ML20023B475

Responds to NRC Request for Addl Info on IE Bulletin 81-03 Re Application of Hypochlorite to Control Growth of Biofouling Organisms in Salt Svc Water Sys.Npdes Permit & EPA Regulations Allow Discharge of Chlorine for 2 H

ML20023B475
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	04/21/1983
From:	Pollock M LONG ISLAND LIGHTING CO.
To:	Jordan E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
REF-SSINS-6820 IEB-81-03, IEB-81-3, SNRC-846, NUDOCS 8305050109
Download: ML20023B475 (3)

Text

--

^'

e e

asasampassrnasemurar I75 EAST OLD COU N TRY ROAD

• H ICK SVi LLE, NEW YORK 11801 MILLAPD S. POLLOCM VICE PRESIDENT NUCLEAR April 21, 1983 SNRC-846 Mr. Edward L. Jordan Director, Division of Engineering and Quality Assurance U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19404 I&E Bulletin 81-03 Long Island Lighting Company Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

Dear Mr. Jordan:

In response to your request for additional information concerning the subject bulletin, we have enclosed a copy of our letter SNRC-682, dated March 30, 1982. We believe that this letter, which was supplementary to our original response, SNRC-590, dated July 7, 1981, provides the major portion of the information presently being requested.

In our original response it was stated that during l normal operation of the plant, the attachment and growth of l biofouling organisms in the salt service water systems serving

, the plant will be controlled by application of hypochlorite at l the maximum rates allowed by the U. S. Environmental Protection Agency. In complying with your request for additional informa-tion concerning application of hypochlorite, the following update to that response is provided:

At present, our New York State Department of Environmental Conservation (NYSDEC) discharge permit allows for a maximum daily discharge of 0.5 milligrams per liter free available chlorine during test and startup operations. The level of chlorination to be applied during normal plant operation has not as yet been mutually agreed upon by NYSDEC and LILCO. The discharge permit has estab-lished the guidelines for determination of an acceptable level.

8305050109 830421 55 PDR ADDCK 05000322 G PDR

April 21, 1983 SNRC-846 Page 2 Because the permit was issued on December 1, 1981, it reflected the then draft EPA regulations which controlled the discharge of chlorine (40CFR 423.13b). These regulations pro-hibited the discharge of total residual chlorine unless a chlo-rine' minimization study was conducted which demonstrated the necessity of discharging chlorine. The permit _ requires that LILCO submit a plan of study for the chlorine minimization program to NYSDEC for approval within 180 days of the initiation of Reactor Low Power Testing, and also requires that the lischarge of chlorine will reflect applicable EPA BAT Limits., It also noted that chlo-rine discharge would be limited to two hours per day unless it is required for mollusk or crustacean, or any other biota EPA should permit.

On December 3, 1982, EPA issued final r'egulations (40CFR 423.13b) controlling the discharge of chlorine which established a maximum diccharge concentration of. total residual chlorine to be 0.2 mg/1. In addition, the regulations allow for chlorine discharge for more than two hours per day if it is required for macro inver-tebrate control. Therefore, both the current NPDES permit and EPA regulations allow the discharge of chlorine for two hours or longer in order to control macro invertebrates.

We trust the above information has been responsive to your request. If you have any additional information requirements, do-not hesitate to contact us.

Very truly yours, I Y- $/f M. S. Pollock l Vice President - Nuclear l

RWG/SD/HE:mp Attachment l cc: Mr. James Allan - Acting Regional Administrator (Region 1) l Mr. J. Higgins - NRC Site Inspector l "All Parties listed in Attachment 1" l

l m _ J

s cseansn.szwas.mma w w am mmem-.> . m.m-m.-u.come>~. -~ ~..

~

ATTACll:1E::T 1

~~

Laurence Brenner, Esq. .

llerbert H. Brown, Esq.

Administrat.ive Judge I,awrence Coe Lanpher, Esq. .

Atomic Safety and Licensin9 Marla J. Letsche, Esq.

Board Panel Kirkpatrick, Lockhart, '!!ill U.S. Nuclear Regulatory Com:aission Christopher & Phillips Washington, D.C. 20555 8th Floor 1900 M Street, N.W.

Washington, D.C. 20036 Dr. Peter A. Morris Administrative Judge Atomic Safety and Licensing Mr. Marc W. Goldsmi.th

- Board Panel Energy Research Group U.S. Nuclear Regulatory Commission 4001 Totten Pond Road Washington, D.C. 20555 Waltham, Massachusetts 02154 Dr. J a m e s !!. Carpenter MHB Technical Associates Administrative Judge 1723 Ilarailton Avenue Atomic Safety and Licensing Suite K Board Panel ' San Jose, California 95125 U.S. Nuclcar Regulatory Commission .

Washington, D.C. 20555 -

Stephen B. Latham, Esq.

. Tuomey, Latham & Shea Daniel P. Brou:1, Esq. 33 West Second Strcet Attorney P.O. Bo): 393 Atomic Safety and Licensing .

Riverhead, New York 11901 i

Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Ralph Shapiro, Esq.

Cammer and Shapiro, P.C.

i i

9 East 40th Street Bernard M. Bordenick, Esq. New York, Scw York 10016

, David A. Repha, Esq.

U.S. Nuclear Regulatory Commission '

Washington, D.C. 20555

' Matthou J. Kelly, Esq.

State of New York James Dougherty . Department of Public Service.

3045 Porter Street Threc Empire State Plaza Washington, D.C. 20003 A bany, :ew York 12223 6

f .

M Y.

t

.i.4.a.a w- w l .b ,s un.- - Ar L - 5.a.ll.1 u b M w. nA6.saw

% .ma. M A ld W sJ. b a . 4waarri^ -'-

f*

2

/nb pcow

/ .

t

. 3 6 "I'Ra7

.~.:u.e LONG CSLAND LIGi-1 TING COM PANY

.. 175 LAST OLD C O O f 4 T F' Y T4 0 A D H 4 C K SVI L LC. f4 C W iORK a l t, u l motum e rattoen March 30, 1982 viC L PO E ! RE N f '*t n;L E A8' SNRC-682 Mr. Ronald C. Haynen Ngional i.dminis t.:. i tor , Region i U.S. Suc3 ear Regulatory Connaiacion 631 Dark Avenue

' King of Pruscia, PA 19404 IE E Bulleti.n P.1- 0 3 Long Island Lighting Conpany SHOREllAM NUCLEAR pDULR STATION - UNIT 1 Dcchet No. 50-322

Dear Mr. Haynes:

In our response to IEE Bulletin 81--03, via letter SNRC-S90, dc L.:d July ~/ , 1901, it van stated that bio-fouling hai Liden plece in the non-se fety related Turmno Bul.tcting Service isatc 1-Dyntec. The following i nfortc.ation is profided to updat. that response bt. sed up?a recent S tar t up tes t e -:parience.

Our initin3 respcase ~tatcd that the blue must al flyti 7 u: e6ulls pas fouad to have fouled the .:4 inch supply pipo to tne Turoire Duilding Closed Loop Cooling Uater System Iicat l'xcha n g e.: (Tr.dLCU) uith shel! c and debrj a found to be in the TECLCW inlet hones.

This particular nystem had been operated interr.ittently fo:

st me tir..a i 1 exce:m of two yearr Ita.ti r.lly a stan.crs dc pump locate 1 in Lbe intchc canal sup,"'.ied und.ilterai occwate at a lowar than norml flow and vilhout acequato chlorination.

During the latter pr.rt of that tuo year period, a second tcmpo-rc:ry pump ,.a u tili zed providing higher ficw bu t again ' .i t l.out fi ltra t.i c . . Derin t '.u s pericd , final 6 od.:iry of llc i. : . :o cunal var, c'-;o p.3rio;.:a1 unich is consitzrce ta coni > ; ncte .c the bio-foullac p oueca which occurret. It 'nould .x no t e.d ,

that no sa fety related heat exchango, a 'cro cupplicd service .

water through thic':iamo tirc.c span.

I.t present, v:.ric o: cervice watc1 supplied heat exchangern having uafety related functions are in the Startup tent pha .;e . The u'.ter as nupp1]. d a from ti n D .y ' ctr d it : c tor i.;uild: .-

St rvice \..r Mr Syn 'c u u ;i ng th? j, m.  ;, n.g s and c. L;. ainerc . After apprcxilaatc2.y cight months of int.c r.ni t tent operation , the R!iR 4, f aw PM

=aL!L.- . w " '- ' - -- ~'

% 5.t~?;:~ ~~ " h':.r= = 55 :' & &l:==:Fif.25===.5:D J==

. M ",

• March 30, 1982 SNRC-682

• Page Two exchangers were visually inspected for bio-fouling and none was noted other than a handful of shells. The Reactor Building Closed Loop Heat Exchangers have also been simi3arly inspected and found to be frce of bio-fouling.

To asrure adequate flow to all heat exchangers in safety-related systems using service, water, flow elements have been provided on inlet or discharge of each exchanger. Because of the safety and p'erformance implications associated with blockage of these heat exchangers, the station operational procedures will contain requirements for periodic monitoring and inspection. As a minimum, flow for all safety-related' ,

service water supplied heat exchangers, as tabulated below, will initially be checked quarterly with visual, inspection of exchanger inlet channels to be performed at eighteen month intervals as appropriate. The interval for this periodic program will be adjusted.as a result of monitoring and evalu-ation of test data. This program will help ensure that the safety-related heat exchangers are available when required.

Heat Exchanger Designation Reactor Building Standby Ventilation IM50*WC-003A,B System (RBSVS)

Control Room Air' Conditioning (CRAC) IM50*WC-004A,B Residual Heat Removal (RHR) IEll*E-034A,B Reactor Building Closed Loop Cooling IP42*E-Ollh,B Water (RBCLCW)

Diesel Cooler IR43*E-013A,B,C .

We trust the above information has been responsive to your request. If you have any additional information requirements, please do not hesitate to contact us. .

Very truly yours, h77 [/ h 6$

M. S. Pollock p, Vice President - Nuclear 47 HE/pg cc: J. Higgins - i;P.C Trailur bec: W. R. Steiger R. Gutmann .

Dict. #14 l_ _