ML17303A456

Forwards Rev to FSAR Re Compliance W/Reg Guide 1.45.FSAR Revised to Reflect Use of Gaseous & Airborne Monitor Detection Procedures in Place for Quantifying RCS Leakages

ML17303A456
Person / Time
Site:	Palo Verde
Issue date:	07/02/1987
From:	Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RTR-REGGD-01.045, RTR-REGGD-1.045 161-00344-JGH-J, 161-344-JGH-J, NUDOCS 8707130010
Download: ML17303A456 (11)

Text

REGULA Y INFORMATION DISTRIBUTI "YSTEM (RIDS)

ACCESSION NBR: 8707130010 DOC. DATE: 87/07/02 NOTARIZED:

NO DOCKET I FACIL:STN-50-528 Palo Verde Nuclear Station.

Unit ir Arizona Publi 05000528 BTN-50-529 Palo Verde Nuclear Station.

Unit 2. Arizona Pub li 05000529 STN-5Q-530 Palo Verde Nuclear Stationr Unit 3r Arizona Publi 05000530 AUTH. NAME AUTHOR AFFILIATION HAYNESr J. G.

Arizona Nuclear PoUJer ProJect (formerly Arizona Public Serv RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

ForUJards rev to FSAR compliance e/Reg Guide

1. 45. FSAR revised to reflect use of gaseous

& airborne monitor detection procedures in place for quantifying RCS leakages.

DISTRIBUTION CODE:

A001D COPIES RECEIVED: LTR l

ENCL L SIZE:

TITLE:

OR Submittal:

General Distribution NOTES: Standard i z ed plant. M. Davi sr NRR: 1Cg.

Standardized plant. M. Davisr NRR: 1Cg.

Standardized plant. M. Davisr NRR: 1Cg.

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EG&G BRUBKE> S NRC PDR NOTES:

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Arizona Nuclear Power Project P.o. BOX 52034

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PHOENIX, ARIZONA85072-2034 U.S. Nuclear Regulatory Commmission ATTN:

Document Control Desk washington, D.C. 20555 July 2, 1987 161-00344-JGH/JKR

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units.l, 2 and 3

Docket Nos.

STN 50-528 (License NPF-41)

STN 50-529 (License NPF-51)

STN 50-530 (License NPF-65)

Change to the FSAR Concerning Regulatory Guide 1.45 File: 87-A-005-419.05 87-A-056-026.

87-006-216

Dear Sir:

Attached, please find changes to the FSAR to document our compliance with Regulatory Guide 1.45.

The FSAR has been revised to reflect the fact that a

gaseous and airborne monitor is used for detection,

however, procedures are in place to use other means for quantifying RCS leakage.

A safety review and evaluation was performed in accordance with 10 CFR 50.59.

It was found that no unreviewed safety question was introduced.

Due to the uncertainties involved with gaseous and airborne particulate monitoring, any quantification using those methods would prove inaccurate.

By directing the operators to quantify the leakage by another more reliable

method, the results would be more accurate.

The intent of the Regulatory Guide is still being met.

There are still various detection methods and means for quickly quantify-ing the leakage.

Should you have any further questions regarding this matter, please contact Mr.

M. F. (}uinn of my staff.

JGH/JKR/rw Attachment 8707 k3001 0 870702 8

Cg 05000528 PDR Very truly yours,

).5 A~p G. Haynes Vice President Nuclear Production cc:

0.

M. De Michele E. E.

Van Brunt, Jr.

A. C. Gehr E.

A. Licitra R. P.

Zimmerman M. Davis G.

M. Knighton 4'r ge4 g dq~/3ze(di ~

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PVNGS FSAR CONFORMANCE TO NRC REGULATORY GUIDES Since severe sensitization is avoided, testing to determine susceptibility to intergranular attack is not performed.

REGULATORY GUIDE 1.45:

Reactor Coolant Pressure Boundary Leakage Detection Systems (Revision 0, May 1973)

RESPONSE

The position of Regulatory Guide 1.45 is accepted, gxe2er-~

see insert a

secCma-& 2 5+.

Also see CESSAR Section 1.8.

REGULATORY GUIDE 1.46:

Protection Against Pipe Whip Inside Containment (Revision 0, May, 1973)

RESPONSE

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-; r, ~i" Except as discussed below, protection against pipe whip inside

"=the containment complies with Regulatory Guide l.46.

A.

Position C.l.b of the Regulatory Guide:

Intermediate break locations between terminal ends are

"'~'~~""'>>"~"postulated to occur at weld joints where the piping

'" incorporates a fitting, valve, or welded attachment

,-where the following are met (as specified in NRC Branch Technical Position MEB 3-1):

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4%

I I I ~

' LV&AU4

~l(t (1,)

=- -the streys,;range S,exceeds 2.4 S, where S

",~.-~'~~<is -the.',design"stress

-intensity as defined in Section III of the ASME Code, or (2) the stress range S

as calculated by equation (10) n of Paragraph NB-3653 exceeds 2.4 S

and the m

stresses computed by equations (12) and (13) of Paragraph NB-3653 are greater than 2.4 S

, or m'3)

If fatigue analysis is performed, any intermediate

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location between terminal ends where the cumulative Amendment 5

1.8-30 August 1981 1

0 ~

Insert a:

Position C.5 states that each method of detection should have the capability of detecting leak rates of 1

gpm within one hour.

The airborne particulate and airborne gaseous monitoring methods are capable of identifying leakage conditions, but are not used for quantifying that leakage.

Procedures are available that instruct operators to perform a water inventory balance upon alarm of increasing trend of activity. (Refer to section 5.2.5)

PVNGS FSAR INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY 5.2.3.4.2 Control of Welding 5.2.3.4.2.1 Avoidance of Hot Crackin A.

B.

Components in C-E Scope of Supply Refer to CESSAR Section 5.2.3.4.2.1-A.

Components Not in C-E Scope of Supply In order to preclude microfissuring in austenitic stainless

steel, PVNGS design is consistent with the recommendations of Regulatory Guide 1.31 except as noted in section 1.8.

Se2

~ 4 INSERVICE INSPECTION AND TESTING OF REACTOR COOLANT PRESSURE BOUNDARY Details of the inservice inspection program are included in section 6.6, and Section 3/4.0 of the Technical Specifications.

Accessibility of inspect,ion areas is discussed in CESSAR Section 5.2.4.1.

5.2.4.1 systems are sufficiently diverse and sensitive to meet the criteria of Regulatory Guide 1.45~for leaks from identified and except as noted in section 1.U unidentified sources.

DELETED

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&44 S.2.5 REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION

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SYSTEMS Means for the detection of leakage from the reactor coolant pressure boundary are provided.to alert operators to the exis-a tence of leakage above acceptable limits, which may indicate an unsafe condition for the facility.

The leakage detection 5.2.5.1 Leaka e Detection Methods 5.2.5.1.1 Unidentified Leakage April 1986 The four methods employed to detect unidentified leakage are presented in the following sections.

12 Amendment 15 5.2-136

PVNGS FSAR INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY

~

Safety injection line pressure

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High-pressure safety injection header pressure o

Low-pressure safety injection header pressure 5.2.5.2.3 Leakage Detection Conversion to Leakage Equivalent The procedures necessary for each leak detection method to be converted to a common leakage equivalent are indicated below.

5.2.5.2.3.1 Containment Radioactive Gas and Air Particulate see snser b

> 44 A.

Records particulate and gaseous activity measurements

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P t

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at equal t3.me intervals.

B

,Determines.the activity increases during these intervals.

C.

Estimates RCS activity level based on p evious operat-ing history.

D.

Estimates the coolant leakage rate from the radioac-

.tivity increases.

This is accomplished by comparing the measured 'increases to 'urve showing abnormal

'primary coolant leakage as a function of particulate

"--<<'-"'and -'gaseous-"activit vari'ation..-

Estimated leakage and jneasured particulate and gaseous activi-sGvL pipit,

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< ') ni g

P q v)'~Paawi) i...ties then are plotted to test the consistency of the data and to estimate the'me elapsed since the beginning of the leak.

Nonconstant ctivity increases mean either:

o Containment atmosphere activity is approaching steady state o

" "The"abnormal "leakage flow"-i'.-'not constant.

Insert b:

... or indic'ation of an increasing activity trend, the operator conducts a water inventory balance to determine coolant leakage rate.

Amendment 12 5.2-142 February 1984

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PVNGS FSAR PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS B.

Provide for early detection of radioactive leakage-into normally nonradioactive

systems, including primary-to-secondary

leakage, primary-to-atmosphere

leakage, and process system leakage into normally non-radioactive systems.

included is the capability of both the containment building gaseous channel and the containment building particulate channel each to detect independently an increase in the reactor. coolant system-to-containment atmosphere 1 k,

&4-MBA'. ll': -I W 5

h methods of leak detection required to follow the recommendation of NRC Regulatory Guide 1.45. except as noted

'i:he hvgypgq~ yg p.'.c"ocomouzer-contro~.t.ed an:=

x~ cc"--

.an provide,.cggtinuoug,~r@qte.j.ndicqtion~and recording of me,.'~~,,giqPqzne,.xadj,oaqtipaxontamination in the form of c-, e~ particulates end.,jodines,in areas where personnel normally have access, except in areas where the poten-

,>,z;.,tial. for,airborne. activity releases is negligible, in order'o follow the recommendations of NRC Regulatory Guide 8.8'or control of occupational exposure to 1

radiation.

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~,'l 11.5.1.1.2 Effluent Monitoring System

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The effluent monitoring system is designed to perform the fol-lowing functions xn or6er to meet

%he requirements of 10CFR20,

10CFR50, and followShe recomme'n8atxons of Regulatory IQCFj

> f' v>

nc'uide 1.21 during normal operations, including anticipated U

operational occurrences:

A.

Provide continuous representative

sampling, monitoring, recording, and indication of gaseous radioactivity

levels, and, as a minimum, continuous representative sampling of particulate and iodine radioactivity levels along principal effluent discharge paths.

11.5-2

PVNGS FSAR PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS 12 In addition to the three radiation channels a hygrometer which measures dewpoint temperature is provided for the CB-B monitor.

The hygrometer is microcomputer-controlled and is configured to be an extra channel of,the monitor. 'he hygrometer channel measures dewpoint temperature over the range of 0-200F.

Indi-cated dewpoint is accurate to within +.4F with respect to actual dewpoint of the sampled air at a rate of change of dew-point up to +3F/sec.

This channel can be used as a method of RCPB leak detection.

11.5.2.1.3.13 Containment Buildin Atmos here Monitor, CBB Channel "B"

XJ<<S B-RU-01 The containment building atmo-sphere is continuously monitored for particulate,

iodine, and gaseous activity.

The sample is drawn from the containment building in a closed system, is monitored outside the contain-

ment, and then is returned to the containment building atmosphere after it passes through the samplers.

The particulate and gaseous channels serve as two methods of RCPB leak detection in accordance with Regulatory Guide 1.45.

except as noted This monitor is designated seismic Category I.

in section'<1.8.

In order to obtain a representative sample of containment air, the sample line inlet, is located on the operating level between see insert Y.

two of the normal cooling units intakes.

This location also facilitates RCPB leak detection by these monitors.

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Available monitor sensitivities allow the particulate and I-131 I

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channels of the monitor to detect maximum permissible concen-trations allowed by 10CFR20 in the containment building within one hour for Cs-137 and within eight hours for I-131.

The CB-B monitor is located just outside the containment build-ing. It samples the containment atmosphere through piping penetrations.

Isolation valves at the monitor automatically Insert c:

While shown on the 100'-0" elevation in Figure 11.5-3, the sample point is actually on the 93'levation.

February 1984

11. 5-39 1

Amendment 12