ML20033G674
| ML20033G674 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/30/1990 |
| From: | Walt T PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20033G675 | List: |
| References | |
| TAC-72894, NUDOCS 9004110160 | |
| Download: ML20033G674 (26) | |
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March 30, 1990 Trojan Nuclear Plant Docket 50-344 License NPF-1 g
1 U.S. Nuclear Regulatory Commission l
Attn Document Control Desk Washington DC 20555 i
Dear Sir:
Responso Concerni 4g the Review of the " Risk-Based Inspection Guide for the Trojan Nuclear Plant" (TAC No. 72894)
In a letter dated December 22, 1989, the Nuclear Regulatory Commission l
requested Portland General Electric Company to provide additional information on six items provided as part of the " Risk-Based Inspection l
Cuide (RIG) for the Trojan Nuclear Plant", and to review and comment on the draft ver'sion of the RIG.
The attachments to this letter provide tho requested information and comments on the draft. RIG.
Sincerely, r
L 5
l T. D. Walt Acting Vice President, Nuclear Attachments c:
Mr. John B. Martin Regional Administrator, Region V f
U.S. Nuclear Regulatory Commission Mr. David Stewart-Smith State of Oregon Department of Energy Mr. R. C. Barr 1
j NRC Resident Inspector Trojan Nucioar Plant yma age f
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121 S W Salmon Strwt Podia % Oeinn 97201
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l Traj:n Nucic r Plcnt Document Contr:1 Desk j
Docket 50-344 March 30, 1990 i
License NPF-1 Page 1 of 3 J
PORTLAND GENERAL FLECTRIC COMPANY RESPONSE CONCERNING THE REVIEW OF THE " RISK-BASED i
INSEECTION GUIDE FOR THE TROJAN NECLEAR PLANT" (TAC NO. 72894)
I EACEGROUND In a letter dated April 1, 1989, Portland General Electric Company (PGE) provided Trojan plant specific information to the Nuclear Regulatory Commission (NRC) to support the " Risk-Based Inspection Guide for the Trojan Nuclear Plant".
Brookhaven bational Laboratory has performed the analysis and the NRC provided the Draft Report to PGE (in a letter dated December 22, 1989) for comments and a request for additional information on six items. The PGE response for each item of additional information is provided.
NRC_ REQUEST NO._,1 Whether the air supply to the pressurizer power-operated relief valves (PORVs) is backed by nitrogen bottles or air accumulators.
PGE Resp 2nRR The PORVs are backed by four Seismic Category I air accumulators (T-233A, T233B, T-2330. T-233D). These are shown on Final Safety Analysis Report (FSAR) Figure 5.1-1 B, " Reactor Coolant System",
which is attached (Attachment 3).
NRC_ REQUEST NO. 2 The number of PORV actuations that the backup supply is expected to support.
EGE_Enapanne The two air accumulators to each pressurizer PORV are capable of a combined total of 32 cycles. The basis for this is attached (Attachment 3) and is from the Reactor Coolant System Design Basis Document.
NRC_REQUESLNQ._3 The number of PORVs that would be required to open to achieve sufficient core cooling in the " feed and bleed" mode.
EGE_Responas l
l Two pressurizer PORVs are required during the " feed and bleed" mode.
Emergency Instruction (EI)-0, " Reactor Trip, Safety Injection, and Diagnosis", Step 12 on Page 7 of 18, references Functional Restoration (FR)-H.1, " Response to Loss of Secondary Heat Sink".
l Step 14 of FR-H.1 on Page 11 of 22 references operation of both PORVs. Partial copies of both EI-0 and FR-H.1 are attached (Attachment 3).
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l Trojan Nuclear Plant Document Control Desk Docket 50-344 March 30, 1990 License NPF-1 Page 2 of 3 1
i NRC_REQUEEI_ Hat _h i
The success criteria for the PORVs/ Safety Relief Valves (SRVs) during anticipated transient without scram (ATWS) events.
EGE_ Response The success criteria during an ATWS is all five pressurizer relief valves, two out of two PORVs and three out of three SRVs.
This is shown in FSAR Table 15.8-1, "ATWT Analysis Model Summaries", and is attached (Attachment 3).
NRC_REQUESI_NO _5 The specific locations (e.g., Containment elevations) of the SRVs PORVs, and block valves.
EGE_ Response These valves are showa in an isometric view in the attached (Attachment 3) FSAR Figure 3.6-22, " Pressurizer Safety and Relief Lines (RC-2501R-8 and RC-2501R-12)". The Containment elevations are as follows:
PSV-8010A 119 ft 3 inches PSV-8010B 119 ft 3 inches PSV-80100 119 ft 3 inches E0AVs PCV-455A 127 ft 0 inches PCV-456 127 ft 0 inches Block V_glygg MO-8000A 127 ft 0 inches M0-8000B 127 ft 0 inches
- Mean Sea Level
Trojan Nuclear Plant Document Control Desk Docket 50-344 March 30, 1990 License NPF-1 Page.3 of 3 NRC REQUEEI_HQi_b The PORV control power supply breaker designations and locations.
FSE_ Response The electrical drawing for PCV-455A is Drawing No. E-546, " Schematic Diagram Reactor Coolant System Valves", and is attached (Attachment 3).
Power supply is 125 VDC, Panel D10 Breaker 72-1016, Control Building Train A switchgear room.
The electrical drawing for PCV-456 is Drawing No. E-548A and is attached. Power supply is 125 VDC, Panel D20 Breaker 72-2016, Control Building Train B'switchgear rvom.
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CFM/k1h 4346W.0390
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Trojan Nuclear Plant Document Control Desk Docket 50-344 March 30, 1990 License NPF-1 Page 1 of 1 PORTLAND GENERAL ELECTRIC COMPANY COMMENTS ON " RISK-BASED INSPECTION GUIDE FOR THE TROJAN NUCLEAR _ELANT". DRAFT OF _ TR-A-3875-T2B. REY. O. DECDiBER 1989 General _foaments 1.
There r*re systems in the document that are HQI Trojan specific.
For example, Trojan does not identify a "High Pressure Service Water" system as shown in Table 2, Table A.1-1, and Figure A.1-1.
The
" Emergency Safeguards System (ESS)" as shown in Table 2 for Trojan is the Emergency Safeguards Features Actuation System (ESFAS). Trojan does not identify a " Power Conversion System (PCS)" as shown in Table 2.
Also, the high head injection at Trojan is the centrifugal charging pumps (CCPs), the intermediate head injection is from safety injection (SI) pumps and accumulators, and the low head injection is the residual heat removal (RHR) pumps. This document uses just high head and low head injection modes.
2.
The introduction states that the inspection guidance will be periodically revised, but does not identify who will perform this revision.
Editorial Commenia 1.
On Page 2 and other places throughout the document, the acronyms LHR and LPR are used for the same thing; likewise for HHR and HPR. These should be clarified as to their meaning. Also, these are not Trojan specific acronyms.
2.
Page 10 uses the acronym USAR. This has been changed to be FSAR (Final Safety Analysis Report).
This acronym needs to be identified in the text.
3.
On Page 11, there is reference to a motor-driven auxiliary feedwater (AFW) pump. Trojan does have a motor-driven AFW pump, but it is not safety-related. Trojan has two safety-related AFW pumps, one turbine-driven and one diesel-driven.
It should be clarified as to what is intended here.
4.
On Page 12, there is no mention of charging pumps in Footnote 5 or 6.
5.
On Page 13. Table AX-1 should be clarified to indicate that the "X" is the number listed in Table 2 on Page 12.
6.
On Page A-16, the "Ncrmal/ Emergency AC Power System" is misplaced and not consistent with the other title blocks.
7.
On Page A-67, what do the
"?" marks mean?
CFM/k1h/4346W.0390
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1 License NFP-1 i
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Trojan Nuclear Plant Document Control Desk l
Docket 50-31.4 March 30, 1990 i
ge g,, ppp.3 Page 2 of 25 59MS4.
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4,9.l.6 YT-4 fl A /N YT-o f f A /S. YT-a f 3 A tt. and YT-4 74 A/s cont lnuous Vibra
- L on Moelters a
toch RCp Le equlpted with two vibration plekups mounted at the top of the motor support stand to measure redLal vibrations of the pump. The signals are taken to a sult1.pnint selector switch mounted outside the teatter Contalnment. A perteble vlbratLon meter is connected to this seletter switch, and so the signal f rom any one plekup may be monitored at one LLme. It Le recommended that the vlbration levels of the RCps be monitored periodically or whenever an abnormal condLtton is suspected. There is no requirement fer continuous monitoring or recording.
For further detallt about the continuous vlbretton monLtors, soo Subeestion 4.3.4.
e.10 evampatAsunt ettttCAT!Wo EYSTEM
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Section 4.10 provides the design bases and configuration for the Overpressure kitigating System (OMS). This information was obtained free the following sorrespondenset (1) Westinghouse Letter to PCs, Pos.87 304, Low feeperature Overpressure Protection Systee' (LTopS) teanalysis, Janvery 23, 1947.
(2) Westlnshouse Letter to PGt, POR 87.$16, Low temperature overpressure Protection System (LTop8) Setpoint Analysts Under High Mass Injection CondLttons. February 12, 1987 (4) Pct Letter to the Nuclear Regulatory ConadesLon (IrtC), C. Coodwin Jr. to A. Schweneer. Overpressure Mitigating System. April 8,1977 (3) PCE Letter to the ifRC, C. Coodwin Jr. to A. Schwencer July 21, 1977.
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l Trojan Nuclear Plant Document Control Desk i Docket 50-344 March 30, 1990 I
License NFP-1 I
Page 3 of 25
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the ons must be designed to prevent the acs pressure from esseeding the ilmLts stated in 10 cra so appendix c.
It also must be designed to meet the I
requirements of Institute of stectrical and stectrentes tagineers (tter) tie, as follsws:
(1) Separate power sources must be provLded for each low-pressure circuit.
(2) The low-pressure etrcutte must be indapandent and redundant, to satisfy the single.f allure erlteria.
(3) Equipment quattty and qualif tcotton must be consistent wLth that of the original Rc8 componenps.
(4) system inputs must be derived from signals,that are a direst meteure of the desired variable.
(3) The system saast be capable of being tested and callbrated.
t Three Trojan specific mass input everpressure analyses were performed by means of the RETRAar code to determine the specLfic poRV setpolnts and design
"c'riterla for the OMS (see letter mentioned above, PGt to the WRc, July 21, 1977). A Trojen 81 pump startup incident was anatyred to deterstne the maximum predicted Rc8 pressure overshoot for mass input incidents, since this pump his the highest flow delivery. An incident of a Trojan tentrifugal pu.mp chargLng trtth letdown isolation was analysed to deterstne the criteria for p0RV cycling that was used in the design of the air weeumulators. This purep has the highest flow delivery for sttuatlans Ln whleh a loss of instrument att causes both letdnin isolation and overpressure. The Trojan positive dLoplacement purp charging with letdown isolattan was analysed to deterstne the earlmum prodleted Rc3 pressure undershnot for mess input incidents, since this pump has the lowest flow delivery.
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1 Trojan Nuclear Plant Document Control Desk j
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Docket 50-344 March 30, 1990 License NFP-1 At t achment 3 Page 4 of 25
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i The two Trojan PORVs were determined to have dlf ferent opening and closing characteristles. PCV.aS6 la ennsidered the f astest acttng of the two PORVs, conversely PCV.453A Le considered the stuwest acting. In the three RETRAN t
analyses, the appropriate PORY was modeled to find out which would yletd the most conservative results. The analyses determlned that the eetpelnt for PCV 4S$ A (slow PORV) should be 440 pslg, and that the setpolat for PCV.454 (fast PORV) should be 490 pels.
Por the Trojan centrifugal pump charging with letdown 1selstion incident, the fastest acting PORY (PCV 456) was assumed to be actuated. This action results in a minimue PORV sycle time of 29.1 seconds, and this information forms the
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basis for sizing the air accumulators in the cms. The air accumulators were designed to assure that 32 PORY cycles can be accomplished during the 10 stnutes during whleh credLt for operator action cannet be taken. CalculatLon I
TM 011 has determined that a alntmum,yolume of 7.52 f t is necessary to meet these regulroments.
g.10.2 COWFICURATf0W The OM81s designed as two independant, redundant, thannels that actuate the re11ef valves. Each channel constate of the followings (1) A pressure transmitter (2) A pressure alarm b1 stable and annunctator
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(3) A pressure actuating blstable
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(4) A mode selector switch and indication lights (5) A circultry activation annunciator (6) Valve actuation circuitry 1
(7) A relief valve
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Trojan Nuclear Plant Document Control Desk 8 i
Docket 50-344 March 30, 1990 I
l License NFP-1 j
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t setamic cleos I air accumulators have been instatted for each pony operator to ensure that the ponys have en one supply for proper operation ef ter a setemte event. The occumulators were f abricated from 4 f t sections of t2-in.
Schedule 408 pipe with two 12 in. Pipe caps. Thus, two assusulators (3.93 ft each) are used for each potv, and the total volume provided is f.68 ft.
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4 Trojan Nuclear Plant Doctime nt Control Desk l Docket 50-344 March 30, 1990 License NFP-1 1
Page 6 of 25
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tr. ACTOR tatP. s ArttY fM3tCtf0W. AND Bf ACW05f t 8tep Attlon/trpetted Response Response Not Obtained W0ts Stepe 1 throulh 11 are IMMEDIAtt
_Actiov stees.
IMMFbtitt ACTf0N STEPS 1
Verifv Reactor Trie Manually trip reactor. IP
- Reactor trip and bypass reactor is W01 subtritical. THEN l
breakers - CPt2 to to PR-3.1, RE8PON$t to POWER CENERATION/ATV3. Step 1.
- Rod bottoa 11thts - LIT 4
- Woutron fluu DECREA3ING 1
Yorify hrbine tries Verify the following valves.
a.
a.
Manually trip the turbine.
CLOSED:
- Stop valves
- Control valves
- Intercept valves
- Reheat stop valves b.
Bleeder trip valves - CLostD b.
Manually tioso valves, i
Extraction line drains OrtW
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c.
c.
Manually open drains.
3 Verifr cenerater tries i
a.
Cenerator output breakers -
e.
Manually open output CPtV breakers 30 seconds af ter turbine trip.
b.
Generator exetter field b.
Manus 11y open breaker.
[
breaker = CPtY l
L E1-0 page 2 of 18 Revision 16 i
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e Trojan Nuclear Plant Document Control Desk l Docket 50-344 March 30. 1990 License NFP-1 Page 7 of 25
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REACTOR TRIP. SArtTY fM3tCTf0W. AND f,f ACNOSIS 8tep Attlon/ Expected Response Response Not obtained IMMEDIATE ACTf0N STEPS 4
Yorify Power to AC taartenev husest Al or A2 emergency buses - At a.
LEAST ONE ENERCIZED Try to restore power to at a.
least one emergency but by manually starting and leading the EDO from the control room. IF power CANWOT be rastored to at least one emergency bus. THtW go to ECA-0.0, LOSS OF ALL AC POWER, Step 1.
b.
Al and A2 emergency buses -
b.
Try to restore power to DOTH EWERGIZED doenergised bus per CN!-32, 12.47-kV and 4.16-kV system Faults, while continuing with this procedure.
5 Cheek if af te Actuated:
C-required. THEN manually actuate.
check if SI is required. IF SI is IF 81 is NOT required. THEN to to E8-0.1, REACTOR TRIP RESPOW$t, Step 1.
a.
Seguencer tree lights - LIT Manually start applicable a.
equipment, j
b.
SI status lights - LIT b.
Manually allsn app 11eable equlpment.
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Trojan Nuclear Plant Document Control Desk f
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htACTOR TFIP. RAFETY TNJtctf 0W. AND DfACN0Sf 3 Step Action /txposted Responso Response Not Obtained IMMEDIAft Actf0W titPS 6
Yorify containment Yaolation.
phase At a.
Containment Phase
'A' a.
Manually initiate CIS.
1 solation status 115 hts - LIT Manually close valves that DO NOT have status 11tht lit.
7 Yerify_Feedwater Ysolat tent Manually close valves.
FWIVs - CLost0 FWIV bypasses - CLSSED FWRVs - CLOSED e
e FVRV bypasses - CL08t0 8
Yerify AFV Ptnama tunn1MrI a.
Turbine-driven ATP - STARTED:
a.
Manually open valves.
- Steam supply valves - OPtW
- Stena stop valve - CPEN
- Trip and throttle valve -
OPtW b.
Diesel AFP - STARTED b.
Manually start pump.
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Docket 50-344 March 30, 1990 License NFP-1 At t aciunent 3 Page 9 of 25 I
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mtACTOR TRIP. Sh[IIY IKJEFTf 0W. AND DIACN0$f t step Action /tzpected Response Response Not obtained i
IMMEDIAft ACTIOW titPS I
9 ggylfr tect Plows:
i 4.
CCp BIT flow - FLOW on FI.917 s.
Manually start pumps and align valves.
b.
RCS pressure - < 1,520 pots b.
Go to stop 10.
(< 1.000 pois for adverse containment) 1 c.
31 FLOW on FI-918 and FI-922 c.
Manually start pumps and align valves.
d.
RCS pressure - < 200 pois d.
Co to stop 10.
(< 400 pois for adverse containment) e.
RNR FLOW on F1-970 and FI-971 e.
Manually start pumps and align valves.
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10 cheek ff Main steamlinen should be Isolated s.
Steam flow - HIGH COINCIDtWT s.
Go to step 11.
WITH:
- Lo steam pressure
- CR -
- Lo-Lo TAVs b.
Verify MSIVs and bypasses -
b.
Manually close MSIVs and cLostD bypasses.
EI-0 page 5 of 18 Revision 16
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i Trojan Nuclear Plant Document Control Desk!
I Docket 50-344 March 30, 1990 I
License NFP-1 i
Page 10 of 25 I
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REACTOR TRIP. SAFETY INJECTICE. AND DIACNOStB Step Action / Expected Response Response Not Obtained IMMEDIAff ACTION STEPS 11 Check Containment Pressuret a.
Containment pressure - MA8 s.
Ce to step 12.
EXCEEDED 30 psis b.
ks!Vs and bypasses - CLostD b.
Manually close usive and bypasses.
c.
Containment spray eductor c.
Perform the followinst flow - FLOW on FI-2079A and FI-20798
- 1) Manually initiate a containment spray signal.
- 2) Manually start the containment spray pumps.
- 3) IF no flow on FI-2079A and FI-20798. THEN manually align valves.
d.
CIS phase B valves - CLOSED d.
Manually close phase
'B' 1so'.ation valves.
- MO-3294
- M0-3294
- M0-3300
- Mo 3320 e.
Stop all RCps l-END CP IMMEDIATE ACTfoU STEPS {
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T Trojan Nuclear Plant pocument Cont rol Desk j
Docket 50-344 March 30, 1990 1.icense NFP-1 Page 11 of 25 i
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REACTOR TRIP. RAftTY INJtM IOK. AND DIACW0fts Step Action / Expected Response Response Not obtained Wott RERP actions should be performed i
in parallel with this procedure.
lt Yerify total AN flow > 495 ana IF 8/0 WR 1evel > 5% (> 12% for advers, containment) in any 8/0 THEN control feed flow to maintain WR 1evel.
L IF VR 1evel < 5% (< 12% for I
adverse containment) la all 8/0s.
I THtW manually start pumps and a118n valves as necessary.
IF-AFW flow > 495 Spa cANWOT be s
established. TNSW to to FR-H.1 Resp 0N88 70 L088 0F 88c0WDARY NEAT IINK, step 1.
13 Verify 103 Mont ma=avait a.
TAyg - DecktASING to 557'r a.
If temperature > $57'F. THEW
- Dump steam to condenser
- OR -
- Dump steam usint 8/0 PORVs.
b.
TAYS - STABILIZE 8 at 557'T b.
IF cooldonm continues TXtW l
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- 1) Verify steam dumps and S/0 p0RVs ct.08tD
- 2) Maintain total feed flow
> 495 Spa until WR level
> 5% (> 12% for adverse containment)
- 3) IF tooldown continues.
THEW tiose MSIVs and 3
bypasses.
(
EI-0 page 7 of 18 Revision 16
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Trojan Nuclear Plant Document Cont rol Desk I Docket 50-344 Ma rc h 30, 1990 License NFP-1 I
Pag 0 12 of 25
)
k'8P" b i3 See SRp/4 tttroust to Loss or I;tcoWDAkY HEAT stWK Step Action /tzpected tosponse Response Wot CDtained seeeeeeeeeeeeeeeeennenseeeeeeeeeeeeeeeeeen l
CAlff!ON l
j IF total feed flow is < 720 spa due l to operator actlen, this procedure 3
3 should WOT be performed.
3 eeeeeeeeeeeeeeeeeeeenreeeeeeeeeeeeeeeeeeen i
gemeeneeseeeeeeeeeeenomeoneseeeeeeeeeeeeeg g
CAUTION' 3
,I If WR 1evel in any 3 s/Gs < 25%
l 3 (o 38% for adverse containment) EB i
g FIR pressure > 2,335 pois due tc, loss 3 of secondary heat sink, RCPs should l be trlpped and steps 10 through 1$
3 should be instediately initiated for 3 blood and feed.
neeeeeeeeeeeeeeeeeeee,eeeeeeeeeeeeeeeeeeen i
go. eeeeen nemene.oeneneseen.eeeeeeeee.
CALITIOW l
C Feed flow should not be established
- l to any faulted 3/c if an intact s/c, l
, ; is available.
n e n nee n ne s e e n n e ne e *** ema n n e e n en e m en e e n e n n e; 1
check tf secondary Heat sink te Recutred s.
RCS pressure. > ANY IWTACT a.
Go to II.1, LOSS OF REACTOR CtWERATOR PRESSURE OR SEC0WDARY C00LAFf, Step 1.
b.
RCS temperature - > 350*F b.
Try to place RNR system in servlee per 0141, Residual Heat Removal, while continuing with this procedure. Ir adequate tooling with luct is established. THtW return to the procedure and step in effect.
FR.H.1 Page 2 of 22 Revislon 7
p e
e 8
i Trojan Nuclear Plant Document Control Desk !
Dc,:ke t 50-344 March 30, 1990 j
l License NFP-1 Page 13 of 25 i
i, RtsPoust to 1.oss or litc0NDARY HEAT sfWK step Action /tzpected Response Response Not obtained t
NOTE Refer to OW155. Operation of 31octric Arp Supplied by 200 for the steps necessary to start the electric Arp on an EDC if offsite power is not
_available 2
fry to istablish AN Flow to a(
kgagt one sto:
s.
C. weck control roca indications foi cause of AN fallure:
- C8.* Invol Turbinn AN pump steam e
supplies stop valve, trip and throttle valve
- Diesen ArW pump fuel oil supply
- ArW systen valve alignment.
C 4
b.
Try to restore A W flows b.
Start the electria ApW pump.
- Start the diesel A N pump
- Start the turbine A N pump s.
Check total flow to 8/C -
c.
Dispatch operator to locally
> 720 spa restore AFW pumps and valve alignments. Go to Step 3.
d.
Return to procedure and step in effect 3
Sten All RCPs 4
Check CCP Status - AT LEAST ONE Co to Step 10 AVAlt.ABt.t FR-H.1 page 3 of 22 Revision 7 l
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a Trojan Nuclear Plant Document ControlDeskl Docket 50-344 March 30, 1990 License NFP-1 i
Par.e 14 of 25 ttEPON$f TO t.0SS_ OF lltCOWDARY_yAT StWK Step Action /trpected Responso Response Wet obtained 5
fry to totabitsh Main sV Flow To At least One 3/Cl a.
Check condensate system - IW a.
Try to place condensate SERVict system in service por 01-B-1, Condensate and Feedwater System. IF WOT, THEW go to stop 9.
b.
OPtw fv!Vs to the selected b.
Open Mvs and TRVs to the 3/Cl selected S/C per Appendix A.
- 1) Rack out the reactor Ir no rav and FVIV can be opened, trip breakers and their THEW 30 to Step 9.
bypass breakeas
- 2) Roset 31
- 3) Roset TWIS
- 4) Open the FVIV, and FRVs C
or their typasses to the selected 5/G
- OR -
- 1) Locally override the applicable TRV open with the manual handwheel
- 2) OPEN and HOLD the applicable FVIV switch in oprW at the FVI control panel c.
Defeat the MrP trip signalst t
c.
L1ft leads specified in Appendix 3.
e 1
- 1) Rack out the reactor trip breakers and their bypasses
- 2) Roset sis d.
Establish HTV flow per 01-8-1, c.
Co to step 7.
Condensate and Feedwater FR-H.1 page 4 of 22 Revision 7
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Trc.jan Nuclear Plant Document Control Desk l
Docket 50-344 March 30 1990 License NFP-1 Page 15 of 25 i
i
[
utsroust to toss 0F litc0WDARY HEAT strK Stop Action / Expected Response Response Not Obtained i
6 check s/C Levels a.
WR 1evel in at least one s/G a.
It feed flow to at least
> 3% (> 12% for adverse one s/c verified, THEN containment) maintain flow to restore WR levet to > 5% (> 12% f or adverse containment). IF WOT verified, THtu go to Ster 7.
b.
Return to procedure end step in effect 4
C i
t t
FR-H.1 page 5 of 22 Revision 7
e Trojan Nuclear Plant Document Cont rol Desk i Docket 50-344 March 30, 1990 License NFP-1 Page 16 of 25
.h f
ttsPOWsr to 1.033 or';tc0WDARY HEAT stWK Stop Action /tupetted Response Response Not obtelned seeeeeeeeeeeeeeeeeeeieeeeeeeeeeeeeeeeeese I
CALITION l,
The following stop es11s for l
3 depressurtsing at least one 8/G.
- l 3
Since steamline delta P $t signals 1 3
CANWOT be blocked, automatis
- l intttation way result. 81 and C18 j q
should be reset as soon as possible g and charginh, letdown and a
containment instavnent air restored I 3
to normal lineup while performing I
{
this stop k
eeeeeeeeeeeeeeeeeeeegeeeeeeeeeeeeeeeeeeen
.;teeeeeeeeeeeeeeeeenleeeeeeeeeeeeeeeeeeee, l
CAttTION 1
,I Following block of automatic st
){
signals, or at reset following
. l automatie actuation, manuel 31 1
- l actuation will be required if conditions degrade C
! reeeeeeeeeeeeeeeeeee reeeeeeeeeeeeeeeeeeen; 7
Try to totablish Faed Flow From The Condensata Svetant a.
Depressur1:e RC8 to e 1,065 psig
- 1) Check letdown - IN
- 1) Use one F1R PORY. IF SERVICE P1R PORY CAFWOT be used.
TK8W use aux 111ary spray. Co to Step 7.b.
- 2) Use auxiliary spray
- 2) Use one PER PORV.
I b.
31ock 81 signals which are blockablet
- Migh steam flow colncident with low steam pressure or low Tay
- Low ??.R pressure continued next cete
(
FR-H.1 Page 6 of 22 Revision 7 i
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I Trojan Nuclear Plant Document Control Desk l
)
Docket 50-344 March 30 1990 I
License NFP-1 At t ac hment 3 Page 17 of 25
.)
i RESPOWIt TO LOSE OF ;ltCONDAltY HEAT SINK Step Action /Ewpected Sosponse Sosponse Wot Obtained 7
Contitwed c.
Depressurise at least one 8/C to e 400 ps181
- 1) Close selected S/C M51V and Ms!V bypass
- 3) Open the steamline 70RV
- 2) Co to Step 9.
to the selected B/C end depressurite the S/C to e 400 ps18 6.
OpKW FWIVs and FVRVs to the 4.
Open FVIVs and FRVs to the selected 8/04 selected B/C per Appendix A.
l
- 1) Rack out the reactor trip brookers and their bypass breakers
- 2) Roset 81
- 3) Roset FVIS
- 4) Open the FVIV and FRV. or
+
their typasses to the selected 8/C
- OR
- 1) Locally override the applicable FRV open with the manual handwheel
- 1) OttV and H06D the applicable FVIV switch in open at the FVIV control i
panel Establish a valve lineup to a.
Co to Step 9.
e.
supply condensate flow to the selected S/C f.
Operate the selected 3/C 70RV f.
Co to Step 9.
and reSulate the condensate flow to control RCS temperature until another means of coolins is available 8
Establish makeup to the 8
Ir level in the CST drops hotwell from the c8T to 9%. Tittu makeup to the (Csf level > 9%)
hotwell usins fire main supply throush an open aanway.
FR-H.1 pase 7 of 22 Revision 7
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! arch 30. 1990 License NFP-1 At t achment 3 Page 18 of 25
)
i ResPoust to toss or litCONDARY HEAT SINK Stop Action /swposted Response Response Wet Obtelned 8
Check S/C Levels:
I a.
WR level in et loost one a.
IP feed flow to at least s/C - > $% (o 12% for adverse one 8/C vertflod. THEW contatteent) maintain flow to restore NR i
level > 5% (> 12% for adverse contalement). IP WOT verified THEW 30 to Step 8.
b.
Return to procedure and stop in effect l
9 Check for Loss of secondary West Return to Step 1.
I.lt@.1
- Vt 8/0 level - < 25% in any 3 8/Cs (< 38% for adverse contelnment)
- CR -
- PER pressure. > 2,335 pelg
+
FR-H.1 Page 8 of 22 Revision 7 6
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j Trojan Nuclear Plant Document Control Desk l
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Docket 50-344 March 30, 1990
)
1.1 Cense NFP-1 At t achment 3 8
i Page 19 of 25 I
i
[
RESPCNSt TO LDSS OF lltc0NDARY HEAT SINE step Action /twpected Response Response Wot Obtained I...................n.....................;
CAUTION
- l
- Steps to throush is must be perfomed l
- quickly in order to establish RC8 I
- 8. heat removal.by RC8 blood and..f eed...........;
j 10 Actuate at l
11 verify recs riow:
l a.
Check flow indlestions a.
Manually start pumps and l
altsn valves se necessary to
- CCP BIT flow - FLOW establish feed path. Er a indicated on FI-917 feed path CANNOT be
- OR -
established. THtt continue attesyts to establish feed
- SI pumps flow. Return to Step S.
- 1) SI pumps - AT LEAST ONE RUWWING
- 2) RC8 pressure - < 1,$20 C
l psis (< 1,000 pois for adverse containment) l
- 3) Verify SI flow - FLOW indicated on FI-918 and FI-922 l
12 Res.t St and CIS l
l l
l
(
l
(
(
FR-H.1 page 9 of 22 Revision 7
I Trojan Nuclear Plant Document Control Desk Docket 50-344 March 30 1990 8
License NFP-1 Page 20 of 25 i
f ktsPoust to 1.083 0F MECONDARY HEAT StKE Step Action / Expected Responso Response Wot Obtained 13 tstabilah it.strument Alr to
$9ALAl.Dgtakt a.
Verlfy at least one instrument a.
IF off site power is A/C. S WWIWC avallabla. THEN locally start one Instrument A/C per 01-7-5, Instrument and Service Alr.
IF of f.slie power or bearing tooling water systen are WCT available. THEN start the S Joy A/C se follows:
- 1) Attach hose to drain between sprinkler valves FP-043 and FP-044 Attach other end of hose to 3 Joy A/C BCW draln valve DC-042.
- 2) Close SCW supply valves C
BC-033 and DC-039 and return valve DC-045 on 3 Joy L/C.
- 4) Place 3 Joy A/C controller in off.
- 5) Roset lockout relays on the LCCat
- 86 501
- 86-302 i
- 96 303
- 96-304
- 6) place 3 Joy A/C controllers in constant and select lead No. 2.
b.
Open - CV-4471. Instrument air to containment isolation FR-H.1 page 10 of 22 Revision 7 1
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1' 4
3 Trojan Nuclear Plant Document Control Desk !
Docket 50-344 Match 30, 1990 License NFP-1 Page 21 of 25 l
1 ttsPoutt to Loss or atCONDARY HEAT RINK Stop Action / Expected Response Bosponse Not obtsLned g...................o....................,
CAUTION i
- l The followLns stop may result in the tvpture of the PRT tvpture disc.
l
- Abnormal contalnment conditions 1 andtseting a Possible RCs leak or ll LOCf. may occur due to a loss of PRT,;
l
,; integrity.
1r.......................................,.;
14 Establish RC9 Riand Paths a.
Verify PER PORY block valves -
s.
Open block valves.
ALL OptW b.
Open ALL PIR PORVs 15 Verifv adenuata act tiend paths a.
PER FORVs - DOTH OPRW a.
Perform the followings
("
- 1) Open reactor vessel head vents:
3
- SV-1015A
- BV-10158
- SV-1016A
- SV-10168 i
- 2) Depressurise at least one intact 8/C to atmosphere using s/C PORV.
- 3) Alisn any available low.
pressure water source to the depressurized 8/C.
L PR H.1 Page 11 of 22 Revision 7 i
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Trojan Nuclear Plant Document Control Desk l
i Docket 50-344 March 30, 1990 License NFP-1 At t ac hment 3 I
Page 22 of 25 l
4 t bp0AL4 b lF y i
TAlt.t 15.8 1
(
P ATVT ANALYSIS NODEP, SUMMAILIES Trojan WCAp4330 Nuclear Parameter Model Plant t
Number of loops 4
4 Core power, NW:
3,411 3,411 Noelaal pressurlser pressure 2,250 2,250 l
Hominal coolant flow, spe 354,000 354,000 Noelnal average coolant temperature, 'T 584.65 584.7 *I
'D_
I Nominal coolant no-load temperature, 't
$57 557 Togel RCs volume including pressurlaer, 12,600(b) 12,527 0I ft 3
Ib Pres surlier volume, it 1,843.7(b)
I,800 Steam capacity of power-operated tellet 210,000 210,000 valves, Ib/hr, 2 0 2,350 pata I8I N
Ib steam espeetty of estety valves, Ib/hr 420,000 435,120 Dest estleate rod worth of bank D at ite 0.3 0.3 full power Insertion limit, tak/k Steam generator design pressure 1,200 1,200 stema generator nostnal etese 533.3 533.3 temperature, 'T Nominal etese flow, Ib/sec 4,192 4,166.1 Noelnal fluid mass in steam generator, Ib 406,400 ~
406,400 Auxiliary feedwater temperature, 'T
>130
>130 Auxilisty feedwater evallable, gal 170,000
>l90,000 capacity of auxillery feedwater, spe 1,760
>t,760 Volume of line between aux!!!ary feedwater 500
>500 connection on feedline and stege generator inlet, total for all loops, it (a) Noelnal T,,, at 1002 power.
[b] Includes eurge line.
(c) Does not Include 31 thermal expansion factor. The RCS volume used in the a
large break LOCA analysis was 12,476 cuble feet.
d (d) Three at 2,500 pale.
(e) Three at 2,590 pets.
9 Amendment 3
.I (July 1985) l l
c"*
Trojan N:c1 car Pltnt, backet 50-344 L1CCOse NFP-1 M
I'nGrmaHan er #6
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' At tach ent 3 - '
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