ML20049A596
ML20049A596 | |
Person / Time | |
---|---|
Site: | Shoreham File:Long Island Lighting Company icon.png |
Issue date: | 06/11/1981 |
From: | Novarro J LONG ISLAND LIGHTING CO. |
To: | Harold Denton Office of Nuclear Reactor Regulation |
References | |
RTR-NUREG-0737, RTR-NUREG-737 SNPS-586, NUDOCS 8106150336 | |
Download: ML20049A596 (59) | |
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.._hresamesnu.O r SHOREHAM NUCLEAR POWER STATION P.O. DOX G18, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792 June 11, 1981 SNPS-586 N & (b N/
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Mr. Ilarold R. Denton, Director fp I Office of Nuclear Reactor Regulation (, q 2,p @ U.S. Nuclear Regulatory Commission K Ug7 C Washington, D.C. 20555 \ p- 4 %, As .N . S!! ORE!!AM NUCLEAR POWER STATION - UNIT 1 Docket No. 50-322 '/
Dear Mr. Denton:
Enclosed herewith are sixty (60) copies of LILCO's responses to the Safety Evaluation Report (SER) Outstanding Issues and Post-TMI Requirements outlined in NUREG-0737. These responses are listed in Attachment 1, and address NRC Staff reviewer question:3 raised during meetings with the Applicant during the weeks of June 1 and June 8, 1981 to discuss previous LILCO SER and TMI submittals. If you require additional information or clarification, please do not hesitate to contact this office. Very'truly yours,
/ ]
q }t om J. P. N varro (/Projec Manager Shoreham Nuclear Power Station CC/mh Enclosures cc: J. liiggins 8.10615O M FC 893:,
_s et t ATTACHMENT I SER OPEN ITEMS Number Issue 2 Masonry Walls 17 SRV Surveillance Program 39 Emergency Procedures 41 LPCI Diversion Fracture Toughness of Containment Boundary Materials NUREG-0737 ITEMS II.K.3.13 HPCI and RCIC Initiation Levels II.K.3.15 Modify Break Detection Logic. to Prevent Spurious Isolation of HPCI and RCIC. Systems II.K.3.17 Report on Outage of ECC Systems-- Licensee Report and Proposed Technical Specification Changes II.K.3.22 Automatic Switchover of Reactor Core Isolation Cooling System Section--Verify Procedures and Modify Design II.B.2 Plant Shielding
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SHOREHAM OUTSTANDING SER ISSUE #2 MASONRY WALL . Question 1.0 In the drawing submitted in response to IE Bulletin, there are masonry walls designated as movable. Please discuss how such walls are designed and built and how they differ from non-movable walls. Are all the masonry walls in Category I buildings movable?
Response
The submitted drawings identify isolated block walls as "re-movable" and not " movable." A block wall identified as "re-movable" is to be interpreted as a wall that is removable by mechanical means, i.e., jackhammer or other equipment. Such a wall is designated as removable for the purpose of equipment maintenance or equipment replacement. Typically, a removable block wall is constructed between reinforced concrete walls in an area where future access is required or desired. The design and construction of a ,re-movable block is identical to all other block walls within the Shoreham Nuclear Power Station. The block wall design basis is as identified under question No. 3 below. Question 2.0 In the drawings submitted you have shown that some masonry walls are acting as pipe supports. Discuss. support design analysis for all the load combinations including load induced by pipe thermal expansion. Use RHR piping system as an example and provide detailed design calculations that demonstrate adequacy of the masonry wall support.
Response
Masonry walls at ,the Shoreham Nuclear Power Station have not been utilized as structural attachment points for pipe supports. The submitted drawings do however, identify block walls that have piping systems passing through the wall. In such a case, a clear space between the pipe and the wall has been maintained to allow for piping system and wall movements. The annular space has been designed to ensure that piping system loads are not imposed on the block walls.
s . - c Question 3.0 You stated that the following references were used to design masonry walls.
- a. New York State Building Construction Codes.
- b. Masonry Design Manual by Masonry Industry Advancement Committee, 2nd Edition, 1973.
- c. Specification for the Design and Construction of Load-Bearing Concrete Masonry by National Concrete Masonry Association in 1968.
The staff has developed interim cirteria for review of masonry wall design. A copy is attached for your use.
~
Provide justification of your critcria using the above references when it is less conservative than the staff interim criteria.
Response
The Shoreham project has utilized the National Concrete Masonry Association (NCMA) specification allowables as the design basis allowables. The test data published on the ultimate tensile strength of Type S mortar on masonry walls ranges from 60 psi to 110 psi with an average value of 93 psi. Since the allowable ten-sile stress in the NCMA code is 23 psi, there is a factor of safety of about 4 inherent in the design. Furthermore, the interim criteria indicates that operating plants are allowed to be exempted from designing the masonry walls to zero tension. The Shoreham Nuclear Power Plant block walls were designed in the early 1970's and nearly all the concrete masonry walls were installed by 1975. Thus with regard to the interim criteria, we request that the Shoreham Nuclear Power Plant be considered as an operating plant and be allowed to utilize design tension stress normal to the block mortar joints. We request that the wall design basis, as outlined above, be utilized as the Shoreham acceptance criteria. Additionally, we request that the interim criteria requirement for interstory drift effects not be applied to Shoreham. The above requests are made to avoid major plant modifications
- and associated costs that would be required to implement the proposed interim criteria. Because the Shoreham masonry block walls are of a non-load bearing, un-reinforced design, any feasible field modification would require an allowable mortar tension value.
By definition, an un-reinforced block wall will have tension across , the mortar joints. Therefore, it is our position that the block walls can not be modified to meet the interim criteria of zero a tension perpendicular to the bed joints.
Question 4.0 Provide your method for determining the damping values and natural frequencies of the masonry walls and describe how you computed (determined) the maximum accelerations using the design floor response spectra.
Response
The Shoreham project will utilize maximum damping values of 4% for ODE and 7% for DDE for the analysis of the blockwalls. The natural frequencies of the block walls are computed with due regard to the stiffness and inertia properties of the walls and the actual boundary conditions. After the fundamental frequency of a wall is determined, the designed acceleration is read off the-peak broadened amplified response spectra curves. i Question 5.0 Provide the results of your masonry wall analysis in terms of computed maximum stress levels, location of the stress, and the corresponding safety margin. Your response may be limited to one typical case and one worst case example.
Response
At present, Shoreham is in the process of obtaining as-built dimensions of the block walls and all wall attachments. Pre-liminary analyses show that nearly all the walls have funda-mental frequencies greater than the rigid range frequency as defined by the amplified response spectra curves. Due to inertia loads alone, most of the walls have a maximum tensile stress of less than 12 psi. Reanalysis of the block walls is still proceeding. The effort is scheduled to be completed in three to four months.
1 i Revised Response - 6/81 SHOREHAM OUTSTANDING SER ISSUE #17 SRV SURVEILLANCE PROGRAM LILCO commits to accumulating the SRV data records which are required to support the proposed surveillance program. LILCO will evaluate any pending industry sponsored generic SRV surveillance programs and will commit to participation when such a program is developed. At that time, the analysis described in Paragraphs 3.1.5 and 3.5 of the proposed sur-veillance program will be performed using the previously accumulated data. 1.0 Purpose The purpose of the program is to accumulate information in sufficient detail to allow identification of generic safety / relief valve problems. 2.0 Scope This document defines the data records which will be used for monitoring performance of the Main Steam Line Safety / Relief Valves (S/RVs) throughout the useful service life of each such valve. 2.1 The program is structured to collect sufficient data to allow the identification of safety / relief valve problems to minimize the possibility of a failure of the valve. 2.1.1 Data is also to be collected on inadvertent safety / relief 2 valve operation, and on the failure of safety / relief valves to open or close. 2.2 For each safety / relief valve problem that is found to exist, the following information would be reported: i) A description of the problem; 4 ii) The operating conditions; iii) The failure mode (s) and the reason (s); iv) The remedial action 3.0 Description of Program 3.1 Introduction 3.1.1 A MSL safety / relief valve data record will be maintained for the Shoreham SRV's. 3.1.2 The information identified in Section 3.2 through 3.5 will be recorded and maintained for each safety / relief valve. 1
-3.1.3 The maintenance records will be updated with entries each time any work is done on the va;7e(s). This will include information regarding scheduled maintenance, and unscheduled' maintenance, as described in Section'3.4.
3.1.4 If subassemblies or components are interchanged.for maintenance, the records will provide traceability for the components and the valve assembly. 3.1.5 The SRV maintenance history will be analyzed annually for the purpose of identifying potential-trends which could lead to generic safety / relief problems, as des-cribed in Section 3.5. 3.2 Records Maintenance records will be maintained for each S/RV. The record will, as a minimum, identify the following:
- 1) Manufacturer and model number; ii) Type and size (including throat bore);
iii) Manufacturer's serial number; iv) Set pressure stamped on nameplate; v) Date first installed on main steam line; , vi) Vessel hydrotest pressure after the valves have been installed; vii) Copy of original production test records; viii) Results of startup tests and any special-tests; ix) Manufacturer's drawing and instruction manual references (GE-VPF). - 3.3 Scheduled Maintenance Records 3.3.1 Identification of whether the complete valve or subassembly has been serviced and/or removed from the steam line. 3.3.2 Dates when equipment is: i) Removed from service; ii) Reworked; l' iii) Retested; iv) Reinstalled in Service. 3.3.3 Operating history will be recorded for prior service cycle.
- This will include the following information
i i) The number of power actuations, and date; l ii) The number of pressure actuations, date and cause j of actuations; iii) Leak detection device indications / signatures and history of these; iv) Other events; such as whether the steam lines were flooded for reactor shutdown; v) Ambient temperature, air and electrical supply condition. t h, _ . . _ .__- _ .
I 3-3.3.4 Resultt of tests conducted prior to refurbishing, if applicable, will be recorded.
- 1) Performed where; ii) Performed by; iii) References used for cleaning, testing and refurbishing
, procedures; iv) Extent of disassembly performed; v) Details of any machining, rework or nondestructive examinations performed on components; vi) Post reassembly bench test details will refer to test report number and attach summary of results. 3.4 Unscheduled Maintenance Records i 3.4.1 The following information will be maintained for unscheduled maintenance. 3.4.1.1 The reason w:1y a valve'is being removed from service. 9 4 3.4.1.2 The following information will be recorded about the operating history of the valve: 1 i) Has the valve malfunctioned in the past? If yes, a brief su nmary of past history will be provided. ii) Has this vtive caused trouble in the past? If yes, a brief sum nary of past history will be provided. 3.4.1.3 Record the resu: ts of diagnostic tests -if and when performed prior to disassembly. 3.5 Analysis of Data 3.5.1 The data accumulaued on this program inay be stored manually or by electronic data processing in a manner which gives 4 flexibility in data retrieval. 3.5.2 A summary of cumulative failure rates will be maintained for predominant failure modes and for overall failures. This summary will be updated annually. i
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' Revised Response - 6/81 SIIOREIIAM OUTSTANDING SER ISSUE # 39 EMERGENCY PROCEDURES Emergency procedures for ATWS events will be developed and submitted to the NRC for revi^w. Operating procedures for the primary to secondary containment leakage detection and return system will also be submitted to the NRC for review after their development. LILCO will develop and submit these procedures at least six months prior to fuel load. . D
e e SHOREHAM OUTSTANDING SER ISSUE #41 LPCI DIVERSION To resolve the concern of the NRC staff that premature diversion of Low Pressure Coolant Injection (LPCI) flow to containment spray could adversely affect core cooling the Shoreham symptom based emergency procedures have been carefully constructed to caution the operator against such diversion unless " adequate core cooling is assured." These procedures, which were developed with
! the assistance of the BWR Owners' Group and reviewed and accepted by the NRC staff, clearly identify LPCI diversion as secondary to the core cooling requirements except in those scenarios beyond the plant design envelope which involve multiple failures and for which maintenance of containment integrity is required'to minimize l
risk to the environment. l l ), i i a 1-e i i
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1 l Fracture Toughness of Containment Boundary Materials Attached is the following information:
- 1. Attachment 1 - Mill test reports and associated documentation for a main feedwater isolation check valve in the steam tunnel (lB21*A0V-036A)
- 2. Attachments 2A thru 2F - Mill test reports and associated documentation for the thickest containment penetration sleeve (for each type of material). Also included are mill test reports for the flued head fittings for the main steam ponctrations. This information is organized as follows:
af Attachment 2A - Penetration Survey. Penetration materials were determined from documen- , tation. For each of these materials representative ponctrations were chosen with the thickest wall. b) Attachment 2B - Mill test reports and associated documentation for flued head fittings (includes main steam). . c) Attachment 2C - Mill test reports and associated documentation for main steam penetration lA sleeve. d) Attachment 2D - Mill test reports and associated documentation for ponctrations X-27 and X-26 slooves. c) Attachment 2E - Material specification for cold ponctration piping sleeves, f) Attachment 2F - Material specification for hot and cold ponctration sleeve material.
- 3. Attachment 3 - Mill test reports and associated documentation for process pipe material for main steam penetration X-1A and feodwater penetration X-2A.
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- . ./ - .,, PITT5GerGH CES 90!r.E! STEEL COMPANY 0 OE D ., )* ; - [ ,.( -; , r.v. .t. i. c . ,r ., . < - ..a ;:, c . . :.r. n :.. .
- c. A i 1-25.71 o.. .> ..
605.:.'ld ORDER RECORD s,,,.....
. Su P Piri . tr 'i18:t'C 1 6 1tr.
e ?.nir a us. *a a P.'a0 t.e. O 10 . r a s'.> r .*, e. ea r *. r sa 1 + A L L t: v t la t. , a.u s f u f es ! *
- g e. ; .. , ,
* - - - - - ~ ~ - - - - ..
Pd f VIL L C l' L A tJF1 */ t NT gi g, r ,.
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- COLLECT' 7 t R'95:
IICUTC
- I 400.740 i e A l'Pf a rj w et T Capitol Pipo & Stool Producta, Inc. ,
;; Contract 10093-CC0lt e
s oseu g
- s ; * '
PLE ASE SE ND v os A ACCC DT A *.C C OF T ht$ OH r.E H OY R E T UR td 74 AIL A ND ST A T C T HL D A T E, CD D AT FS YOU ,WIL L M A K E $ Hbw( *
,..u,_.. .. . _ . . .
e rw v. a *. ' CCSCRIPTION
- PR IC f Groun Ilo. KZl_ Ponotration l'o.
I'O' l 27 ---l-1/4"'ScW.~ h0 ~ Pip'o':: 6'-h"-"XS-25,'XS-25, ~ ~ ~ ~ ' ' " 30: Lon a - - - - XS-27,-X0-23,'~~~ Ilo, Hoat Fo 8 XS-29, XS-30 --Troat-l [ _Groun No, FD1 V f, f.) ' 3 j 2" Sch. 80 Pipo x 78-6" Long X-11, 4 X-18 i
. 5.66.
Fg (' l , l
~
- 29. I 1 8" Sch. 40 Pipo :. 71-4" X-17 l
; 33 42 ; j Long lio Heat F4 r; . ~~~Troa u @ 2 10" Sch. 40 Pipo 7'-8" XS-5, XS-6 ; 25.bc
- ; Lor.g I .
Pc
. l
- 31. ; h 10" Std. Pipo a 7 8-6" Long X-13 74.'s.'
i ! . l ! Groun No . K Tl 8
- 32. 1 16" Std. Pipo z 6'-8" Iong X-26 ; 74 8
, , : 2 ..v i i Groun I!o. _I_C_dl _
_No Hoat i Troat c.o.l 33, _ i;3n-Std.-P'l.po-:-6 8 -8"-Long---X-27-- - - ' 74.[2
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1
- r e . .- 5 $- .. .
. . _ . . ._ ACKt40WLCCG ED: . _ .5.H. I.P. M E..N. T. .PR Ou i".C D : .
64 A1 f Rl AL T f# A PI.'.POf> I A T f GN I,,a.a ; , no.
- o. . . . i .i . . u , . . r...., o... i n. . . - o...
, .i m . ..f . ,. . . . c. . . . . ; s e . .. . , . .,, . a : .. o, , , - 9, . ,, .. ....s. . a.n : A -- ..um uo c.~. *-- -4. -- !. -,. .'...
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H T T s ? u ".ri 7 E , vo. ~ r . ,1 i n. c 0. . . m - f [(p ,
~ , u . .. -
ORDER RECOPD . . Philadolphi.n, Pa. g s~ ,, , , ,,, , ,. P1'ttOburgh.-Das Moinca Stool Co. , ., ..
) . , . .. s s . , , , - . - ,,.,,...,,p., Hovillo Iolond, Pc. , , ., . . . n . . n ....4 .:otttc, r . . s. . . ,, e . . .
Capitol Pipo 6: Stcol Proc.loto, Inc. .w e , . CO-57 Par:arcJ Contor ......... .
, s c w, E.111 ding uno, Roca 21$ n .: , . . . . . . -
- 87$ Grocntroo Road P_ookhoven, L.I.f.'
i Pittsbur@, Pa. 15220 Contract 10093-.CC .
,. NI 4 ._ _ ._. _ _. _ .___._ -
- ro r a sr . r - . em, a c r n- o:c. nr r m. o,r r r r
. r w".: u w. i, : s- r.:c v..r: e t c .. e a - -ce w . i i .mrw v ,r .:..s . . 884 tC f.
- h. ... ..
r . .,; o ; r ? 'e s i Chcn;p Order No. 3 to our 0: dcr 60$70, Chcnry Order No.1 j , datoa 1-27.-71 and 60270 dated 1-26-71 icccod to corroot tho follo rinL; 10r_3 - so H3-6 7 I ; Metericl: AS:13 CA333 Gr. 6 P2B Socaloca por Spoo. j i MS9 4 dated 12 2-70 (Rov.)
- m .
J4.-j l Grmm Ho EC1 Pe .M.? ^;ic . No .
. d ,
- 10. i (1 : Po. 2" Sch. 83 Pipa n 6'-4" X-33 5 6' j .
(T.'o heat tv0at) i I
! Grmm ro., I.U1 'I '
33 1 Pc 18" Sch. 40 Pipo n 6 8 8" X.47 :15h 95
, (:To_ hont troat) .Grmm Ho_ _F.'.1
- 35. 5 Poc . 16" Soh. 30 Pipo n 6 '.4 1/4" Xc.1dA,Iw1C3, 39.lE X 15, X"09, XS.10
- Grmm Ho. PGl 1, . -- .
40 @ Pc. 3" Sch. 40 Pipo n 68 8 1/4" X-31 5 06s
@ Pipo n 6 '-8 1/4" X 32 9.0' Po . 4 S ch.Q 40,jl'Cn.NE $ N= 0A 3 ! ? -- G U- ' M.@ rial: Ao.C D.'i312-5.9 T,;o 3OhL Socrlocc S .alnlocs Pipor par l'S3 4 ,dctod 12-2-70 (Rov.)
Ar.rr4 r .u :.u.n; a n rr.u e n i i m n A ' -
. . . , . , . . . . . ..r.,, \
i . 4. . .. , .... ,,, .. i......- 9 .. . .. . . ..... ... ....
...... . r..... i...... .....a ......... . . .e, _ . . . #. . i i... . . . . . - . .....2 ,,. .......
7 ,>
/ - .. w . V : ' ' ' A. f .spe -
7O AL L'th .C-
- i '
Vhtj.' WCE- Y Al 3' El * .~'~ ~- u)ad'j $<& 7 Y N I ,
?20-ti% vin 4 J ze deg. ..ru2 % %_ T A ,. S '?=t-s@%4/ .-tmvhw2l I;.o-Y ' f ihm ad? YW !
r- p -Wl'l'M_ A
. u... . w= umr w.;ms onLrmcor/mv n -v ~~ .<
L c.*ca:.a. Lov **'ork lNFo C)NLY
~
(A R V
- fan. 22, 1971 :
"* C.ot.~0 pu N r TGIN6 E,LGOll:TggRev, reb. 15, 1973 - ._ i . !!ATERI AL SPECI TIC /frION_ ltS-9. p.&r.E7ap M ocJ, g/26 +
Soamicus and L'oldod Pipo for Low Tcaporaturo Sorvico r O'f ' g, 3 Pipq chall confora to ASME SA333-69 Grado 6. All catorial shall bo j fine grainod, nornalizod ahd chall coot the requirononts of tho 10GD ; ASifS Nucinar Codo, Suction III, Clnau D Vossolo including 1960 i Su=mor Addonda cnd ANSI D31.1.0-1907 odition. ! b I, All tosts and inspections [ required by SA333-69 and SA530-G9 chall bo perforsod. Mochanical F tosta required by SA333-09 and S4530-69 shall bo parforned in
~
accordanco with ASM2 SA370-68. Longitudinal Charpy V-Notch I= pact tosto shall bo nade in accordanco , with paragraph N-330 of Nuclear Codo Soction III and SA370-30 at a , test tc peraturo of ninus 30*?. Averngo value for a cot of full i. sino cpeciscas (10 n 10nni chall be 20 foot pounds tinimut, with only one specimen of a sat of thrco pormittod to bo loss than 20 [ i but not loss thcn 15 foot pounds. Tho othor two of tho cot must i. g be 20 foot pounda or over. ,fi
- s. ..w . >
*}(J/Subsined c?ccimon valuco chall bo' prorated in accordanco with parn- !
graph N-301 . 2 of Nuclear Codo III and an shown bolov in Tnblo 1 . Tho rulo for determining rinizun cvorngo chall bo tho cano as t doscribed abovo for the 1G:n = 10 n cino, oncepting fcr substituting tho subsinod valuca. . i t TADLS_I '. i _S iz e o f Sp e_c_f r.c n Foot-Pcunds Mininun ! Avorago Incividual 10 by 7.5 cn 16.67 12.5 . 10 by 5.0 en 13.34 10 i 10 by 2.5 na G.67 5 ! f. The lateral o.xpansion in inches and the porcent ductilo fracture area for cach impact specinen, rogardlcss of sizo, shall be reportod for infor=atio-.
- t b
If during fabrication, tho pipo ic to bo subjectod to heat treat =ont ! in addition to mill hcat treatment, than all tost coupons shall ba heat troated by the mill in tno cano mannor. Rofor to paragraph 131 o f ANSI E31.1.0-1957 edition. When this additional heat treat = cat is required for tho tost coupona, it will bo sc npocified on the advnnced bills along uith tho heatlag rato and cooling rato and hold tino. > thic heat trentucnt vill bc 1125*F !05'?. f).Thoto14tcz.wrnturofor
's '! no Lon: te:atuant in ..c..cicr ;c w.il hcc; trontuon is required, - tho advanced x.11 vill ba nnr2cd "10 pcst void beat troat=cnt timo rce.uired o f t;at ccu ponc . }.
t
. ?
4 1 of 3
P.Cftontr:.cS 2FJ0'::R Dr5-YJ.TTU i.dr* Inir.ud Lichtin, Conpany A R ov . Doc . 2,1070 1971 g C5[y
*Shutcham, Nov York .h Rev. Feb.
J an. 15, 22, 1973
,hRev.
naderial idontificntion nnd carking shall bo in accordanco with (~)) paragraph 1G of ASME SA333-G9 and paragraph 19 of AS"3 SA530-G9. I.icatification ahall bo pernanont nurks mado with round noso (1/32" min., radius) ctcol die stamps and located 12" from tho and of each length of pipo'. . Pipo longth under 24" shall be marked about 3" from the end of each ' picco. '
?
For small diancter pipe which aro bundled, identification cay be , legibly stamped on a metal tag securoly attached to cach bundle as ~. r shipped. Pipo purchased specifically for this order shall bo identified with the following information:
- a. Manufacturor's Namo or Brand :
- b. Lottore "ASTU", Specification Number and Grado *
?
- c. Mcat Nv=bcr i
- d. Hot Finichod or Cold Drawn, Soamless or ifolded -
- o. Schedulo Numbor .
- f. Lottors "LT" and Temperaturo (LT30) '
]h> g. Contract 10003 (may be marked by tho supplicr at PDM plant)
M i> Tho natcrial furnished may bo subject to inspoction by PDM and/cr ko/ their agents and/or the ovnor or its authorinod reprosentativo.
- Certified copics of actual mill test reports of the physical and chemical requirements shall bo cubmitt.od The cortified documcats shall ; includo the folloring: -
- n. Type of stcol and heat treatment l b. Furnaco charts, carhod with hoat nu=ber and pipe t identification, or certified records showing time and
; tcaporature as taken Irom tho heat treating furnaco h zono control instruments. I.f not availablo, heat I treatacnt tenperaturos shall bo stated on cortified . mill tost roportu.
1
. - . ~
{. t i ' 1 l = 7
' s. . / p p
9 r 2 of'3 l{ l [ . . . ._
- emweate tra , swww ; . .Lc;.; . Island Lii:htic~ Compt.ny Rev. Doc. 2, 1970 , Rev. Jan. 22, 1971 .7 .3 A Rev. Feb. 15, 1973 iine copion of tbono cortified reporta nro to bo cont to: {$ ,5 lir. Georgo L. Dador I Pittsburgh-Dos L'oinou Stool Co=pany i ! Novillo Island Pittsburgh, Pa. 15225 .
Tolo. 412-331-3000 Ext. 249 j . Approved: i Dato - Signaturo 1 3 J . Projoct Engtnoor
*?s .? / / ; & ss- A-~ .
i 1 Uchding-i!ctallurr;y Dopt. 1
.i -
if .
- c. . .
)1- S DATERIA1. I!1 PMS SPECIFiCATiC') .} 1/lUST BE PURCHASED. FCG:J M1 APPROVED VEi130R j e .
1 s.
.1 i ) -
2 i
, '., 5 p .
1
.1 . . ~ ]
1 i
- O,
~
s - 9 ** I 1 3 of 3
..v..:; . .s . a m. ... ... u 2.., Coa.pa ny Ir4FO 0% (o's- - - . . - . ..
Shorcham, New 1*ork g or ( COLD PU NT SunDJC MTL:0'.hev. March 1G, 1971
- A)$dc inenh gfr
__) ,
- PLATE /ATERI AL SP2CIFICATION MS-10.7 jgj Carbon Manganenn Silicon Steel Plate G7 SA537-GD Gr. B Q u T (5/8" to 2" incl .) dh .
#' Plate shall conform to ASME SA537-69, Grade B, Quenched and Tc=pered . to the requirements of the 196G ASME Section VIII Boiler and Pressurc Vessel Code including 19G9 Winter Addenda and 1968 AS:.:3 Doiler and . Pressure Vessel Code Section III Nuclear Vessels Class B. In ,
addition, materials shall be tested by the drop-weight test in jps accordance with ASTM 2203 per Tabic 13 The drop weight tests shall represent cach plate as heat treated (both mill heat treatment and, wherp applicauAc, post viold heat treatment). All tests and inspections required by ASME SA537 and ASME SA20 shall be performed. Mechanical tests as required by .t.5"E SA537 and AS"E SA20 shall be performed in accordance with ASME SA370. If during fabrication, the material is to be ' subjected to heat trcatment in addition to mill heat treatment, then all test coupons shall be heat treated by the mill in the same nanner. t'h.cn this additional heat treatment is required for the test coupons, it will be so specified on the advanced billu along with the heating and cooling rate and hold time. The hold temperature for tais heat treatment will be G 1050 F -0 F +50*F. If no heat treatment in addition to mill heat treatment is required , the advanccc bill will ~s
.g, be marked "No post wc1d heat treatment tiac required of test coupons."
Material identification and marking shall bo in accordance with ASM2 SA20, Paragraph 9. As a minimum, the followlng permanent marking, round nosc or interrupted-dot die stamp having a minimum radius of 1/32" is required.
~
Material purchased specifically for this order shall be identified
~
with the following in two places not 1 css than 12 inches from the cdgo.except as noted in Item 2 below. (1) a. Ma'nufacturer's Name or Brand -
- b. Heat and Slab Number
, c. Specification Number, Grado and Condition jg (SA507-Gr. B Q S T .:aterial 1 1/4 and under 80,000 min.
tensile, over 1 1/4" to 2" 75,000 min. tensile MT) ^
- d. Contract Number 10093 (may be marked at.the mill
. or by PDM plant)
(2) Plates under 72" square, mark in one place approximately midway betwcon the conter and an' edge.
.m .
The material furnished may bc subject to inspection by PDM and/or their agents and/or tho owner or its authorined represcatative..
/. TABLE I e % g* Material 5/8" to 1 1/2" Inclusive, Minimum NDT - 40*F Over 1 1/2" to 2" Minimum NDT - 10*F 1 of 2 -
-2 ~. ~ ~' ~ ~ - *f. f. , ->
N __ PRocccs pipe H n_.
'P. .ENT M-lA \ .2 \ 9 , %-\%g(p ." oy## .. , i n o x w o ., . .s % 9 gg , I " ')- ':::
1 C.*PITOL PIPE t. STEEL PROJCTS, INC. " * * ^ " ' ' *
~.0. ; Ciw Line Avenuo "h @* / o[ '~/ .J Saia Cynwyd, Pa. 19004 'o Ah0 W*1f 3 - o.,, 18 February 1972 j c.. ,... c.... r... c.i.w. >.... o, ., n o.
E s,,,,,,..,,,, i
,,5.33 tJgzi F-13456 _AST!'-A-333 Gr. 6 and ASME-SA-333 Cr. 6 c.......n ud,',,,, 0.0. ?"" . i .o. a#ALL ,._ FCP. 110 .___ ___
c .s.w. P .,e N.. 86-3456-240-215 ,/ [ Pitts. Des-Moine. Loc.ti.a CHEMICAL AN ALY515 Stcel Company Hsat N.. .. P0r..i 6051670 5....i s.. C Mtl P S 51 CR HI MO Contract 4 10093
.17 1.22 017 014 .32 i 'K 2718 llk
- w. . . . .
Each !cngth of pipo ultrasonically inspected 100% in accordanco with the 1969 Sur.T.or Addenda c: tho ASv.2 Boiler til Para. N-324-3 using 5% por notch and found acceptablo. M' . l Y i o l,c y.. .onnT MECH AMCAL PROFERTIES iest T *g' ' ' XForx14 g ,,, O. l c itity ., e ,. cl N .. l i n...N.. (oc* Yiels r. Red. Moe,. Bend . .ng Erch Test F51 T. El.af" in. , A,e. Test 6 K 2718 Trans. 76,200 49,900 30.7 63.8 OK Forging Scr.! 9855Y Charpy lepact Test Values at -50*F.: 9355Z Ft.Lbs. lat. Exo. I Ductilo Fracturc 9856X 50.0 .ub9 ton 9856Y 78.0 055 25 9357Y 42.0 031 10 l 9357Z Fol lo.ti r. test cerfomed as Charpy Impact Test Values at -30 F.: specifici and fcur.c acccatabic.
- Stress Rolieved at 1125 F. +25* l-l/2 hrs. Furnace .-:esT.
A. Tensilo Test (Transverso) eno ccoling rate above 60T 7. 50*F. per hour. C. Charpy Tcr.ccrature (LCngitudinal)?t.Lbs. Lat. Exa. $ Cuctile Fracture C. Ir.cact Test Values. '212.0 .v/4 100a 192.0 083 100 D. Flatter.ing Test Laterd61 Expansion 196.0 08+ 100 E. F. Percent Ducti10 n i o. 'e c T"' E?ch le: ath of oiro hverostaTically tested at 2133 psi for 5 sec. and fcund ccc :1
.-s e s 7, e. ,e a e:
(:) 17'.,7 F., hold 2 hrs. at ter.p. Air cool. (2) 1375*F., told 6 hrs. at Te~a. Ai r ccol . [ ~. .; , c t . , noio 2 hrs.o? Tct. . Air ccol.
, ,- _. *,.ru***
e* * , f' t . O Ces,e ty ,,*ebe 9.tib f u . c 6. ',C J/ e t i a' 'Cu " 4 . ** N *' Febreary 1972 'h * **ma r- '/ 16.n e.ffM':-.-.+up /. w LL ./ I f . ;. =
...., w M.. .n . . .y ,,. - .. n. . ./A% . , . a . .o . ,
G.A.iC ,J. , W_", y ..yy p .; e in :q f.3r n:ms Ccu 'y.p. 1
..am.......- .. ..m 3;.r.s 2, 4 1. m =
.. .. e ,. ..3.j,.>. 'i.Wd.n0 0 $ E r .e . . . . '. .. s . > A..;.} .- - 1.J A lu.6 ba.:. L;.%v r!.. . .
S.7 gat.o,%.s t.. . .2..,,.. . . . . .w l . H , PE;;;;A 15225 .
' ~3 ~'
Pcur %- t A Pa_ocmss A pc Mn.. G:x/2^c.~. .
,%to.#9 PIT *.*30LP.GH DES-MOIt!ES STEEL COMPAi Y b W IEVILLE ISLAr;D
- SAL'~-S O: DER FITTS3U3GH, PEfJ:JA 15225 7,
od dS 2o 9 os- J SAfr 2-16-72 11 14,0N O. JILL ......... ...,.. .,. ... ........ ,u........... :..,......... i,e...,w................, ,2 605470 i TRX Ril-5090 l H41284-R:1 T- ,S l t- P,,.m - .. ,... ...........,...u.. ,p m .,. ..t. .. ...
- SEE BELO'J l EXEMPT I .J ' i
__L 1/2- 10-3 0 . t ._P A.. _._ L ____ __ _.2.,,,.u _ _ _ _ _.
. , . . , ........,,.,...u.,.....u. ,,u.,.u.... ...u... u.....
'3 2 PCS j 24 S/SO SA333 GR 6 & PDM l.. i X 15, 4 3/4 CUT SPECIFICATI0!! MS9.4 PE.'J T X- 1 A X-ID
...,u.........,...........u, ..u...u.... ...u. ... ..u..... . . .n . . . . a i
4 ; 2 PCS i 24S/80 SA333 GR 6 & PDM .X 16' 10 1/2~ CUT SPECIFICATI0!; MS9.4 X-IB X-IC
.... a.. ......... ..u.u....u, .. u ..u .... ...u ..,.., .u..... ....,..a
' SHI PJ-._ '2 72 : SUR E - t e es. 3. . . . . , v . w . , ses..s......u. s .... ...e.. . . . . . .w . e t .u...., ..o..o,,.4. l i
-0 . . .. .... .. .. .....,
S
.u, c ., . . . , . . . . .... .: .. . . . , . . . . . :,u,:... . . . . . . . -,u, . < - . . . . . , ~ . . .
j ] l
' 14 _ h 'i/A K 2718 !
1610h K 2718 ! !i ;
, i i i J j "
14 h h& " i 16 10h l N i l
. 1 :
l l l s l ! I g j ,, I, l II i. i l . l l-i l ' f .
; i i . 1 i l 1 f t . 'l1, l l , . l l i . ; i. , ! l I ! .
l fIl g 1 i; . 9 e ; I.l l . i. l d
,3 I ! ) i I s>w )d .
9 I i
'l '1 l
6 9 l i
.,' y ;~r.-- . - - ^-. - _ _ - - . - - . _ = . - - _ _ . _ . . . . . . . . - - = . .. . c. L .
{0 6 201X 3 l33l9 ITEM q !l h aro I.......-... :.u. l........., 9_, .- - .., c..cm es h lo s 3, .
*~
bk [ g'./ / 3/ U fJ.T i'/.I't] ,'? q g ;2.cGet Pips sTt&,..i., [L uJU.Wj!,h,9,iP 9. ~ ' " " " "' "" ' ~c.
$ CAPITOL P!PE & STEEL PROCUCTs FEE ,2%2' ,' ,{ ",{.,g k'.izoueIo$.IuME$ rroo, .), 301 City Lir.o Avonuo /. . 'Ini } () $ M O-Q Bala Cynwyd, Pa. 19004 j'.]\ b 3 6 3 [7 I ' ' # 7 " Mlq.
o \... c ... . w.. . . >. 1 13 July 1971 s
./_221_3 1. \5 6, " mt ...
c....-.. c.... u.. c . . >, . s . . . . o . . . u . . . < . . . ....
..3,.~....... /
F-13238 ASME-S A 333 Gr.' 6' and' ASTM-A 333 Gr. 6 56505-00N - o,.........
.' 0.0.
18" m I.D. ,. ._ _ a*A { (SCh 120 prems c.i .e. e... u.. 06-1800-1550-30 Materin't Bored to 18" Schedttl.e r~ 100)
/ - P l'l't a bU r g h Di:s N.o i n'?
t cn cmc At. m Au sis f n ,.. u.. I t.. ..... ca us uo Steel Co. c us e s si I s .. .i n. . PO r/ 605470 C 0 # 1
- Contract #10093 CCC; J 3356 .21 1.09 .016 009 .22 Q ./ e '.*q C' /J/,
U.T. perfomed by P. Sexton U.T. Prccedure PU-8 All Pipo ultrasonically inspected 100". and found accootablo por ASME Boiler Prossuro Vossal Codo Scciion ili Paro. N-324. L I LCO P.O. 31010ov REFERENCE
MECH ANIC AL PRCPERTIES <~
r ,..ne.e f Test T;;,"- o n. ..
. 2 *Ye.id n...
i .. . . , n . .
% Elorio. t. R e d. M.c .o 8.aJ s .,.n g , e t. .. j .oC.
- t. Psi an. gis A,.. Etch T. e T .s, j
44,700 33.0 64.7 OK 5 J 3356 Trans. 71,100 54,900 33.1 64.7 OK Trans. 72,400 V-Notch impact Tost at -20 F. Average
.. FT. L:s.
Ft.Lbr.. Latoral Exocnsion' % Ouctile Fracturo 7 9.0 032 Ds Forg. Sor.# 5708 050 30 49.0 a709 53.0 38.0 034 5 8710 P711 100.0 .0B0 40 8712 87.0 86.0 070 35
- 75.0 061 30 l Folic.ilag test perforrod as speciflod.and found acceptablo. - - '!- ~ - "
A. Transverse Tensile W'# -- l 8. Irt. pact Test at -20*F. 7[, A stcMu bu 4 - ; l '2 3 - 7 / - C. Fictrcning Tost
,........eT... Each lenoth of pipo hycrosf67tcst1y testec at 2600 psi- end found acceptable.
I s...T........ hom.a l i zo & Tempo r 1700*F., hold 4 hrs.ct tcap. Fan ccol . 1300' F. , ho l d 6 b rs . at temp . Ai r cco l . t \ I .
.........,s................ io,..,..........,,...,......... .... ....... ' ' ' '" " "'s e r - .
63Tn 0.r .;u17 197i I .. b,...... .. w.s.scWA * ' om
....li......i...<..... O..a..j.
r.- now, rou c sa a,a 1:e ei.riis C6an:7. I*'il Ca rCgeeggge eff/ # ,
. . . ... .m m.,m g mTs4 [
THCu ac H. A pe 3 C i t J ag
... .. _ . ~ . .. . , _ _ _ ,
l') , . . . . . . . , . . . incorporaiod
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DENT 'Z ~2.A P20ctss Pipc art. 'S 8 + #b 7 FEG h KTCR. CMARP'l IM?ACT TEST RESULTS foa Capitol Pipe & Steel Productg, Inc'. DATE _7 71 I A3 No. 745-71 . ORDER NO. L 57470-02 u47cafat _1_8'_' S/120 ASTM /ASME SA333 Gr 6, Heat J3356 INDENTlilCATiOH Coupon PV TES: TENP. ~30 Y SPECIMEN T(PE Cimrpy V-Notch . SPLCIMEN SIZE 10mm x 10mm HEAT TREATMENT 8 PO.ss Relieved 1125"F for 1. 5 hrs- licating & Cooling Raw 50VFg# *
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CONN.ENTS TAG: PDM 005470 HN 5000 H36256 Copacity of impact enachine is 2M foot pounds with a striking velocity of 16.8 fact por second. IDENTlitCATION IM?ACT VALUE Ur !bs.) % SUEAR LATERAL EXP (ir ) PV 20.0 25 017 PV 24. 0 29 023 PV 16.0 25 .016
.. Piitsburgh Des N.3 1n st e' C-Above material bored to 18" Schedule 100 POS 605.'7b .
Contr :i31CC?! CCO'
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METALLON, INCORPORATED
- s. ' SM4h ( . '1.Tf g fM
, Donald R. McGehec, P. E.
0; 2524 Sutherland
. Houston, Texas 77023 .
713 923 7761
,___. _- .s- - -
_ u- . 19F0 00Ly - i e, e , February 15,'1973-POM Contract 10093 PRocc% P)PG WTMtIR
$ Long isiand Light ing Compan'/ Nench "pg1 $p Rev. Ap r i 1 ;12, 1973 ~
Shoreham, New York
' }ggg g f. Q MATERIAL _SPFCIFlCAT10N MS-9.4.1~
s Seamless and welded Pipe for Low Temperature Service. m X- i n . y-2A. y-28. Process Pine for Penet rat ion <; Y- 1 A . y_- _1 8 . y- i c .
>-(2. v-16. x-20A. y-20s r,x-Lo -
x-3. x-4 x-S. x-6A. X-68. X-11 . Pipe shalI conform to ASME SA333~ Grade.6 as given in th ASME'Boi1er and Pressure Vessel Code, Section i1,." Material Specifications-Part A . Ferrous," 1968 Edition, including summer 1969 Addenda. All material shall be fine grained, normalized and'shall meet the requirements of the ASME Eoiler and Pressure Vessel 5 Code, Section ill,," Nuclear Vessels," 1968 Edition, including Summer 1969' Addenda, in addition, pipe material shall also meet the requi rementr 'of the Ameri'can " Nuclear National Star.dard Code f or Pressure Pip ing, ANSI- 831.7 Po.ver Piping," 1969 Edition, for Class l ' p i p i n g ."""1 All tests and inspections requi red by ASME SA333, SA530, Nuclear Code Section 111 and ANSI B31.7 shall be performed. Me'chanical tests required by SA333 and SA530 shal1 be performed in accordance - with ASME SA3 70. , All pipe shall be ultrasonically examined in accordance'with the requ i rement s of AWST~B'3T.T parag raph '1-724.1.1. Personnel perform-ing ultrasonic examination shall be qualified to recommended y y p ract i ce SN,T-T C- 1 A. _ Longitudinal Charpy_V-Notch Impact test s, shall be made ~ in accord.ance with paragraph N-330 of Nuclear Code ' Section 111 and SA370.. Er a test t emperatu re of minus 30
- F. Average value for a set of full size specimens (10 x 10mm) shal l be 20 f oot pounds minimum, with only one specimen of a set 'of three Thexother permitted to twobeoless of the. set th'an,20 plust-but not less than 15 f oot pounds.
be 20 foot pounds or over.' N _ c, , Subsized specimen values shall be prorated in 'accordance with paF2- ' graph N-331.2 of Nuclear Code iII and as shown-below in Table 1. ' The rule f or determining minimum average shall be the ~same as described above for the 10mm x 10mm size, except'ing for substitut ing
. the subsized values. y ,
TABLE I - . s ~, Foot-Pounds Minimu, Size of Saecimen Average Indivicual-10 oy 7. 5 mm , 12.5 10 by 5.0 mm 16.67 - 13.34 i' 10 10 .by 2. 5 mm 6.67 5 ; O The latera; expansion in inches sr.d the percent ductile fracture i d area for each impact specimen, regardless of size, shall be reported n W for information. . ,
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_: 'POM Contract 10093 (MS-9.4.1) February 15, 1973 f ' x CLong Islcnd' Lighting Company Rev. April 12, 1973 Shoreham, New York 1,
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(])! ' If during fabrication, the pipe is to be subj ected to heat treatment in addit ion to mill heat treatment, then all test coupons shall be
' heat -t reat ed by the mil l in the scme manner. Refer to paragraph I-731 ~of ANSI B31. 7- 1969 edition. When this additional heat treatment is . , required _for the test coupons, it will be so specified on the advanced Tbills.along with the heating rate and cooling rate and hold time.
The hold temperature for this heat t reatment will be 1125*F 125*F.
, if no heat treatment in addition ta mill heat treatment is required, the advanced bill will be marked "No post weld heat treatment time required of test coupons." Post weld heat treatment of test coupons is required f or the process piping of penetrations X-1 A, X-1B, X-lC, f> X- 10, X- 2 A , X-28, X-5, X-6A, X-6 8, . X- 12 ; X-20A and X-203.
m Material identification and marking shall be in accordance with p'Bragraph 16 of ASME SA333 and paragrcph 19 of ASME SA530. ' Identification shall be permanent marks madh with round nose (1/32" min. rad i u s) steel die stamps and located 12" f ran the end of each (f - length of pipe. Pipe length under 24" shall be marked about 3" from the end of each
. piece.
For small diameter pipe which are bundled, identification may be legibly stamped on a metal tag securely attached to each bundle as shipped. Pipe purchased specifically for this order shall be identified with the following information:
- a. Manufacturer's Name or Brand
- b. Letters " ASTM", Specification Number and Grade
- c. Heat Number
- d. Hot Finished or Cold Drawn, Seamless or Welded
- e. Schedule Number
! f. Letters "LT" and Temperature (LT30)
- g. Ultrasonic In spect ion Let ters UT
- h. Contract 10093 (may be marked by the supplier at PDM plant) .
The material f urni shed may be subj ect to inspection by PDM and/or i their agent s and/or t he owner or its authorized representative.
- '.cterial certification and reports shall be in accordance with sj Paragraph l-723.1.2 of B31.7 and Paragraph 18 of SA530 The test 2 of 3 .
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. *PD:t Contract 100'J3 (MS-9.4.1 ) Feb ra.: y 15, l'f/3 .- Long Island Lighting Company Rev. A,aril 12, 1973 Shoreham, New York -
dp 7 4' 7 )N) report shall include certified reports of the actual results of all required chemical analyses, mechanical test s and examinat ions. The certified documents sha.ll include the follcwing:
- a. Type of steel and heat treatment
- b. Furnace charts, marked with heat number and pipe identif icat ion, or cert ified records showing t ime 'and temperature as taken f rom the heat. treat ing f urnace
- zone control instruments. If not available, heat treatment temperatures shall be stated on certified mill test reports.
Ultrasonic Information c.
- 1. UT procedure and operators qualifications meeting requirements of ANSI B31.7.
- 2. Certification that pipe meets UT requirements of Paragraph l-724.1.1 of ANSI B31.7.
- 3. Record cf UT defects, if any found.
The supplier shall furnish nine (9) copies of these cert ified reports to PDM. Mrs. Ann Wiese Pit t sburgh-Des Moines Steel Company 6 Neville island Pittsburgh, Pa. 15225 Telephone: 412-331-3000 Ext.: 249 PDM (Pgh Purchasing) is to send six (6) copies of these certified reports to: Stone and Webster Engineering Corporation P.O. Box 2325 Boston, Massachusetts 02107 Attention: Mr. W. C. Shepherd Telephone: 617-434-7224 Approved: Sign G s DateEk 23 Sign. b. . I WA Date 2/FS/73 []) Weloing-Metailurgy Dept. Proj ect Engineer s. 3 of 3 LIATEmA1. IN TH!S E?ECIFICATIOM T CE PUT C.:l SED FRC.'.i A.1 Ai430l.'ID 5.'E0005
II.B.2 Shielding Review Computer codes LILCO Position
-1. QAD-MOD: This Stone & Webster in-house shielding computer code was used to calculate dose rates-from-components such as the RBSVS filters. lit is a point-kernel gamma ray shielding code. Gamma ray dose rates, energy dispositions, and uncollided fluxes may also be calculated using this model-.
- 2. ANISN "D": This Stone & Webster in-house shielding computer code was used to calculate dose rates from. pipes carrying suppression pool water. This is a multigroup one-dimensional discrete ordinates transport shic1 ding code.
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.~ ' Revised Response - 6/81 II.K.3.13 Separation of HPCI and RCIC System Initiation Levels - Analysis and Implementation NRC Position Currently, the reactor core isolation cooling (RCIC) system and the high pressure coolant injection (HPCI) system both initiate on the same low water level signal and both isolate on the same high water level signal. The HPCI system will restart on low water level but the RCIC system will not. The RCIC system is a low-flow system when compared to the HPCI system. The initiation levels of the HPCI and RCIC system should be separated so that the RCIC system initiates at a higher water level than the HPCI system. Further, the initiation logic of the RCIC system-should be modified so that the RCIC system will restart on low water level. These changes have the potential to reduce the number'of challenges to the HPCI system and could result in less stress on the vessel from cold water injection. Analyses should be per-formed to evaluate these changes. The analyses should be submitted to the NRC staff and changes should be implemented if justified by the analyscs. BWR Owners' Group Discussion This item has been broken down into two parts for consideration by the Owners' Group as follows:
- 1. II.K.3.13A - Separation of Initiation Water Levels of HPCI and RCIC
- 2. II.K.3.13B - RCIC System Automatic Reset II.K.3.13A - There are two classes of transients which can cause RCIC and UPCI initiation. One occurs'when the coolant inventory is being lost slowly due to decay heat *-
steam generation. Manual operator action has been demonstrated as being successful in avoiding automatic HPCI initiation on low water level. The other class-occurs when coolant inventory loss is rapid. In this type of transient, it has been demonstrated that
- i automatic HPCI initiation cannot be avoided even if the RCIC setpoint were raised to the normal wateE' level.
Lowering of the HPCI setpoint would be required for these events. This is clearly not de,sirable from a safety consideration.- II.K.3.13B - Allowance of an automatic restart capability to RCIC following trip at high water level would con-tribute to improved system reliability and could be accom-plished'without adverse effect on system function and-plant safety.
o BWR Owners' Group Implementation Criteria II.K.3.13A - Separation of Initiation Levels - Separation of HPCI and RCIC low water level initiation setpoints has been shown to provide negligible benefit as a means of reducing thermal cycles. Furthermore, the design basis for thermal fatigue usage of the reactor vessel and com-ponents presently includes a sufficient number of HPCI and RCIC injections. In addition, any changes to the present setpoints of RCIC and/or HPCI would lessen the existing margin for assurance of adequate core cooling. No change, is there-fore, recommended. II.K.3.13B - RCIC System Automatic Roset - RCIC system termination is presently accomplished by closure of the turbine trip valve. Several options are available to accomplish automatic restart capability as follows:
- 1. Automate the reopening of the turbine trip valve following the high vessel level trip.
- 2. Automate closure of the steam supply valve in lieu of the turbine trip valve on high vessel level.
- 3. On high vessel level, reroute the RCIC pump flow to the condensate storage tank (if suction is from this source) or close the steam supply valve (if suction is from the suppression pool).
Option 2 has been recommended because it minimizes the modification required to the logic circuitry and accom-plishes the intended function-of automatic reset. LILCO Position LILCO endorses the recommendation of the BWR Owners' Group to - implement option 2 above and modify the existing circuitry to l provide automatic restart capability for the RCIC system follow-i ing high water level trip. Accordingly, the motor-operated RCIC turbine steam supply valve will terminate system operation at high water level by automati-cally closing. This valve will automatically open if the water level again reaches the low level initiation point, thus re- ! initiating system operation. An effort is currently underway to I qualify the reset logic equipment and, to the extent possible, it will be installed prior to fuel load. Complete implementation, however, may not be accomplished until after fuel load. No change will be made to the existing water level initiation set points for RCIC and HPCI. l -
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. t Revised Rnsponse - 6/81 II.K.3.15 Modify Break Detection Logic to Prevent Spurious Isolation of HPCI and RCIC Systems NRC Position The HPCI and RCIC systems use differential pressure sensors on elbow taps in the steam lines to their turbine drives to detect and isolate pipe breaks in the systems. The pipe break detection circuitry has resulted in spurious isolation of the HPCI and RCIC systems due to the pressure spike which accompanies startup of the systems. The pipe break decection circuitry should be modi-fied so that pressure spikes resulting from HPCI and RCIC system initiation will not cause inadvertent system isolation.
BWR Owners' Group Discuss.4 0_n The BWR Owners' Group have reviewed this issue and agree that the current control logic could contribute to an unnecessary degrad-ation of HPCI/RCIC System availability. BWR Owners' Group Implementation Criteria Several design changes are capable of eliminating the unnecessary ' system isolations that can occur as a result of-short term flow peaks in steam supply lines. These changes include the addition of a time delay to the flow sensing isolation logic, the addition of snubber devices to the elbow tap instrument lines, raising the nominal setpoint, or addition of small diameter bypasses around the steam supply valves. The BWR Owners' Group believe the addi-tion of a time delay relay is the best solution because it directly addresses the problem of spurious isolation. Furthermore, this change does not invalidate the design basis safety evaluation of this equipment, thus precluding the need to repeat any safety analyses. LILCO Position LILCO endorses the recommendation of the BWR Owners' Group to adopt a timc delay relay scheme to eliminate spurious isolation of the steam supply line isolation valves during the system start sequence. Consistent with the availability of qualified equipment, implementation will be completed prior to fuel load. e
.- Revised Response - 6/81 II.K.3.17 Report On Outage of ECC Systems-Licensee Report and Proposed Technical Specification Changes NRC Position Several components of the emergency core-cooling (ECC) systems are permitted by technical specifications to have substantial outage times (e.g., 72 hours for one diesel generator; 14 days for the HPCI system). In addition, there are no cumulative outage time limitations for-ECC systems. Licensees should submit -
a report detailing outage dates and lengths of outages for all ECC systems for the last 5 years of operation. The report should also include the causes of the outages (i.e., controller failure, spurious isolation). The present technical specifications contain limits cn1 allowable outage times for ECC systems and components. However, there are no cumulative outage time limitations on these same systems. It is possible that ECC equipment could meet present technical speci-fication requirements but have a high unavailability because of frequent outages within the .llowable technical specifications. The licensees should submit a report detailing outage dates and length of outages for all ECC systems for the last 5 years of operation, including causes of the outages. This report will provide the staff with a quantification of historical unreliab-ility due to test and maintenance outages, which will be used to determine if a need exists for cumulative outage requirements in the technical specifications. Based on the above guidance and clarification, a detailed report should be submitted. The report should contain (a) outage dates and duration of outages; (b) cause of the outage; (c) ECC systems or components involved in the outage; and (d) corrective action taken. Test and maintenance outages should be included in the above listings which are to cover the last 5 years of operation. The licensee should propose changes to improve the availability of ECC equipment, if needed. Appl _ cant for an operating license shall establish a plan to meet these requirements. . LILCO Position Since Shoreham is not yet operational, LILCO does not have any applicable ECC outage information to contribute to proposing changes which improve the availability of ECC equipment. During the first five years of operation, LILCO will include a detailed summary addressing the information requested above, in its annual operating report to the NRC. This reporting-mechanism will supple-ment the normal Shoreham Licensee Reporting System. This program will be established 6 months prior to fuel load.
4 II.K.3.22 RCIC Suction Auto Transfer NRC Question Does RCIC logic currently transfer suction from the Condensate Storage Tank to the Suppression Pool upon hf'h Suppression Pool water level? LILCO Response-RCIC logic does not currently transfer suction from the Condensate
. Storage Tank to the Suppression Pool upon high' Suppression Pool water level, nor do any plans exist for incorporating such logic, s
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