensing new facilities. Please inform us within 30 days if your as-built facility differs from the licensing basis assumd in cur assessment or this topic will be assumed co@lete.

This evaluation will be a basic input to the integrated safety assessant for your facility unless you identify changes needed to reflect the as-built conditions at your facility.

This assessment may be revised in the future if your iacility cesign is changed or if NRC criteria relating to this subject are :rodified before the integrated assess.i;ent is completed.

In future correspcndence regarding this topic, please refer to the topic number in your cover letter.

Sincerely.

Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing

Enclosure:

SEP Topic V-5 cc w/ enclosure:

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tiarch 10, 1981

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Docket No. 50-213 LS05-81-03-010 Mr. W. G. Counsil, Vice President Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Post Office Box 270 Hartford, Connecticut 06101

Dear Mr. Counsil:

RE: SEP TOPIC V-5, REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION HADDAM NECK.10 CLEAR POWER PLANT

[aclosed is a copy of our evaluaton of SEP Topic V-5 for the Haddam Neck Nuclear Power Plant. This assessment compares your f acility, as described in Docket No. 50-213, with the criteria currently used by the regulatory staff for licensing new facilities. Please inform us within 30 days if your as-built facility differs from the licensing basis assumed in our assessment or this topic will be assumed complete.

This evaluation will be a basic input to the integrated safety assessment for your facility unless you identify changes needed to reflect the as-built conditions at your facility. This assessment may be revised in the future if your facility design is changed or if NRC criteria relating to thir subject are modified before the integrated assessment is completed.

In future correspcndence regarding this topic, please refer to the topic number '.n your cover letter.

Sincerely, k

Dennis M. Crutchfield, C ief Operating Reactors Branch No. 5 Division of Licensing

Enclosure:

SEP Topic V-5 cc w/ enclosure:

See next page

HADDAM NECK PLANT Mr. W. G. Counsil DOCKET NO. 50-213 cc Day, Berry & Howard U. S. Environmental Protection Counselors at Law Agency One Constitution Plaza Region 1 Office Hartford, Connecticut 06103 ATIN: EIS C0ORDINATOR JFK Federal Building Superintendent Boston, Massachusetts 02203 Haddam Neck Plant RFD #1 Resioent Inspector Post Office Box 127E Haddam Neck Nuclear Power Station East Hampton, Connecticut 06424 c/o L. S. NRC East Haddam Post Office Mr. Janes R. Himmelwright East Haddam, Connecticut 06423 Northeast Utilities Service Company P. O. Box 270 Hartford, Connecticut 06101 Russell Library 119 Broad Street Middletown, Connecticut 06457 Board of Selectmen

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Town Hall Haddam, Connecticut 06103 Connecticut Energy Agency ATTN: Assistant Director Research and Policy Development Department of Planning and Energy Policy 20 Grand Street Hartford. Connecticut 06106 Director, Technical Assess:ent Division

- 0ffice of Radiation Programs (AW-459)

U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460

HADDAM NECK SYSTEMATIC EVALUATION PROGRAM TOPIC V-5 REACTOR COOLANT PRESSURE BOUNDARY (RCPB) LEAKAGE DETECTION I.

Introduction-The safety objective of Topic V-5 is to determine the reliability and sensitivity of the leak detection systems which monitor the reactor coolant pressure boundary to identify primary system leaks at an early stage before failures occur.

II.

Review Criteria The acceptance criteria for the detection of leakage from the reactor to:lant oressure boundary is stated in the Genera" Design Criteria of f.ccendix A, 10 CFR Part 50.

Criterion 30, "Quali y of Reacto-Coolant Pressure Boundary", recuires tnat means shall be orovided for detecting an:. to tne extent cra::ical, identifying tne 1::atien of :he source of leakage in the reactor coolant pressure ocuncar.

Criterion 32, " Inspection

'f :esctor Coolant Pressure 50undary", recuires na components which are part of the reactor coolant pressure boundary shall be designed to permit oeriodic insoection and testing to assess their structural and leak tight in egrity.

III.

Review Guidelines T.e accentance criteria are imolemented oy the *. : lear RegJiatory Commission in Section 5.2.5. " Reactor C: clan: Pressure 5:uncary Leakage Detection,

an: Section 5.2 A, " Reactor Coolan Pressure 50;-:a y Inse vice Inspection a.: Testin ", of tne Stancar: Review Plan. Tne areas of :.e Safety Analysis Re: ort and Technical S;eci#ications are reviese: c estaclish nat informa-

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ti:n submitted by the liceasee is in coroliance '.' n egulatory Guide 1.05.

";eactor Coolant Pressure Ecundary Leakage De e:: don Syste-s" and tha: the irse-vice inspection pro: rams are based on the -er ire ents c'Section XI of :ne ASME Boiler and Pressure Vessel Code, ":.ules for *.he Inservice Inspet-

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tien of Nuclear Power Components".

Although not a :: art of this review, the consecuences of break and crack location in component failures is analyzed and evaluated in Section 3.6.1, " Plant Design for Protection Against Postulated Oi:ino Failures in Fluid Svstems Cutside Contain en:", anc Section 3.6.2,

":e ermination of Break Lo aticns and Dynamic 5"e: s Ass 0:iated with

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stulated Ruoture of Picing", of :ne Standard :e;ier Pl an.

IV.

Evaluation-Safe v Topic V-5.tas evaluated in :nis revie' #:- :: : liar:e of tne infor-

.a:i:n submitted by the licensee with Regula ry Guide 1.45, " Reactor Coolant

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e i n#0rmation in the Safety

. assure Boundary Leak 3;e :stection Systers" A aijsis Re:: ort and Te r.ni:al 5:ecifica icns izas su:stantiated by telephor,e

-.ers ation with the licens ee. Regula:Ory Sui:e 135(re:uires that at P00R ORIGILI.

.. least three separate detectio7 systems be installed in a nuclear power plant to detect an unidentified leakage from the reactor coolant pressure boundary of one gallon per minute within one hour.

Leakage from identified sources must be isolated so that the flow rates may be monitored separately from unidentified leakage. The detection systems should be capable of performing their functions following seismic events and capable of being checked in the control room.

Of the three separate leak detection methods required, two of the methods should be (1) sump level and flow monitoring and (2) airborne particulate radioactivity monitoring.

The third method ray be either monitoring of condensate flow rate from air coolers or mor.itoring of airborne gaseous radioactivity.

Other detection rethods, su:n as humidity, temoerature and pressure, snould be consideret to be alarms or indirect indication of leakage to the containment.

Tne recuire-rents of Regulatory Guide 1.45 and Standerd Review Plan 5.2.5 and plant in:orocrated systems that meet those requiremer.ts are tabulated in Encicsure 1.

V.

Oce iusions Our review indicates that the Haddam Neck Plant is in compliance with Regulatory Guide 1.45.

9 P00R BRIGINAL

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ENCLOSURE 1 TABLE 1: REACTOR COOLANT PRESSURE B0UNDARY LEAKAGE DETECTION SYSTEM Plant S.R.P. 5.2.5 or Incorporated Re; Guide 1.45 Sysler System Pecui rement Yes,1 or 2

1) Sums Level Monitoring (Inventory)

X Manda tory Sum: Pue: A::uations Yes,1 or 2

2) Monitoring (Tire Meters)

Manda tory

3) Aircorr.e Parti: alate Yes Radioa::ivity Monitoring X

Manda tory

1. ) Air orne Gaseous Yes, 4 or 5 X

Radica :ivity Monitoring Manda tory

5) Condensa:ec Flow Rate Yes, 4 or 5 fro-Air Coolers Mandatory

6) Containmen A: sraere Yes Pressure M:nitonn; 0;;ional Containment A: Os nere Yes

7) fiuridity M:r.itoring 0;;ional X

Containme-At Os:eere Yes g) Tem;erature M:nitorin; Op;ional Yes

9) CVCS Makeu: Flow

• ate Optional

10) Portable Ultrascri:

l Optional Yes Dete:: ors II) Air Conditioner Co:la,:

b0 Tenperatu*e Rise 12) l 13)

P00R ORIGINAL