ML20214H868
| ML20214H868 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/18/1987 |
| From: | Rotella T NRC OFFICE OF SPECIAL PROJECTS |
| To: | NRC OFFICE OF SPECIAL PROJECTS |
| References | |
| NUDOCS 8705270527 | |
| Download: ML20214H868 (297) | |
Text
May 180 1987 l
Docket No. 50-327, 50-320 PLANT: Sequoyah Nuclear Plant, Units 1 & 2 UTILITY: Tennesee Valley Authority
SUBJECT:
MINUTES OF MARCH 26, 1987 MEETING TO DISCUSS THE SECU0YAH DIESEL GENERATOR SEQUENCING CALCULATIONS On March 26, 1987 members of the staff met with representatives of the Tennessee Valley Authority (TVA). The purpose of the meeting was to discuss the diesel generator load sequencing calculations that are presently ongoing for Sequoyah. Enclosure 1 is a list of attendees.
The discussions held at the meeting mainly centered around questions the staff had on the calculations. In response to these staff questions, TVA provided a copy of Revision 5 of the calculations along with the Engineering Change Notification (ECN). A copy of this information is contained in Enclosure 2.
As a result of the meeting, the staff will continue its review of this area using the information contained in Enclosure 2.
Several agreements were reached between TVA and the staff where TVA would undertake some additional actions. These are:
(1) Continue to purr.ue a revision to Technical Specifications, and supporting bases, for diesel generator testing; to be submitted by September 30, 1937.
(2) Timely submittal before Unit I restart, provide the excess voltage drop calculations for Unit 1; (3) Remove all unverified assumptions from the calculations; and (4) In the future, notify the staff of all revisions to the calculations and sutrit any revisions that change the conclusions.
Original signed by:
Thomas S. Rotella, Project Manager D1 vision of TVA Projects Office of Special Projects
Enclosures:
As stated cc: See next page 8705270527 DR 870518 p ADOCK 05000327 PDR Distribution Docket File (50-327/328)
NRC PDR Local PDR OFC :TVA:0SP :TVA:0SP :BC:T :AD:TVA:05P : :
_____:.._______ : _ _ _ _ _ _ _ _ _ 2j . . . y4
_____: _... ____.TRotella NAME :Caamerse
._______ g :JD d _____..:JZwolinski:
DATE :5/ 8 /C' !.,:5/i 4/87 :5//467 :S/d/87:___ ________:______
Of M ~REGU D COPY
Tennessee Valley Authority Sequoyah Nuclear Plant cc: Regional Administrator, Region II Tennessee Department of U.S. Nuclear Regulatory Commission, Public Health 101 Marietta Street, N.W.
ATTN: Director, Bureau of Environmental Health Services Atlanta, Georgia 30323 Cordell Hull Building Nashville, Tennessee 37219 Mr. R. W. Cantrell Mr. Michael H. Mobley, Director ATTN: D.L. Williams Tennessee Valley Authority Division of Radiological Health 400 West Summit Hill Drive, W12 A12 T.E.R.R.A. Building Knoxville, Tennessee 37902 150 9th Avenue North Nashville, Tennessee 37203 ,
Mr. Bob Faas Westinghousa Electric Corp. County Judge P.O. Box 355 Hamilton County Courthouse Pittsburgh, Pennsylvania 15230 Chattanooga, Tennessee 37402 Mr. R. L. Gridley Mr. Richard King Tennessee Valley Authority c/n U.S. GA0 SN 1578 Lookout Place 1111 North Shore Drive Chattanooga, Tennessee 37402-2801 Suite 225, Box 194 Knoxville, Tennessee 37919 Mr. M. R. Harding Tennessee Valley Authority Mr. S. A. White Sequoyah Nuclear Plant Manager of Nuclear Power P.O. Box 2000 Tennessee Valley Authority Soddy Daisy, Tennessee 37379 6N 38A Lookout Place 1101 Market Street Resident Inspector /Sequoyah NP Chattanooga, Tennessee 37402-2801 c/o U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 Mr. H.L. Abercrombie Tennessee Valley Authority Sequoyah Nuclear Plant P.O. Box 2000 Soddy Daisy, Tennessee 37379 I
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Enclosure 1 Attendance Attendees Organization M. Burzynski TVA TVA J. Hudson J. Nesley TVA J. Holonich NRC A. Marinos NRC H. Garg NRC
- 0. Kang NRC J. Knight NRC J. Stang NRC B. D. Liaw NRC T. Rotella NRC .
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- 2. Does the modification add equipment that could involve safe shutdown functions or operational modest ,
- 3. Does the modification involve the oil collection system for the reactor coolant pumps? K
- 4. Does the modification involve changes to the fire detection systems, estomatic suppression systems, or standpipe and hose systems for safety-related structures?
- 5. Does the modification involve the fire rated compartmentation as shown en drawing series 47W494 (i.e.. fire walls, fire rated doors.
ETAC fire dampers mechanical and electrical penetration seals)?
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- 6. Does the modification involve power.
control, or instrumentation cables for 1 or 2 above (These cables are identified on the cable schedule)?
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- 7. Does the modifisation involve a previously i identified or create a new potential I associated circuit of concern (see Sqs-DC-@24.0 " Design Criteria for Fire Protec$onofSafeShutdovacapabilities")?
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- 8. Does the modification involve 8-hour battery pack emergency lighting required for operation -
of safety shutdown equipment and access and egress routes thereto or require additional emergency lighting? K
- 9. Does the modification involve any cables associated with the anziliary control room, transfer switches, or that penetrate the "Q" .
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- 10. Does the modification involve changes -
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! could affect the detection system in safety-related structures? _
- 11. Does the modification involve any of the communication systems that serve safety-related structorest
- 12. Does the modification involve the security ,
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- 1. Could the change affect. add. or delete equipment _
within the secpe of 10CFR50.49 (see 10CFR50.49 List)? /J S {
- 2. Could the change affect the basic function of a device or system that performs or supports the !
_ l performance of a safety function? /J @ l
- 3. Could the change affect design conditions or require-mests such as process pressure, process temperature, fluid chemistry, device heating, voltage. - ' :;; rating-" s r cycles (which could impact QMDS requirements or invalidate test data)? /J
- 4. Could the change affect environmental conditions in either harsh or mild areas such as pressure, temperature.
humidity, flooding corrosiveness, site aloration, i nuclear radiaties (both rate and total integrated dose). _
and duration of esposuref /J S
- 5. Could the change affect location or operation of high energy piping systems. location or operation of radio-active piping systems, operation of environmental control systems, or envirossental barriers such as walls. doors, relief panels, ducts etc. (which could affect S
ouvironmental conditions in either harsh or mild areas)? /) '
- e. Could the change involve relocating or reoriesting a device or system (which could impact location-specific or shielding analyses or place the device or system in as area with different environmental conditions)? /J h
'1 SqEF13.A ,
SqEP osoite
3171s105 or EUCLIAR EECumnC (DIE) SECTIOR VIII sEQUOYAE EECnMIEC FR(MBCT (SQEP) SEQUOUR ENGIBMDC FROCEDURE SQEP-13. 3E718105 0 ATTACEMENT 2 FACE 9 0F ~5) 10CFR50.49 ENYIR(EfMENTAL QUALIFICATI05 CRANCE IMFACT RETIEW CEECELIST '
(Contianation) I YES E0 acI E0. _L G'71ci
- 7. Could the change affect materials such as lubricants.
- seals, etc. (which could impact QMDS requirements.
qualification analyses, and invalidate test data)? /J @ l
- 8. Could the change affect operational and/or safety I
I requirements under various conditions such as plant I startup, normal operation, shutdown. emergency conditions, abnormal conditions. operational _
transients, and mitigation of DEAaf /f /3
- 9. Could the change affect special maintenance ((plDS) and/or administrative requirements and controls O
(which could i:spect the qualification of an item)? /J 10 . Could the change affect redundancy diversity, or separation requirenoote of-rcomponent or systesi' (e.g., relocation of iten due to Appendia R _
analyses could invalidate EQ)? /J h IINAE15:
6 0
e O
i SQD13.A .
l l
l USQD SUPPORT SHEET ECN L-I/IIh !
SEQUOYAH NUCLEAR PLANT !
Curiginal to be filed with ECN package) i Additional information of sufficient detail to accurately describe the scope of the change ;
FOR. A LOSS OF OFF5ITE pot 0ER. C00C(JR.REMT tutTH AO et AMD PHASE B conTAIMMEQT (SOLATIOM THE FOLlou310C, CMA26E6 ARE REQUIR Eb -
l
- 4. COQTAI MMEOT $PRAN 9049 ; C6P CLR FAO d 6PRAN RDR 160 L U A LVG - CM AMGE THE LOAD $Ec u EMCE TI M6 DELAM f:RO M %O 4EC To 3 Mtlll 2, EL BD RM A M U - T RI P AMb BE LAN RE5 TART UMTlL AFTER. t00TAIMMEOT 49R.A9 PdMP 6TAETS .
(.
. Design Change Checklist
.. - Seismic Analysis Required? ? Yes ')< No Category I (Class IE) Yes X i Position Rotention Yes 1 Pressure Boundary Rotention Yes l Retest Scoping Document CPnT)? Yes 1 No l
. Appendix R Analysis Affected? Yes X No i FSAR Affected (drawings or text)? Yes No Potential Tech Spec Change? Yes No t Environmental Qualification Affacted? es No %
Electrical Separation Required? Yes % No l Westinghouse Involved? Yes No v Other OEP-11, Attachment 2 item's considered? Yes No h TVA Material Classification:
4E
-l Referskeis 1 Knowledgeabia Individuals: blCE MA655 WAbE 14GL8R00K.
Memos, SCRs, FCRs, etc. 46R $G MEEB fBG2 9 R3 I Responsible OE Engineer
- 4M [d -
[85 ,
.an.t .. date F i l
I l
m . .. . ~ . ,
, UNITED STATES GOVERNMENT QA Reced l Mcmorandum TENNESSEE VALLEY AUTHORITY
]
l To :
D[ [b /d/f dA f ,_;
P. R. Wallace, Plant Manager. ONP, P05-2, Sequoyah Nuclear Plant (Attn: J. B. Sullivan)
FROM :
4 D. W. Wilson, Project Engineer, Sequoyah Engineering Project, DNE, DSC-E, Sequoyah Nuclear Plant
- DATE :
j
SUBJECT:
/o -/sV4 -
SMUOYAH NUCLEAR PLANT UNITS Ik1 ScL - ENGINEERING REPORT TOR CM REPORT NO. SQd EE62619 F.3 REVISION LI
.I The original Engineering Report (ER) describing the conditio.1 for the identified CM is attached. Please review this report for potential reportability under 10CFR21,10CFR50.72, and 3.0CFR50.73.. Please document' your receipt and handling as requested by completion of the return receipt below, bfx e b VAB:JAS
, , D. W. Wilson.) ' ~
Attachment '
cc (Attachment): !
RIMS, SL 26 C-K
- H. L. Jones, DNE, DSC-A, Sequoyah _
~
J. A. Raulston, W10 C126 C-K
~
W L. Elliott, DNE, DSC-D,- Sequoyah .
- d. 5. En.aklev . hue- WSC1:U.C-K ,
a .T. MalR - 046 ixc' P. sm,s A i ,
fin, , ,;$ -
.;.yp . 4pu *: -
D. W. Wilson, Project Engineer, Sequoyah Engineering Project, DNE, DSC-A, Sequoyah Nuclear Plant
- P. R. Wallace, Plant Manager, ONP, P05-2, Sequoyah Nuclear Plant
~
~. .
We have received the subject CAQ Engineering Report for determination -- .
i of reportability.
P. R. Wallace -
H. L. Jones, DNE, DSC-A, Sequoyah
. J A. Raulston W10 C126 C-K Y 5. hublev,. DNG , W7d11c4 :
C.T. dilt' . 04s . DGC- F . sequu, .L
, j I
l l
l SQEP - Sep. 10, 1986 .
'I DE04;JS6230.04 ~
l
i
.
- E$GINEERING REPORT RIMS Accession Number I (By ONE for CP Plant) g ER Rev. (By Site oirector s
- Organization for OL Plant)
CAQ Report No. and Rev Plant and Unit Site Director's Contact and Date Notified (OL Nuc Plants Only a g; SCR SQNEEB8629 R3 SQN Units 1&2 ~
5$ Definitive Statement of CAO (See Note 1.)
The diesel generators at Sequoyah Nuclear Plant will have an engine failure (engine l
~5 g Co overload) if the random loads of the generator are applied at t = 30 seconds. I 96 Maximum total load (starting and running loads) at the t = 30 seconds cannot .
36 exceed 4482 kW. At present time, a loss of offsite power with a safety injection l 23 (SI) and Phase B isolation, the total loads at t = 30 seconds are: 1A-4563 kW, i 1B-4636 kW, 2A-4650 kW, and 2B-4925 kW. (see attachment 1)
- See Note 2 on page 4 for completing Part B . Part 8 continued on pages 2 and 3*
Yes (OL Nuclear Plants Only) Due Date of Failure Evaluation Preparation of Failure No Evaluation is required? FSAR Revision Required? Yes No Conclusions (See Note 3.) J c ~.
See attachment 2
.9 !
2 W$
20 3W 5Z !
'3 b Recommendations (See Note 4.)
I See attachment 2 o-Suggested Corrective Action
~
Implement reco=mendation 1 before unit 2 restart. Implement recommendations 2 and
% 3 during first refueling outage. This is based on memorandum from W. S. Raughley ')
- to D. W. Wilson dated 9/29/86, B43 860930 901, attachment 3. >
Date Failure Evaluation Received Date Management Notified Operational Limitations / Actions Justification For Continued Operation C
.9 1 3s
. :)
$ ti Conclusions 1 l
%.5 -
i M5*
l
.E Indeterminate item?
n.
. . . .... . . . ... . .. ... . .. .. . ... .. .. O ve' O ~-
Potentially Reportable to NRC7 Yes
,, , , , , , ,,,, ,, ,,, No Deficiency Adversely Affects Safe Operation of Plant?
Yes
] No ONE Contact Approved By and Date i
Prepared 8v and Date -
TVA 10826 (ONE446) cc: RIMS, (Submit to RIMS as stancatone docuenent.)
4
. Part B (Continued)
CAQ Report No.and Rev. Page 2 of 4 ER Rev.
- 1. - Tabulate Data on All Failed and/or Affected Components. Structures, and Systems: -. Give descriptions, model and .
manufacturers' numbers, and original and revised design criteria and/or specifications. (See Note 5.)
Diesel generators lA, IB, 2A, 2B, and C-S Contract Nos. 71C61-92652 and 74C63-83090 Vendor - Morrison-Knudsen Company, Inc.
t
- 2. Failure Mechanisms of Affected Components, Structures, and Systems: State whether each affected component, structure, and system became open or closed, inoperative, or shorted;or had shortened life, reduced accuracy, increased drift, reduced capacity, etc. (See Note 6.)
Exceeding the diesel generator's transient power capabilities will cause the system frequency to dip below Reg Guide 1.9 limits and can cause the engine to stall.
Sir.ultaneous start of ERCW and AW pump motors will cause voltage drop to exceed Reg Guide 1.9 limits and can cause inadequate voltages throughout the power train.
- 3. Alternate Uses and Generic implications: Identify alternate uses of the components, structures. and systems in the plant. Discuss generic implications. (See Note 7.) , ,
,.4 zp. . j . . .
Alternate uses do not apply. Generic implications have been addressed by Potential Generic Condition Evaluation Memo B43 0418 918.
j . ..
I
- 4. Component, Structure, and/or System Failure Mode (sl: Give description and extent of effects of failures on each
- component, structure. and/or system involved. (See Note 8.)
Loss of a diesel engine due to transient overload can cause loss of a safety-related l- power train. Inadequate voltages in the auxiliary power system can cause motors to l I
stall and motor controllers to operate inadvertently.
- i 4 ,
I I
l y- , y y- ,y-g w- g- y*IQ 9-b q- =-w-" w w- A --s- y, e-- -w-en < *+-4y" ' * ' P,-Wi .- g
Part 8 (Continued)
ER Rev. 1 CAO Report No. and Rev. SCR SONEEB8629 R3' Page 3 of 4 l S. Cause of the CAO: Discussw. hat the CAO was due to, e.g., a program breakdown, new regulation, analysis or design error, test results showing a deficiency, and/cr failure to meet design criteria and/or purchase specifications. Include calculations, analysis resu!k test results, and/or purchase requirements not met, or other bases. (See Note 9.)
Failure to establish an adequate system of procedures to ensure th'at calculations / studies performed by EEB are updated and revised to support the design ,
as changes are made after plant operation. This was identified in Office of Quality Assurance Deviation Report D51-A-84-0006-D01 dated July 2, 1984. Also, l I
previous analysis erred in assuming that the worst-case loading would occur for a concurrent SI and phase B containment isolation. .
l
- 6. Consecuences on Plant Design Functions: Discuss effects of failures on all involved component *s, structure's, and-system's ability to perform their plant design functions. (See Note 10.)
Engine overload can cause the engine to stall and cause the onsite power systen to be unable to perform its design function. Also, the auxiliary power system's ability to perform its required functions cannot be guaranteed with voltages outside of its design basis (ANSI C84.1-1970).
- 7. Justification for Conclusions in Failure Evaluation: Discuss the reasoning based on the information above which leads to the conclusions stated. (See Note 11.) -
. , , The loading at each sequence step was determined in Diesel Generator Loading Analysis, SQN-E3-002R3 (B43 860827 909). The diesel engine's capabilities were -
provided in Morrison-Knudsen Report No. 6957R Rev. 1. The generator's capabili ties were provided in NEI-PEPI Report T-1016. Comparisons of the maximum possible Joad at each step with the diesel-generator's calculated capabilities demonstrated t he potential overloaded conditions. The worst- case loading used in the analysis was I the simultaneous start of the process-controlled loads and the containment sprey l pump. All other loads that could 1.e running on the diesel-generator were also .. I considered. This is a very low probability event. DNE1 - 0551W Prepared By and Date Coordinated in Site Director's organization with:
%d %.4~0suk loMss erified By and Date Discipline Lead Engineer (s) and Date I f
- 10,i Yb g
Approved By and Date l k2.h ff W 10/2/8); V
l l
l Page 4 of 4 NOTES ON ER FORM BLOCKS
- i
- 1. Provide a definitive statement of the CAQ. The NCR/SCR description of the CAQ is to be restated verbatim or expanded for clarification to ensure the statement reflects standalone" documentation of the CAQ.
- 2. Various items in Part 8 (pages 2 and 3) are to be completed to support the conclusions and recommendations. All items on the form (pages 2 and 3) are not necessarily applicable to each CAQ. Add sheets and data as necessary.
- 3. Explicitly state the conclusions of the, failure evaluation regarding the ability of,tt}e affected component's, structure's, or
~
. . ..sys.
. c.
.6 tem. 's.a.apability t.o perform its require.d..d. esign func. tion.
. . . . . . ,p ,
- 4. Recommendations in this block (or elsewhere on the ER) should '8r' ovide DNE's'besfjudynent as to what is needed to correct the condition. Recommendations are to reflect suggestions that correspond to the stated conclusions of the taiture evaluation. The recommendations should not be worded as requesting work authorizations or funding for additional work. ,
- 5. Other affected components. structures and/or systems (CSSs) not specifically identified in Part A of the ER should be identified here.
- 6. " Mechanism" pertains to the mechanics of individual component failure (s).
- 7. Attemate Uses and Generic implications: Identify alternate uses of the affected CSSs in the plant. If the condition has generic implications, they should be discussed here.
- 8. " Mode" as used here pertains to operational manner or process. --
- 9. Self explanatory.
- 10. A conclusive statement is needed here on the ability of the affected CSS to perform its intended design function with the condition documented in Part A of the ER. Plant safety aspects (i.e., safety evaluation) are not to be considered here.
- 11. Provide adequate justification to ensure the conclusions stated are logical and reasonable based upon the evaluation findings and statements. -
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es10 t
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- 4 Attachment 1 Sequoyah Nuclear Plant Units 1 & 2 SCR SQNEEB8629 R3 Definitive Statement of CAQ (continued) .
Revision 2 of the DG load analysis (843 860827 909) has identified heavier loadings for the condition of a loss of offsite power with a delayed SI and .
Phase B isolation. Also in R2 of the load analysis, it was determined that load sequence timers for the ERCW pumps are reset by an SI in either unit.
An SI in one unit can cause the simultaneous start of the ERCW and AFW pumps in the other unit. The voltage dip for the simultaneous start is 30 percent, which exceeds Reg. Guide 1.9 limits (25%).
e i
a.
O e
DNE1 - 0551W t
9
- - - - - - - - - -- - -. , - ..n-- , , . , , - - ., ,, -, ,~ - -- e ,
. ~ ._ _ _
sheet 1 cf 2
~
Attachment 2 -
Sequoyah Nuclear Plant Units l' S 2 SCR SONEEB 8529 R3 CONCLUSIONS The diesel engines can be overicaded for a less of offsite power with a SI and phase B containment inclation during the containment spray pump start. This can cause the loss of the auxiliary power train. For an SI in one unit and a loss of offsite power in the other unit the ERCW and AFW pumps can be,1caded onto the diesel
, ,. generator simultaneously. This would unacceptably degrade the class ' ' -
lE auxiliary power system.
RECarir1ENDATIONS
.? :
- 1. To ensure that the maximum transient loading is within the diesel generecor's capabilities, for a loss of offsite power concurrent with a SI and phase B containment isolation the fellowing is recommended.
A. Change the load sequence time delay for the containment spray pump motor from 30 seconds to 3 minutes. This allows the diesel engine to reach it's hat rating before the containment ,
..,. spray pump motor starts.
k$.
.i-B. Trip the electric board room air handling unit on a loss cf
- . . . . offsite power and cantainment inclation phase B signal and T2){@P restart after the containment spray pump start.
C. For unit 2, train A, ass'ure that the electric board room it compressor can not start at the same time as the shutdown board !
- hgW,{ room air handling and chiller package. It is acceptabis for the ~ ~
electric board room air handling unit and compressor to start at the same time.
L sir handling unit And and it is acceptable for the at shutdown board recm) .
compressor to start the same time. _
l E. For a loss of offsite power with a delayed SI and phase ,B containment inclation, in addition to the previous recommendations; l A. Change the Containment Spray pump sequencing logic so that after the diesel engine reaches it's hat rating the 30 second timer is reinstated.
1 g-e--- --T y y----.3-rw -s
-.,.---m --m- g--r----,3-- - - - +
.-m-ww -.-a -er e - --s--ae--*'9*-- -*--e---- w Ne*w
i l
l
~
sheet 2 of 2 Sequoyah Nuclear Plant Units 1 & 2 ,
SCR SONEEB 8629 R3 .. l B. Trip the Ecllowing 1 cads en a-loss of offsite power and containment isolation phase B signal and restart after the containment spray pump starts;
- 1. electric board room compressor
- 2. shutdown board room water chiller packages and air handling units
- 3. control room air handling units and compressor
- 4. 400U board room air conditioning system -
C. Trip Reactor Vent boards and Conteci and Auxiliary Building -
. Vent boards 1A2-A, 1B2-B, EA2-A, 2B2-B on a loss of offsite power and safety injection.
change the ERCW conteci circuit to disable the cross-unit reset of the load sequence timers.
t e
6 e
~
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< :y- :q,ey . ,. -in3g
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4 ScR SGNEE58629 R3 Aitachmed 3
,/ ER Red I B43 '86 0 9 3 0 901 !
70 : D. W. Wilson. Project Engineer, Sequoyah Engineering Project. DNE. DSC-A,' Sequoyah FROM : W. 3. Raughley, Chief Electrical Engineer W8 C126 C-K l
l DATE : September 29, 1986 QA Record .
SU:: JECT: SEQUOYAH NUCLEAR PLANT - DIESEL GENERATOR ANALYSIS l
i
- ~
. The purpose of this memorandum is to provide my position with regard to those
- h. ,
load modifications identified in the SQN diesel generator loading analysis.- ;
._ The SQN FSAR Chapter 8 (pages 8.3-9.10) and the SQN design criteria " Normal i and Emergency Auxiliary AC Power System" (No. SQN-DC-V-11.4.1) identifies 1 three diesel generator loading sequences: 1
- 1. Loss of offsite power (LOOP) concurrent with a safety injection (SI) ,
signal, i
This analysis has addressed each of these sequences, with corrective action required for each sequence. However based on a review of internal NRC correspondence (attached) that indicates a delayed LOOP or LOCA event does not signifier.ntly contribute to a core meltdown. I conclude that only the modifi-cations for a LOOP conederent with an SI should be performed prior to restart g py' ,y,ig - -
of unit 2, with the remaining modifications scheduled for the next refueling yt+
outage. -
(I N n,_M W. S. Laughlp O JDH:BW -
Attachment ec: RINS, SL 26 C-K. w/1 1 R. G. Domer, W12 AS C-K. w/1 .
J. A. Kirkebo, W12 A8 C-K, w/1 .
l G. T, Hall, DNE DSC-A, Sequoyah, w/1
- A. Priest, OEPS-4. Segreyah, w/1 1 Principally Prepared By: J. D. Hutson. Extension 2928 ,
- DNE1 - 0721W
~;.
t l
- . -,-----.---..--.e _= . . , , - . . - , . . . . -
.-._.. , .. y.,._, ., - . , _-,__. _,..ry.- ..- m ,-, - . _ , ,-,...,3--.m.-,,yw,-,-- - ,
.-.-.--,.3-.,.--,s
-t v a . . ... $dt.LJ S53 860428 843 Eec s g o , , , c ATTACHMENT
. ., UNITED STATES GOVERNMENT i SHEET _ Z-___op_1 jf Meinorandum TENNESSEE VALLEY AUTHORITY TO D. W. Wilson, Project Engineer, Sequoyah Engineering Project, DNE, DSC-A, -
Sequoyah Nuclear Plant FROM : H. B. Rankin, Manager, Design Services, ONP, DSC-E, Sequoyah Nuclear Plant '
~
DATE : MAY 05 bed -
SUBJECT:
SEQUOYAH NUCLEAR PLANT - DESIGN CHANGE REQUEST (DCR) - SQ-DCR-D2259 RESOLUTION TO PROBLEMS ASSOCIATED WITH NCRs/SCRs/ERs Please process the attached Design Change Request in accordance with NQAM, Part II, Section 3.2. Pertinent information is provided below ,,/
~ ' ~
Category -
A (X ) NRC cocmitment, Nuclear Safety, or EPA requirement B( ) Availability, capacity, and reliability improvment C( ) ALARA and safety (industrial)
D( ) Improved maintenance and operational efficiency E( ) Convenience X( ) Documentation only .
This modification has a priority 9 rating.
Account number 87XX-54671-21302-J13-D2259 should be utilizied by DNE for this modification.
This DCR is to provide ONP a generic method in which to expedite the resolution of problems which occur as a result of NCRs, SCRs, or ERs. All Engineering --
Change Notices (ECNs) issued against this DCR will be requested by a specific ONP document.
, .y. pf ~, . , ; . + q. e.p. 4 3 t - e
. -...j$.3-H. B. Rankin KAY 0 5 '86 PRW:GNB:JRW:CCM c,,,,,,,
Attachment _ A_/> W I 'i 72A-C - -
E. R. Enni s , ONP, Watts Bar sn R. J. Johnson, Power Operations Training Center *[$6-[
F. A. Szczepanski, BR IN 76B-C .
.o*
01 - 1 This was prepared principally by Renee' North. oc (l- . .
.p"o.5 t
' L *'
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_.' L^,'. _ ';_ __. _-l-'
jAC l:'
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- SQNP AI Part III
- ' ECN NO.Iz. ur 1 ATTACHMENT Attachment 2 uSHEE 3 g pf Page 1 of 1 .
Rev. 12 50 /
DCR ROUTING SHEET SQ-DCR- A3 b I
- 1. Cognizant section supervisor., review
//I ~/ M7-7k Cog. Sect. upv. Initial D te p 2. Appropriate Plant Superintendent review ~Dk / 4 9l 80 L_,
,' k Approve Disapprove Plc. Supt. Initial -
Recommend "P" Strike (Yes / No Date'
)
Recommended work period for scheduling .
p Remarks:
- y 3. Safety determination performed I -
/
'(Locally approved DCR's only)
.- - Cog. Engr. Initial 3e 4. DCR, OWIL number assigned. Qate L.
,A /M////26 A- 5.
Doc. Coofd. Initial Date PORC review of LDCR safety review -
, /
Presiding Supv. Initial Date
.it 6. . Accounting data, assigned , /
Rep. Sect Admin Off. Initial Date
, / / Capital Job Order No. 87Xl' - fY67/
L-
/ / Maintenance Account No.
- ^ .3 - 2 Gov - 713 X 7. Plant Superintendent approval S-t/
Secy to Plt Supt Init
/M/3o
- Date p
.i(- 8.
- a. Transmitted to Director of Nuclear Power
- '/
% b. Preliminary DCR package received from ~ Doc. Coord. Initial
/
Date OE
$ .' c. Doc. Coord. Initial Cognizant section evaluates for "
- Date #.7 .
d' original intention Cog. . Sect. Initial
/
Date
- d. - Accounting data review ,
/
F
- e. SNP Adm Syc Supv Initial Date w Field work evaluation included /
Cog. Engr. Initial Date__
g f. Plant superintendent approval /
L Secy to Plt Supt Init Date 3 "P" designation removed, transmitted /
OE Doc. Coord. Initial Date k 9. Non-safety-related locally approved DCR's i,,,' a. If capital expense, Chattanooga i
/
approval for expenditure obtained SNP Adm. Sve. Supv. Initial Date' . k..
g b. Copies made and transmitted to {
l-Cognizant Section for workplan
/ ;
initiation.
Doc. Coord. Initial Date~ -
{
. # 10. DCR closed (DCR cancelled, ECN received, Doc. Coord. Initial Date or workplan assigned) / -
)
I Doc. Coord. Initial Date ;
-t .
t t
i -
34 .
O
l
~ .: ,l '* ?.*'.. ,'. SQi!P-
? ~. cCN NO I A 7As-
- s. ,
AI Part III gCgT3 ,
grep-p- .
Rev. 9 i DESIGN CHANG' GUEST
(
[ Sequoyah Nuclear Planti DCR No. SQ-DCR-
-M N Date Originating Section Eedbrv Yw heer,*e _ Originator FC.Wdhdhone ' 68lN Outstanding Work Ites No.Cl[A - o00 - /Ne3
' Uhit System Sequence
[ Component bndS Change Requested:~b4eeed c rverM0e., ' cirMcM iho.nM b d in reelvbOM $
a '
h@%*. ewMrtrM wM b-dwea c 4 Ik e d Y ( n A h b'D H .
- and, ed.bn hk A*M e au%or*m Ed k &6b b DA/.
4 I. Reason for Reques : I hhUMo- A Co w v*ir_' N b '
d O fc>-dNOA d' f Po O 6V55' mwe~ re,A+ cf A/2/2 4 / 402 + /R D '<
- s. ! -
Non-safety-related DCR Safety-re2c.ted DCR
[ 1. CSSC non-safety related 1. CSSC safety-related [
L. 2. Non-CSSC and does not directly affect 2. Non-CSSC but directly affects safety-related CSSC stfety-related CSSC Work can be completed prior to'offsite
- 3. 3. ~TecW spec changes involved
. approval section Non-safety-related review completed by
( , ,'(,1) Accounting Data L.
.y i -
,*- '~
pg Preliminary EN DES sconing work to be done under Job Order No.- 68'IIS7/-M C 'This modification is to be capitalized under
/ / This modification is to be charged to .
Maintenance Account No.
&_ W. & ~
/ Y- tr-8 te Nidl. LLes brou,.afM '--. Of ficer -
Date
/ / This is a non-safety-related modification, a safety review has.been performed, anc
,. approval is given to begin modification. '
/
h '
L Plant Superintendent Date Work completed; transmit to EN DES for drawing revision only. 4 4
/_ .
Field Services Group Supervisor Date
/ / This modification is safety related or is to be transmitted to EN DES for
'. processing.
.g Approved for transmittal to Director 'of NUC PR .
L /
JP1 t 'intendentr bath Anproved for transmittal to EN DES. / ffjyr):4h / [ Jif' .
f 1) On1'y filled out if under consideration after ,D/r'e'ctor of Nuclear Powhr ^ Date l-closure of construction accounts. ,'./O
. =,_:-. _ . .- - -
' ", ~
~
SQNP ECN NO.1r.,is-m Att chme t H op
.- Page 1 of 1 Rev. 9
- y. DCR NUMBER ddO 5
COST ESTIMATE
$ UNIT 1 $ UNIT 2 $ UNIT 0 $' TOTAL LABOR F
HATERIAL FIELD ENGINEERING _
. DESIGN ENGINEERING ,
r- TOTAL '
ALTERNATIVES CONSIDERED: 4Cor1Ne _ nbw v.c $ wi{ \ (o# -
bV Or, Ab omt IA Mkb' -
a\udw 4c && sc/t/e A
{
@ g COST BENEFIT ANALYSIS: CDSY hhh vsf% ruedd-p bi comp \ekd ockI cm+ osbah is esidliskcI.
This eLa is in aR d e.+ v re/akd a ;.
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[ Cate ry A(
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{. NRC Commitment, Nuclear safety or EFA Requirement -
B( ) Availability, Capacity and Reliability Improvement .
C( ) ALARA and Safety (Industrial) l D( ) Improved Maintenance and Operational Efficiency E( ) Convenience
- X( .) Documentation
'{ a. Is this a commitment? To W B Wen h MS M@4., %*hc_
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What condition must the unit be in when modification is implemented? vekM Shut down Mode 2 ~ Mode 3 Mode 4 Mode 5 Any Time If shut down, how long? System out of service g Action statement 1
y Who is to do the work? Field Services
-Y 'Specify other O11 WMi l Scheduling P*iority %Q ,
I W en Needed Wy?
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Should we request the Central Office to strike "P"?
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ATTACIDENT 6- E ECN NO z/ 7/s *
. Page 1 of 4 Rev. 9 ATTACHME )
SHEET _ 7 op_ _NT h2,_
P DCR JUSTIFICATION SKEET YES NO
, I. Will unit shutdown be required oY startup be prevented without this modification? If so,
( ()
state why.
"T.A dA In Abo _ S . hibins h twd d be ( e_.Mb brior b -d o f -
- II. Will nuclear safety be compromised without implementation of this modification? If so,
( () -
state why.
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III. Is this modification necessitated by a commitment to an external agency or
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organization?
e A. To whom was commitment made?
w B. ' Attach commitment source documentation.
C. Required implementation date?- If so, ~ ~ ~ ~
r' state and attach source documentation.
. . , _ , ;; w ryp.: -
D. By whom and why? ,
W -
r E. Can commitment be deferred? '
L F. Consequences of deferring.
i G. Are we presently meeting the terms of the i
( requirement? If so, how? .
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ATTACH Page 2 of 4 SHEET v$EN OF_-
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P YES . NO IV. Will failure to implement this modification () .,
present or result in a significant, industrial '
safety hazard? (State hazard assessment result number). Attach support documentation. .
o il V. Cost Benefit: ,
A cost benefit analysis procedure is being developed by the Budget and Cost
' Control Section and the FSB t!adification Section. It is intended to provide a uniform basis for estimation of modification cost and an accurate cost-benefit ratio and cost on which we can base our division budget.
L The cost benefit will not longer be based on potential lost generatiron.
f Change requests in this category will be sent to EN DES for verification -
[ of cost by using the preliminary Design Change Request procedure.
rg Changes in this cateogry should be supported with drawings. Items falling -
under this criteria will include but not be limited to the following.
A. Will failure to implement this modification ( y) ()
a derate the unit? If so, state why. . _ _ , _ _
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. Attachment 6 ECN NO L67/r
- Page 3 of 4 ArrACHMENT 2c__
SHER 9 OF #
Rev. 9 .
P YES NO B. Is this modification necessitated by ALARA? () ( .
- 1. Actual dose rate experi'enced.
p 2. Expected dose rate experienced. '
'- 3. A hazard analysis must be performa.i. (Attach results).
- 4. Frequency of personnel entry. -
- 5. Duration of personnel occupancy. '
f 6. What will be the total dose received in implementing this modification? .
~
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C. Will major equipment failure occur from not implementinjithis modification? ~
'. ( -
()
. 1. Cost of replacement equipment.Un h
.g 2. Rated life of the equipment. -
3.
Required man-hours to replace. (List by craft and L' 4.
~
include engineering and Operations support man-hours).Un
. 4 d^
Coppquences of having this equipment out of service. 9 tsot !M Ausb $ Men E'[ e o (k%k-cre ans v4'S co 5 D. Will this modification eliminate significant manpower expenditure? () '
(
- 1
- 1. Detail method or present procedure and show man-hours
,.- expended for each major segment. .~
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- 3. State man-hours saved.
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AI Part III ECN NO. 44 wr r Attachment 6 ATTACHMENT Z ~
Page 4 of 4 , SHEET _IO _op_ /t Rev. 9 -
ES NO VI Documentation Change Only () (
[. *
- 1. Is this change related to physical changes in plant configuration?
How? Explain fully.
- 2. Does this change affect only a controlled drawing or document?
Give drawing / document identification. .
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B2 5 861017_504 QA Record ATTACHMENT A SEEET 1 of 7
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MODIFICATION CRITERIA No M'l- G7 i 6 -01 -
TIttE ,REQUCE OVER(.OAD OM STDBY
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SYSTEM NO./ FEATURE 67 ( STAM DSV DS L GEM DISCIPLINE INTERFACE INVOLVED '
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. 1.3 Scope of Criteria 6 EE. SHT, To '
1.4 Is Quality Assurance Requiredt YES
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1.5 If yes, give esfety classification of the modificatica C .L. A s s 4 E.
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, 2.1 Fua'ctional Requiremente THis Mob (01(1. REbtlG QAOlMG 00 blESELS Aub SATISFY REG. .
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l DIVISION OF WUCLEAR ENGINEERING (DNE) SECTION VII SEQUOYAR INGUEERUC PROJECT (SQEF) YARIANCES/ EIFANSIONS FROJECT MANUAL NEF-3.2. REVISION 3 ATTACHMENT A SEEETfa,of 7 NCDIFICATION CRITERIA NO. M7.-0f7i6 - 04 4.3 scope OF CRtTERI A FOR A LoS5 oF OFF5(TE PotDER COOCURREMT (0tTH AM 6l A DD PH A-6E B cot 0TAf 0M E O 160 LATIOM THE FULLOt0lud; CHAO6E6 ARE REOutRED.
i.COOTAiOMEOT $PRA9 PUNP, csp CLR FAO 4 6PR.A4 HBR.
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PROJECT MANUAL REF-3.2, REVISION 3 4
ATTACHMENT A f
SEEET 3 of 7 MODIFICATION CRITERIA NO. Mt- 67M-Of 2.0 DESIGN BASES (Continued) p 2.3 Invironmental Requirement. MILD EOVIR O OM EDT' (PER 47 E ZM -01 EDVIRONMEPSTAL DLO653 i
2.4 Instrumentation Requirements MOME D .
1 1
2.5 Electrical Requirement. ' c.LAS S 46 REGUiREMEMT6 614ALL BE MAIOTAIMED , '
, 2.6 Mechanical Requirements klO M E .
i 2.7 ', Civil Requirement. SEISMIC 00 ALIF. 0F ADD'L. TIME DE(Ay/
R3 aux RELAYS OM SHTDM Bb REuy LO6IC PML .
2.8 Regulatory Requirement. REG. 6UIDE i.9 RO 4
1
? o 2.9 ~Special Logic for Operation '6EE f.3 (scope OF CRITERIA) 2,10 Special Malatenance MOM G !
. I
! 2.11 Other N0 M G, 4
l SQEP Aug. 12, 1986
- t!
9 - l CEP.06 - NEF.3.2
. ~ . . _ _ . - _ - . - - . . , _ _ . - _ _ _ . _ , . _ - - . _ . - _ _ _ . _ - - _ . _ . _ - . _ . -
DIVISION OF NUCLEAR ENGINEERING (DNE) SECTION VII SEQUOYAR ING MIER MC PROJECT (SQEF) YARIANCES/EEFANSIONS PROJECT MANUAL NEP-3.2, REVISION 3 j ATTACEMI3IT ,A ,
SEEET 4 of 7 noorrIcaTIDs cRITInzA no. Mt-6116-Oi 3.0 TEST AND INSFECTION REQUIREMENTS ,
ERE If the required infossation saa be found la esisting TYA documents, s'ive ' ~
document number only.
p,g, goo p gg 3.1 Componene T..tlas ^'""^" ^ ' TESL OF TIME DELAY / AUX. RELAYS ,, ,
Aub ASSOC, CouTROL 0.(RCUn~5 FOR FUNCTIOMAL OPERASILITY. 1
^
3.2 System Testins 5 . 2'"2 5 Pnrr
- 95 3.3 Inservice Inspection PERIODIC IMSPEC.TIOM 15 REQ'D TO ASSU RE 1 1
- PROPER -OPER ATick! 0F TIME DELAY RELAYS .
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[ PROJECT NANUAL NEP-3.2, REVISION 3 ATTACEMENT A saEIT 5 of 7 1 .
- MODIFICATION CRITERIA 50. MZ- M155-Of 1
i i 5.0 CEECELIST OF 70 TERTIAL EFFECTS W DESIGN DOCUMENTS .
Y = YES N = NO
~ '
Data Sheet j Mfected Required Y/N Y/N
- 1. Safety Analysis Report (SAR) affected Y (drawings or text)? gg y,3,4(,2
- 2. Technical specification changef. 1/+ 5-31 MM) N i 3. Retest scoping document required?
- 4. Seismic analysis required? Y
- 5. Condition Adverse to Quality (CAQ) report (NCR/PIR/SCR) required? Q
- 6. Security system modified?
N 0
~
-, 7. Euesa fatter review required? . .
?
g i '8. Pipe rupture analysis requiredt..
g
- 9. Vendors involvedf,
- 10. Fire protection or Appendia 1 analysis? Y
- 11. Equipment environmental qualification analysief M
- 12. Electrical or physical separation , analysis? Y
- 13. Flooding evaluatloaf N N P
- 14. Radiation shielding and/or As Low As Bessonably Achievable (ALARA)1 '
- 15. Reviston to Eavironmental Impact Statenient (EIS)
N N I required! ,'
l ;
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5.0 CHECKLIST OF FOTENTIAL EFFECT! ON DESIGN DOCUMENTS (Continued)
Y = YES N = N0 ,
Data Sheet ufacted Required ,
T/N Y/N
- 16. Impacts other analysis or calculations? Y I
- 17. Occupational health and safety considerationsf. N N
- 18. Revision to state and/or Federal licenses or permits?
- 19. Drovings (including Environmental Data R3 Drawings)?
- 20. Bills of asterialf T T
- 21. Construction specification?
- 22. Instrument tabulations?
- N N
' ~
- 23. Q-List? N N
- 24. Systes description? .N '#
N
- 25. Vendor documents - new or revised? N N N3
- 26. Protective Relay Setting Sheets to be revised? N i 27. Electrical Penetration Protective Devices N N
. affected?
l l
28.
0 Non-1E load isolators' affectedt
- l 29. Fuse Identification Progress affected? N
- 30. Revision to design input required? '
- M N *
- 31. Procurement-related documents (e.g'. procurement R3 requests, requisitions, requests for: delivery.
y* y*
and certified design specifications)? ,
- 32. Environmental Q'salification (EQ) bindera and/or N 10CFR50.49 list?
N
- 33. Pipe stress analys'is/ evaluation required? N N
- 34. Component / equipment selente qualification required? Y Y ,
SQEP Aug. 12. 1986 12 OEP.06 - NEF-3.2 -
I e ,
e DIVISION W NUCLEAR ENGINEER 3C (DNE) SECTION VII SEQUDYAR ENGINEERING FROJECT (SQEP) ' VARIANCES / EXPANSIONS PROJECT MANUAL NEP-3 2. REVISION 3 i
ATTACEMENT A-SEEET 7 of 7 noorrICATION CRITERIA No. Mi- 67 f 6 -Oi
6.0 REFERENCES
6.1 List of Required Design Input (8ee Checklist. Attachment I)
DSL GEM 6EQUEMC.E LOA 0lM6 CALC. Bt87- M - O'316'- 701 -
Mcc coMT ctRCulT (MAX LOABIN6) B19-%- Of17-30i i
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6.2. Other References (if required) ~
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QA Record TENNESSEE VALLEY AUTHORITY
'
- DIVISION OF NUCLEAR ENGINEERING ENGINEERING CHANGE NOTICE NO. LG*716 BRANcs M N DATA SHEET NO. /
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--...+-. I UNITED STATES GOVERNMENT QA Recml Mcmorandum '
TENNESSEE VALLEY AUTHORITY B25 '861015 028 To : P. R. Wallace Plant Manager, ONP, P08-2, Sequoyah Nuclear Plant (Atta J. . Sullivan)
FROM : D. W. Wileo Project Enginee:r, Sequoyah Ecgineering Project. DNE, DSC-E, Sequoyah uclear Plant
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SUBJECT:
CLEAR PT. ANT UNITS ld1 - ENGINEERING REFORT FOR CAQ SEQUOYAH REPORT NO Sct. 5Qd EE6P4M F-$ REVISION II
- The original Engineering Report (ER) describing the conditio for the identified CAQ is attached. Please review this report for potential reportability under 10CFR21, 10CFR50.72, and ')C FR50.73. Please document your receipt and handling as requested by completion of the return receipt below. , l dr bfs e let _
)'
- D. W. Wilson
. VAB:JAS Attachment . l ec (Attachment):
- RIMS . si. 'M t ' !
B. L. Jones, DNE, DSC-A, Sequoyah J. A. Raulston, W10 C126 C-K L. Elliot , DNE, DSC-D,. Sequoyah'
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- D. W. Wilson, Project Engineer, Sequoyah Engineering Project, DNE, DSC-A, Sequoyah Nuclear Plant P. R. Wallace, Plant Manager, ONP, P08-2 Sequoyah Nuclear Plant We have received the subject CAQ Engineering Report for determination -~
of reportabli.ity. l
- P. R. Wallace .- l
,.' cc: RIMS, MR AN 72A-C H. L. Jones, DNE, DSC-A, Sequoyah
. J A. Raulaton W10 C126 C-K d 5. bublev,. DNG , WM11L c -4 C T. llin' . 04e, DGr_ p' sewy.L SQEP - Sep. 10, 1986 DE04;JS6230.04 Buy U.S. Savings Bonds Regularly on the Payroll Savings Plan
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6 RIMS Accemun Nustibe:
ENGINEERING REPORT ER Hee.
1 '"'s"N"''""
iuv ie U.r.sion i Orqanuation for 04 Piano j
Sitt LJens tIIJf % t. eaitJL1 arat! (Jete Not.tsett Lf)l pgyg ,,g g n g g ( ),,g , j i
Pf alit anal Viist c AQ fig. Jus t No and New SQN Units 162 Jig s; wit H 9/9/gf !
gg SCR SQNEEB8629 R3 ' <
=a os,m,,,, w,...ent 6,e cAo isee Note i i
[g The diesel generators at Sequoyah Nuclear Plant will have an engine failure (en);ine CB overload) if the random loads of the generator are applied at t = 30 seconds. !
96 K2ximum total load (starting and rtinning loads) at the t - 30 seconds cannot
)
At present time, a loss of offsite power with a safety injection I$ exceed 4482 kW.
(SI) and Phase B isolation, the total loads at t = 30 seconds are:
LA-4563 kW, ;
23 18-4636 kW, 2A-4650 kW, and 2B-4925 kW. (see attachment 1) J
'See Note 2 on cane 4 tot comuteting Part B Par a d continuets on tid =ert ? anit .4*
Yes ICL Nucicae Planis Only)
""e Dat, ne F a.iu,e E valuainan q/A Preparat un of Failuse I SAtt 6teviseun HettuaruqP T 'S No No Evaluat on is teuveredP
('
Conc'usions (See Note 31 1 See attachment 2
- i 4 J ei t3 3Lu {,
QZ e iD Recommendations (See Note 4.1 'l i j a- See attachment 2 f
Suggesteis Coerective Act on a Implement recommendation 1 before unit 2 restart. Implement recommendations 2 and b, 3 dur tg first refueling outage. This is based on memorandum from W. S. Raughley to D. J. Wilson dated 9/29/86, B43 860930 901, attachment 3.
Cate Fa.sure Evaluation Heceived Date Management Notified Operational Limitatsons/ Actions Justification For Continued opeeation c
.9
$3 2 t$ 5 Conclusions D5 3:
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Det.cency Adverteiv Af fects $4fe Operation of PlantP Ves No ONE Contact Aputowed 6, and Date Prepared 8v and Oate
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- Part 0 (Continued)
ER Rev. ! CAO Report No, and Rev. SCR 3GN EEB F629 R3 Page 2 of 4,
- 1. Tabulate Data on All Failed and/or Affected Components. Structures, and Systems: Geve descriptions, model and
~
manuf acturers' numbers, and original and revised design criteriidndTor specifications. (See Note 5 i Diesel generators 1A, 1B, 2A, 2B, and C-S Contract Nos. 71C61-92652 and 74C63-83090 Vendor - Morrison-Knudsen Company, Inc.
l
- 2. Failure Mechanisms of Af fected Components. Structures, and Systems: State whether each affected component, ,
structure, and system became open or closed, inoperative, oc shorted; or had shortened life, reduced accuracy, increased l drif t, reduced capacity, etc. (See Note 6.)
Exceeding the diesel generator's transient power capabilities will cause the system l frequency to dip below Reg Guide 1.9 limits and can cause the engine to stall.
Simultaneous start of ERCW and AW pump motors will cause voltage drop to exceed Reg Guide 1.9 limits and can cause inadequate voltages throughout the power train.
- 3. Alternate Uses and Generic Imolications: Identify alternate uses of the components, structures, and systems in the plant. Discuss genenc implications. (See Note 7.)
t Alternate uses do not apply. Generic implications have been addressed by Potential Generic Condition Evaluation Memo B43 0418 918.
I
- 4. Cwoonent. Structure, and/or System Failure Models): Give description and extent of effects of failures on each component, structure, and/or system involved. (See Note 8.)
Loss of a diesel engine due to transient overload can cause loss of a safety-related power train. Inadequate voltages in the auxiliary power system can cause motors to stall and motor controllers to operate inadvertently.
d Par t ; (Contmm:dl CAO Report No. and Rev. SCR SONist186.'9 10 Page 3 of 4 ER Hev. I
'a Cause of the CAO: Discuss what the CAO was due to, e q., a program t>reakdunn new acquiation, an,elysis or design cour, test sesults showing a deficiency Jntl/Or fJilule to meet design CriteriJ and/or lintt. haw specifications f nthule Calt;ulations, asialysis results, test results, and/or pufchase requurments not met, or uther luses. (See Note 9 ) l Failure to establish an adequate system of procedures to ensure,that calculations / studies performed by EEB are updated and revised to support the di sign as changes are made after plant operation. This was identified in Office of Quality Assurance Deviation Report D51-A-84-0006-D01 dated July 2, 1984. Also
( previous analysis erred in assuming that the worst-case loading would occur for a
- concurrent SI and phase B containment isolation.
- 6. Consecuences on Plant Design Functions: Discuss effects of failures on all involved component's, structure's, and system's abihty to perform their plant design functions. (See Note 10.) .
Engine overload can cause the engine to stall and cause the onsite power systeri to be unable to perform its design function. Also, the auxiliary power system's ability to perform its required functions cannot be guaranteed with voltages outside of its design basis (ANSI C84.1-1970).
)
1 i
- 7. Justification for Conclusions in Failure Evaluation: Discuss the reasoning based on the information above which leads to the conclusions stated. (See Note 11.)
The loading at each sequence step was determined in Diesel Generator Loading Analysis, SQN-E3-002R3 (B43 860827 909). The diesel engine's capabilities were provided in Morrison-Knudsen Report No. 6957R Rev. 1. The generator's capabili tice were provided in NEI-PEPI Report T-1016. Comparisons of the maximum possible J oad at each step with the diesel-generator's calculated capabilities demonstrated t he i potential overloaded conditions. The worst- case loading used in the analysis was the simultaneous start of the process-controlled loads and the containment spes y
- pump. All other loads that could be running on the diesel-generator were also considered. This is a very low probability event. DNEl - 0551W Prepared By and Date Coordinated in Site Director's organization with:
%). @1.4wk>ak tohlss % Smith erified By and Date Disciphne Lead Engineer (s) and Date I I W 10 t i Y(
Approved By and Cate I fo/g/gg gg W nNr; V' "" ,
I fQs p-
P.sge 4 of 4 NOTES ON ER FORM BLOCKS .
- 1. Provide a definitive statement of the CAO. The NCR/SCR description of the CAO is tu tse restated vertiatun or espanded for clarification to ensure the statement reflects "standalone" documentation of the CAQ.
- 2. Various items in Part 8 (pages 2 and 3) are to be completed to support the conclusions and recommwndations. Allitems on the form (pages 2 and 3) are not necessarily applicable to each CAQ. Add sheets and data as necessary.
- 3. Explicitly state the conclusions of the f ailure evaluation regarding the at>ility of the
- af fected component's, structure's.or
' system's capability to perf orm its require..d... design function. ..
- 4. Recommendations in this block (or elsewhere on the ER) should Movide DNE'slesfiudgment as to what is needed to correct the condition. Recommendations are to reflect suggestions that correspond to the stated conclusions of the tailure evaluation. The riscommendations should rot be worded as requesting work authoritations or funding for additional work.
- 5. Other affected components, structures, and/or systems (CSSs) not specifically identified in Part A of the ER should be identified here.
- 6. " Mechanism'* pertains to the mechanics of individual component failure (s).
- 7. Alternate Uses and Generic implications: Identify alternate uses of the af fected CSSs in the plant, if the condition has generic implications, they should be discussed here. ,
- 8. " Mode ** as used here pertains to operational manner or process.
- 9. Self explanatory.
- 10. A conclusive statement is needed here on the ability of the af fected CSS to perform itsintended design function with the condition documented in Part A of the ER. Plant safety aspects (i.e.. safety evaluation) are not to be considered here.
1
- i. . . . .%.... . ; s:, , . :n .. . . . . . , . .. ...;, . .,. ,, ..,. i.,..,,e .3,,e ,**sm ahle hawd unon the evaluation findings and statements.
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Attachment 1 i Sequoyah Nuclear Plant Units 1 & 2 l SCR SQNEEB8629 R3 Definitive Statement of CAQ (continued)
Revision 2 of the DG load analysis (843 860827 909) has identified heavier loadings for the condition of a loss of offsite power with a delayed SI and Phase B isolation. Also in R2 of the load analysis, it was determined that .
Ioad sequence timers for the ERCW pumps are reset by an SI in either unit. .
An SI in one unit can cause the simultaneous start of the ERCW and AFW pumps in the other unit. The voltage dip for the simultaneous start is 30 percent, which exceeds Reg. Guide 1.9 limits (25%).
1 1
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sheet 1 of 2 Attachment 2 Sequoyah Nuclear Plant Units 1 & 2 SCR SONEIS 8629 R3 CONCLUSIONS The diesel engines can be overicaded for a less of offsite power with a SI and phase B containment isolation during the containment spray pump start. This can cause the loss of the auxiliary pcuer train. For an SI in one unit and a loss of offsite power in the other unit the ERCW and AFU pumps can be loaded ente the diesel generator simultaneously. This would unacceptably degrade the class lE auxiliary power system.
RECOMMENDATIONS
- 1. To ensure that the maximum transient leading is within the diesel generator's capabilities, for a 1 css of offsite pcwer concurrent with a SI and phase B containment isolation the Eclicwing is recommended.
A. Change the lead sequence time delay for the centainmsnt spray pump motor from 30 seconds to 3 minutes. This allcws the diesel engine to reach it's hot rating before the containment 3
B. Trip the electric board eccm air handling unit on a loss of offsite power and containment isolation restart after the containment spray pump start.
phase B signal and f{
C. For unit 2, train A, assure that the electric beard reem compressor can not start at the same time as the shutdcwn board room air handling and chiller pacl: age. It is acceptable for the electric board room air handling unit and compressor to start at the same time. And it is acceptable for the shutdown board room air handling unit and compressor to start at the same time.
- 2. For a loss of offsite power with a delayed SI and phase B containment isolation, in addition to the previous recommendations; A. Change the Containment Spray pump sequencing logic so that after the diesel engine reaches it's het rating the 30 second timer is reinstated.
n l
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F sheet 2 of a [>.
Sequoyah Nuclear Plant Units 1 & 2 SCR SONEEB 8629 R3 B. Trip the follouing loads on a 1 css of offsite power and containment isolation phase B signal and restare after the containment spray pump starts;
- 1. electric board room compressor
- 2. shutdown board room unter chiller packages and air 3.
handling units control room air handling units and compressor ff
- 4. M80V board room air conditioning system C. Trip Reactor Vent boards and Control and Auxiliary Building Vent boards lA2-A, 1B2-B, 2A2-A, 282-8 on a loss of offsite power and safety injection.
~
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change the ERCW control circuit to disable the cross-unit reset of I the load sequence timers.
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- _ --- " ~ -@___
SCR .sONEE68co 29 :43 Affochmed 3 ER Rev I B43 '86 0 9 3 0 901 TO : D. W. Wilson, Project Engineer, Sequoyah Engineering Project, DNE, DSC-A, Sequoyah FROM : W. S. Raughley, Chief Electrical Engineer W8 C126 C-K DATE : Septembe'r 29, 1986 Record
SUBJECT:
SEQU0YAH NUCLEAR PLANT - DIESEL GENERATOR ANALYSIS The purpose rf this memorandum is to provide my position with regard to those load modifications identified in the SQN diesel generator loading analysis.
The SQN FSAR Chapter 8 (pages 8.3-9,10) and the SQN design criteria " Normal and Emergency Auxiliary AC Power System" (No. SQN-DC-V-11.4.1) identifies three diesel generator loading sequences:
- 1. Loss of offsite power (LOOP) concurrent with a safety injection (SI) signal,
This analysis has addressed each of these sequences, with corrective action i required for each sequence. However based on a review of internal NRC
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significantly contribute to a core meltdown, I conclude that only the modifi-cations for a LOOP concurrent with an SI should be performed prior to restart of unit 2, with the remaining modifications scheduled for the next refueling outage.
(L b_ M W. S. Haughlp O JDH:BW -
Attachment cc: IIMS, SL 26 C-K, w/1 R. G. Domer, W12 AS C-K, w/1 J. A. Kirkebo, W12 A8 C-K w/1 G. T. Hall, DNE, DSC-A, Sequoyah, w/,1 A. Priest. O&PS-4. Sequoyah, w/1 Principally Prepared By: J. D. Hutson, Extension 2928 DNE1 - 0721W j
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. .. . MVOJ j m ,, ,,. . , on napanut GEli!ER SETHE5Dfijip , ,,. .pP 0,,0/ , g UNitse etAtes D W " j' g '
L 1 NUCLEAR M10VLAYoMY Commission m anu. aron.e.s.seems "
April 20,1943 ,
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70Wft$YlitMSBRANCR Y'[h ' ' '
MEM0AANjKLM704: 788 Members ' fh .
3VtJtCT:
Probability of Core Melt Due to loss of offsite .{
rower sunseovent to e i.or.A and MA5 Nelet = l Bener_te Issues eli e #15 ~
I
~
From time to time Pll receives guerries frem other offices en specific '
toautomaticallysequencetheretuiredEctsleadsontheesc '
4 LOCA with the subsequent loss of offsite power. . =
1 This issue was addressed b , ;
^
in 19 the staff astime.
Technical Issus No. 4 in '
NURIG m , ,,,01{ll s. g.ubitsh.ed
........oo.,.- 4.- At that the it.ff **d a -* --ad ~ '
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eennsereo es e design basis ev.ent.".- .w precluse its being At the request of PSI. a systematic study of the above subject was pe W R$l and ARAS (see attached memos). It sho s'
en of this study as sta*ed in RAAl's seme (uld be noted that the senclu.
from A. Thadant to M. Srinivenan dated April it 1983) affirms the staff's otr11er deterni. '
natten in NURtG 0138 that the frequency of *%. this eve ts a statible core salt initiator." .
p amus > ;.$[-
N. Srinivasan power systems Branch "!
Olvtsfon of Systems Integration 4 En410sufea 1.'.-
i As stated ' .: ..:.
- .A A.
l
'84: 2.~Nattson .
i L. Aubuatein A. TMdant .....s..
- h. Sheren '
M. Nineers .. -
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. 10/14/65 l o '_ l o l M-- --' #*"
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P.009 f' SEP.24 '96 09:23 HRCHESSAGECEHTERBENE56RiiD ,
p wenten eta?ss
< NUCLEAR REGULATORY COMMitst0N -
i maammetou,n.e, asses k o ,.e s .
}.
. MR 18 W1
- .s.
IEMORAND'N FOR: 'trian theren. Acting Chief .
Asatser Systems $rench -
FRCH: Chief II. Brinivanan.tranch Power Systems - -
SysJtcT: pa04A11L17113 AND.COMitQUINCES OF LOCA/LO55 CF 0FF5171 ' "
POWER (LOOP)SEQUINCl3 Ve have been discussing with the Reitability and Risk AssessmeM trench * -
(RRA5) of DST the need to perform systematte studies of the probabilities aM sensequences of verfeus LOCA/ LOOP seeuences to dotar.atne if -
esquences other thna esincident LOCA/ LOOP are of sufficiently high i probability to be sensidered as a design bast event. In essence. this feevest focuses the staff as Technical by)ite Power subs Issue Number 4 in NWAtG on 0138aenknown "Less of Offsissue addressed Manual lafety Injection Reset Fellowins a LOCA." In the event of annual -
reset of the 51A5 followed by a less of effstte power durint the '
injection phase,istons et leads . For cons sar than~the dost n beroeptests(ceinti eierator action may be reevired to restartr LO Westen varistiens such u neener in.M aa e 4..co.. a, dent a teuteLOCA/LQQP)I.
ner et ai >
ibsu.
To limit the scope of the RRAS satlysis. it becomes necessary to establish the time frame within which the probabilities and tensequences of vertogs LOCA/ LOOP tequentes are to be analgnd. Since the nature of such a determinatten appears to fall within the scope af til's expertise, we ,
ask your assistance in this matter te provide us the following , ,
- 1. The ties frame (starting with a LOCA initiation) after which it =*w.'
(a permissible to manua,1y reload diesel sentrater buses ..
hassuming subsotuent LOOP etterrent s) with retutred leads to .
T..
metatnin the p' tal in a safe tendit(ion. *
- f. The time frame (starting with a LOOP) after which theuld.a LotA .'*-
subsequently escur aanval estion is permissthis It Pellien from c; safe shutdown leads to ECCS leads to mitigate the LOCA. , ,; -
' ' b~
gce EntactslW" -
gg a.3.; C pia . . .%
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- 5EP.24 '06 09:23 HRC NESSAGE CENTER BETHESDR MD lf
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: i We intend ta use ,#ve response as a b4 sit for 11atting the steps of RAA3
] )I analysis sa this so.iect. * . . , '
If you have any tutstions regarding this, plasse contact QR thopra 44 mil 483. .
. & - . y l Chief '
e M.Stinivasan.tranch Pimer Systens -;
D'Witten of Systems Integration .
l tes A. Mattsen . ,
L. Av6enstein - i l 8.Hanauer *' . l N. Ernst . * .
T. is -
A. dani .
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. . UNIYe0 eTAtts NUCLE ARwas REQUL ATORY COMMISSION w arew.o,s.seen '
JP'If M 1
s NgMORANDUM704:
M. Irinivesen Chfef power lystems trench Division of systems Integration i
FROM:
, A. Thadent Chief -
l Reliabilit & Risk Assessment Branch Divtsien o lafety Technology 8UljtCT:
,. PA0BASILITY OF CpRt MELT DUE TO Loss CF ON5!TE POWERSyl$lQUIN1TOALOCAAND8!A5A!5ff -
5 Your note dated January 27, 1983 transmitte of 1943 frea 3. Sheron ll.LOCA/Less to M Power. $rInivasan of Offsite on "d to us RSB's some of Janua
$44uences."
tenservatively saiculated the frequency of core salt due to a'large,treatIn res LOCA where the safety injection actuation signe) (51A$1 is reset i minutes after safety in.iection actuation ana effsite pone is !sst efter $1A5 Nset.;
We calculate this frequency to be approximately 4.0 x 10=#/AY.
Ps110 occur with'nwing twohminutes Intge er medium LOCA, if a loss of offsite power (LOSP) Joes -
the operstar- abey-reset- the i!A$r -Afte~ r reset of 4
$1A8.
leads subsequent would be 1eW LOSP " wou._ld
"-- ' result in no safety injection (eniv the MaWo'.
.oaos we various si,L6 components on(o the emer.gency buses. .
.. .wr Load eenuaaty ehedding of nonessential the diesels. leads may se required at some y ants.to prevent everleading Since we are considering LOSP after $145 reset we are not grid niability.
tone!ened withBefore LOSPl!As immediately reset after reactor trip due to a s,hallenge to the automat'celly exentne loaded onto the diesel,generatorsthe ECCS components would be on LD5P. We only have and Ally a meno largeofand Jannrymedium ll,1944. break LOCAs based on y,our note of* Jaheary '
,, . 3. ,
To calculate the core melt frequency, we account far the frequency ' J$.
time Intervete. the probability of operator atesel rous - error .+ whic recover %nerator offsit. , ewer operation serer. with 13.LOCA
..r. leeds. and the probabi)ity of .
- ['
- 1. damased. '
sent. i s. een, c. F4, cod
. ._jns.. _
10/14/05 16:15 P. o --- - - ~ ~
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., p. P,.,0g
- te We sporeximate the probability of loss of offstte power during a tfee intervat T' by taking the product of the less of offsite power frequency (0.2/4Y) and the time interval. We assume that a
the frecilency of a larg's break LOCA is 1 x 10-4/AY. (Table!!I6-9, bl45H1400) .
e if a less of offsite power occurs in the interval from the '
- resetting of the $1A8 (at 2 minutes into LOCA
the LOCA, assumed withcoro degradation Will occur since t e aparator isto 30 minutes into !
probabtItt l CA lesde onto the die el generators.1.0 to not Icedshed and resequance the t ne frase.within which the operator We must are uncertain as to the act to restore AC power to fAteaLOCA.revent core salt if AC power is lost between t and 30 minutes e .
during the period from 30 minutes to 8840 minutes ($ days) after the -
LOCA, the saxteinue time interval within which power aunt be restered prevent of offsite powercareis dgradation unity within the is l il sinutes$ minute periodand the i
e t i dvring the per' fed from 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> (5 days) to 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> (1 month),
time within lineer functionwhich AG power must be Mcovered is represented by the 40 afnutes
- _t, _ _ _ -
.i.w.en o649 minutes and 43,200 minutes 1 month) 1 powerinone,totwohour) sis 0.5.(page !!Ir 72 WASH 1400 . The .
o -
the operater sentributes to ifesel generator unavailablitty se fe)1 Probability of OperatorIrror .
Given LOCA and * ' MC. r Subsequent Lolp Time (str.s. Af ter 1,0CA When LC1 Decurs . si.s.
1.6
- y , A.
9 0 to 30 "
.38 80 to 440
,1 g 240 to 8440
.61 p, ) 8640to43,200
,' 7 N
.)..sy['7.v^
O' _ _
t
. gh l g.. s ,.;,
FR0t)
._.a ;.e s.s..A g g. .g. .. :rq li<gg ::s. A.
- p. .
t
. ay r . 4 we avu 11w nannut canien enIHttun nD .yggt P..J 0.50 iZ i
I
-)-
6 These probabilities of operator error are similar to those used in the }
- ANO-11 REP. study (see Table 7*1. pg. 7-13. NUA!Q/CR 2787). The AHO 1 IREP nuabars are a function of the time available for operatof tetion. ;
The AN011 REP st',dy would assign a probability of 0.1 for operator error in the ir.terval from 30 to 240 minutes since we 6elieve only 15 -
minutes are available for operator action. '
~
e after one sonth, there is sufficient time to correct any failure.
end therefore, the sentribution to core melt frequency for the '
period from one month on is negligible.
Using for corethese assuntions sett following weI.CCA a larce calculate where athe frequency $1AS is reset 2 minutesof approx (
after safaty in,jection actuation and offsite power is subsequently lost. . 1 We believe the negnitude of this frequency is sufficiently low to exclude '
this series of events from consideration as a tradtble core melt initiator.
hbh W' , .[ .
.- Chief .'
Ashe't Reliability C. & RisThadant.k Assessment tra Division of safety Technology -
ce: F. Aowsome -
I I
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w m.wI,a .:..,1 A '4'..d.2ndr -I FROM 10/14/85 16: 17 P. 8 _ , _ -
i 357 39 *Ub U1321 H.Rc M p5RGE CEH,TES BETHESDA MD
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. g,.j NUCLIAR**RICULATORY = =, u. e==COMMissicN .
- ]-
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January IT 1983
- e , i
. 1 NOTE 70 A. Thedent, chtef', RRAs -
8VlJECT: P405Al!LITIII AND CON $tqutNcts CF LOCA/LDOP8tQUINCt1 ' -
NowthatRSShasdefinedthetimeframt(Reference
- 3. 3 heron't a .,
copy attachte for of the1/19/83 LOCA to Mr. 8rinivas .
esprestate RAA3's input os r/ LOOP egards the probab111 ties w's sequences,en would . - '
t, of su:h naquences escurrent. Such as assessment wt11 .
anable Pll to detensine if sequences other than .
j soincident LOCA/LQ07 should be considered in tha -
testen review. We would a response in thts subject. pprestate ARA 8's Strly d"M. (N t :
... cn n:. c a., .o.ei, m .
Attashfient: -
As stated '
l
. 841 J. Knight ' '
.,m'
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..,. er F!U'4$,,.JECOPT gy w.. n ' -
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- ) ,.
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I FROM 10elt<65 16 17 P. 3 .
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- SEP.24 '86 49:22 HRC MESSAGE CENTER BETilE50R MD
,,7 .P.007
, l ase% UNif s0 ffAfit s '
NUCl. TAR Rs0VLAToRY cCMMissioN l wAMlf.e700s. D. e.~ etill '
\ '"' ' WWt31983 ; -
l
- 0 MEMORANCtHFOR: M. 3rinivenen. Chfef. Power systems Bran,ch. DS! -
FROH: 5. theron, Chief, React. ' Systems tranch, 051 "
1 SUNICT: PROBAllLIT!!S AND CCHStQUtHCII 0F LOCA/ LOSS OF OFF31TE l
F0WER(LOOP)I! QUINCES This is in respense to your Apef113 sene etking for infore.stion .'
Mgarding the time frames of importance for a non.struiteneous LOCA/LCOP
' event for RRAI perfomance of probabflity studies.
For the first esse considered break LOCAs. most ICCS analyse,s(LOCA predict core Mflood followed by10 about LOOP),
minutes foi PWR 1arge after the event. These analyses also sensrally assume concurrent LOOP so the ICCs equipment has been as wentially loaded onto the emergency .
electrical busses' power 64 by the fesel oenerators. If a LOOP does not '.
occur, the ICCS equipment would a 1 start siesitaneoutly. As your memo ints out, if LOOP doesn't tecur and the operator manually resets the ~-
IAS fler the ap repriate criteria have been met thenaLOOP-(1fter ISg wogd ng t g ng sefeg,jnhgion unQ,he oper,stor takes long after the L90P can the EC the peak clidding temperature PChow be interru$ted wNhodheed '.
limit of 220 'F. and second whst is the paper length of time to assume for the operator to diagnose the LOOP and take estion to realign the ICCS loads.
With ngerd to the first question, e computer analysis was performed for a 1arte kreek LOCA for the sinna reactor which assumes that ECC5 flew is -
teminated during the switchover from the injection to the recirculation ,,..,"
. The resulig ' ndicated that at phase (10 minutes the end of an additional 30 minutet wafter the accident)ithout core FW, the averace -
tempertture was 80'16'F and intress< ne npidly. These results intica - -
i that for the above condition the peak eing temperatuns (PCT) would) ..
nach the maximum allowable valve of it00'F flow senses We consider this time perted to be tempatible with takine in 18 80 minutes after (CCt 4Dpropriate remedial operator action. Therefore the time frame of song interest for eerfernance of LOCA dirLt.34 minutes after LOCA escu/LO0p probability studies would be the .
rrence when the
'dt and the 46htoquense potensially mo,re severe.tytilable ,,,-
tire CONTACT:
s.Mann,xts4d1 rROM .
i.3, pgtgE ELE COPT .,,,,.,g.;/q. ,
GEST Y . . ." W
,.,,.. , , . . 7.
g- ...s . . .ill l . g,ia,g g g:ygtip
_ . - - . ......a...ae. e.e r.yyo
,- y1 4
l ..
f,l
,M. Irfatyssan -t* '
JAN I5 Igg ,
a With neerd to the second case (LOOP f4110wed by LOCALS tht Nietor would suost probably trip with occurrence of LOOP. A subsecuent LOCA -
would occur at lower decay heat condition. Therefore thin casa in less ) -
! sevare than the hnt case, and the results of the first sees wou'.d
&)
Cund the neicend cas3.
- ~ '
yQf Chief Brian ReactorW. 8 heron,tranch. 0$!
- s Systems ett R. Mattien . '
W. Sutler -
L * '
A. Rubenstein W..Thadent
. Lauben J. Knight *
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FROM .
10/14/05 16:19 P.I1 TOTAL P.I1 , .;.:,,..,_,,,,__.
- )
QUALITY INFORMATION REQUEST / RELEASE (OIR)
DIVISION OF NUCt. EAR ENGINEERING l INTsRNAI.USS ONLY l
"'"' ^"*%45 'AR 0 91 1 266 TO DOCUMENT NUMeER C. T. Hall nur ncf'_a enu u.
. -ro n .o .r ,,,
..,y i
PAGE 1 OF H. L. Jonen_ nMR nM. A . RAN 7 TYPE OF DOCUMENT I IREQUEST NEED DATE DATE 5 m'
___________________________________ ,m NT ANo uN,7 RELEASE REF. QlR SQN 1 & 2 REFERENCED DOCUMENTS AVAILAsLE IN ONE OF THE MIMs SYSTEMS ATTACHMENT TO THis QIR DOCUMENT IDENTIFYING NUMeER DOCUMENT ATTACHMENT NUMSER QIR SQNEEB86070 ,
B45 860826 255 QIR NEB 86126 860918T0310 O l l
l susJacT nTrert r=rvera rno e nan ernttrui r rvun not my ego , ge,ayu= - a ngu ,n.. 3 SYSTEMS AFFECTED UNIDTiifTIMId )
GJALITY INFORMATION REQuesTEtifRREAsED As a result of reference 1 NEB has examined the adverse impact of delaying the loading sequence forthe containment spray pumps un*.113 minutes after a design basis event. A response to the information request was provided in reference 2.
The current design basis event governing containment peak pre =sure is a double-ended pump suction loss-of-coolant accident concurrent with the loss of offsite power as are all FSAR chapter 6 and 15 events where a loss of offsite power is assumed. This requirement results in the current shifting of electrical loads to the diesel generators. The containment spray pumps currently load onto the diesel generator at 30 seconds. The original QIR requested relief in the loading time to 3 minutes. This 3 minute delay time would add 150 seconds to the switchover completion time and is acceptable within the current design basis analysis with the following limitation:
If the loss of offsite pcwor does not occur at event initiation or before the switch-over to sump recirculation time (before 2666 seconds), the 3-minute delay time is unacceptable. For a loss of offsite power following this time, the current 30 seconds delay must be retained.
As noted in QIt NEB 86126, the new reduced ice-weight analysis will not allow the requested 3 minute delay without modifications outside of the diesel generator loading sequence.
6U w 8. kJ J mnoveo innamen cuisemuner smoimeen:
d M M E w.. '
/ ,e l M ~~77nu im
~
TVAIG NIO M /
// NES 09/10/86
,, a- g n ,,, ,,, a e, p. A 4 . I S e . D 4 E., D5 t - A , Sepatefh i _
._ T W. 8o be;rTs. e m 5ti c - ^
QUALITY INFORMATION REQUEST / RELEASE (GIR)
'E DIVISION OF NUCLEAR ENGINEERING i INTERNAL USE ONLY l
.s.
~
A"t #'" 'As n w a DOCUMENT NUMBER asx '
f To W. S. Raughlev. Chief Electrical Engineer, W8 C126 C-K OIR NEB 86132 FROM John A. Raulston, Chief Nuclear Engineer, PAGE 10F 1 W10 C126 C-K TYPE OF DOCUMENT DATE n REQUEST NEED DATE 9*I'N '
_________.__________________________ ,mHT ANo u,,,7 N REl. EASE REF. OIR SQNFEB86099 SQN 1&2 REFERENCE 0 DOCUMENTS AVAILASLE IN ONE OF THE RIMS SYSTEMS ATTACHMENT TO THIS QIR DOCUMENT loENTIFYING NUMBER DOCUMENT ATTACHMENT NUMSER_
TI-ECS-67 NEB 820728 236 860918I0635 b TI-ECS-88 NEB 850115 236 l susJacT l tOADING SEQUENCE FOR EMERCENCY DIESE1. CENERATOR SY5 TERM AFFECTED UNIO I SYSTEM ID i onsite power and HVAC QUALITY INFORMATION REQUESTED # RELIASED In response to the referenced QIR, it is acceptable to trip the electric board room air-conditioning system and control room air-conditioning system for ap g oximately 5 minutes-until the containeent spray pump is started following a loss 3offsite power and phase B containment isolation signal- "See referenced- documents;--- - --
l NE#An o l mEvitgoInt(EAsEsONK tj d' u g ' * / v .w w l W(pth GAY.b\
%EG (enAN6H CHIEP/ PROJECT ENG40&idal Q TVA 1dess10MWeist df #
//
INA A
es ' -- r nous.eL 3B c4 D. W. Wilson, DNE, DSC-A, Sequoyah T. W. Robes 6..-WS D181 C-K H. t.. Jonce, DNE, DSC-A, Sequoyah c _ _ _ . _
,e
~
, q .' . J. f. . *
}
QUALITY INFORMATION REQUEST / RELEASE (QIR) nh N ;gd DIVISION OF NIJCLEAR ENGINEERING iINTERNAL USE ONLY I
- Fyxof.cNO 1e , __
^
DOCUMENT NUM8ER
( TO OIR NErl861:'6 C. T. Ita ll . DNE. DSC-A. Sequovah PAGE 1 OF 2 enry .lones DNE, DSC-A, Sequovah DATE TYPE OF OOCUMENT August 13. 1986 NEED DATE _
. U. REQUEST..... ---- ..------------- . PLANT AND UNIT SONP - fil and I!2 lX l REl. EASE REF. QlR z REFERENCED DOCUMENTS ATTACHMENT TO THIS CIR AV AILASLE IN ONE OF THE RIMS SYSTEMS ATTACHMENT NUM8ER IDENTIFYING NUMSER OOCUMENT DOCUMENT 860915T0207 a OIR - SOMEEB86070 1
SUBJECT Diesel Cenerator I.ond Sequence Tine Delav ear Containment 9nrav "unns UNID / SYSTEM lD SYSTEMS AFFECTED 72 Containment Snrav Svsten OUALITY INFORMATION REQUESTED / RELEASED See attached.
l 1
1 i
l l
i i
I IN. Akl } m f APPROVED (BRANCH CHIEF / PROJECT ENGINEER)
F l.TVA18323IDNE4.
M k Lli L U ~ ' l D. W. W i l son , I"T . O T -A, Ses}uov.th '
' a lAtteshmentd / Rim SL 3 g T. W. Hohert D_ __D181 C _K___.._._,__
-A _ _ _ . _ __.___ ,,
7 QIR Nr.itB61/6 l'a m J nt 2 In response to the information requested in the referenced QlRp.I cannot 's (CSP).
approve a delay of 3 minutes in loading the containment spray j
onto the diesel generator (currently 30 seconds) after a design basis l event. This conclusion is based on the following:
The containment spray system is predicted to complete switchover to sump recirculation at 2516 seconds following a large LOCA with the present diesel loading sequence and ice weight. The proposed delay time would add 150 seconds to the switchover completion time (i.e.,
at 2666 seconds) and would be acceptable with the current design basis analysis. However, a new containment analysis is underway using a reduced ice mass. This analysis, when completed, will become .
the new design basis analysis for the plant. Presently, complete ice 9 bed meltout is predicted to occur at 2663 seconds in this revised analysis. Therefore, with the new analysis, ice bed meltout is predicted to occur before containment spray switchover is completed and thus no safety margin exists. A reduced ice mass (or no ice mass) concident with no containment spray could potentially result in :
an unacceptable increase in containment pressure. The absence of safety margin combined with analytical uncertainties and the potential for an increase in containment pressure will not permit a qualitative approval of a 3 minute delay in loading of CSPs onto the diesel generators.
i The water supply for the containment spray system switches from the q refueling water storage tank (RWST) to recirculation from the emergency sump when lo-lo water level is reached in the RWST. Therefore, raising the lo-lo level setpoint in the refueling water storage tank would allow switchover to be started and completed when increased ice mass would be available for pressure mitigation and would restore some of the safety margin lost as a result of the proposed reduced ice weight. Changing the lo-lo setpoint would thus provide additional safety margin that could be used to permit a delay in loading the CSPs onto the diesel generators.
However, the delay time available from changing the setpoint and the potential impact on the plant design basis and operating procedures (if any) must be thoroughly determined.
l
"' " DNE CALCULATIONS TITLE PLANT / UNIT _
Diesel Generator Load Analysis Sequoyah U1 and 2 PREPARING ORGANIZATION KEY NOUNS (Consult RIMS DESCRIPTORS LIST)
DNE-EEB-ECG Diesel Generator-Load Studv or Power Train Load Studv '
Each time these calculations are seausd. properors must ensure that the oresined (RO) RIMS acesesson -
> RANCH / PROJECT IDENTIFIERS number la filled in.
Rev (for RIMS' use) RIMS accession number SQN-E3-002 ,
"O 860207D0131 B25860204 300-ArrucAsLE DEstGN DOCUMEN'f(S) 81 860530A0008 B25860516 301__ _ __ _,,
.2.8 60903E00M a B43 'eb u o e t m w SAR SECTION(S) UNto SYSTEM (S) a R2 R3
} sit)B43 '8610 0 3 904 safety < elated?
Revision 0 R1 No O Yes S -
ECN No. (or indate Not Apptecable)
N/A Statement of Problem N/A N/A N/A Propered Evaluate the transient sequenced' Peter T. Bowman
- PTB*[ m /gb . load applied automatically to each Checked D-G power train for the following C. R. McIntosh* RJM* f.h. Jconditions:
Reviewed
- 1. Blackout loss of offsite R. P. Reese* GRR* aM ' .,yJD power MS)%dQg, Approved ) 2. B0 with Safety Injection G. T. Hall /R GTH*( , d"- Signal (SI) containment R2 Date p "
/ isolation phase A.
7b6 /o d M 3. B0 with SI containment isolation phase B.
List all pages added See Rev
=j by this tevision. 58 % none 4. B0 with delayed SI contain- p I
,) List all pages deleted 217 th'u ment isolation phase A.
,g; by this revision. None 222 none 5. B0 with delayed SI contain-j!l List all pages changed See Rev ment isolation phase B.
by this revision. All Log 10e Abstract These calculations contain an unverified assumption (s) that must be verified later. Yes S No O g gfi,,lp first thret ;
Each Class 1E DG power train was evaluated for the ?tve. conditions stated !
above. The loads on each board powered by the DG of each power train were i evaluat g eration sequence and operation time. The loads were then sunused starting and running KW and KVAR's for each loading time beginning with O seconds to 120 minutes. From this sununation, the worst case sequential loading on any power train for each of the three conditions was determined to be power train 28. This worst case loading was evaluated by the diesel generator contractor to determine capability to accept and carry sequenced and random loads within allowed voltage and frequency limits (attached).
The contractor subsequently determined sufficient capability with a reduced load. Power train 2B was re-evaluated for condition 4 and 5.
R2 l If ERCW pump is started at same time as auxiliary feedwater pump (see j condition 1 page 10e) diesel will be in violation of voltage variance per Reg Guide 1.9.
- 0riginal signed by J. 2. W.. _ m,8 - olli3 Y C-K O
O user.fiim one store enievieiions in aims serv co ceaier. uncrofiimoneasoirov. O S Microfism one return enieviations to: J. D. Hutson, W8 Bill C-K Address ee: RIME. SL 28 C K
REVISION LOG.
Title : Diesel Generator Analysis
" * [,* ' * "
DESCRIPTION OF REVISION 4,,7,,o l
1 Major revision to study correcting unverified I assumptions, of motor data, revision to vendors f analysis with correct regulator and lo6ds. Added additional unverified assumptions.
2 Analyzed delayed SI, containment isolation phase A&B, to find which case will have the maximum transient .
load. Provides corrective action for SCRSQNEEB8629 R2. This study is revised to reflect the effect of
" main feeder cable and transformers losses.
Pages added by this revision 10a-10f, 35a, 80a-80af, 81a, 96a-96e, 117-163.
Pages changed by this revision 1-10f, 35a, 80a-80af, 91a, 96a-96e, 117-163.
3 Revised to add list of changes required-to ensure l f transient loading is within the diesel generator's l
, capabilities for a loss of offsite power concurrent l with a phase B containment isolation. (Changes for l conditions 1 through 3 are being implemented on ECN I L6715. Changes for conditions 4 and 5 will be implemented on next refueling outage.) See memo from W. S. Raughley to D. W. Wilson dated September 29, 1986, B43 860930 901.
i 4 This revision incorporates ECN L6715 which changes the loading time of the containment spray pump from 30 seconds to 3 minutes It also trips the electric i board roon AHU on a lo;s of offsite power and a phase B containment isolation. The AHU is restarted after the containment spray pump starts. 'ECN L6751 which changed the stroke time of valves 1 & 2-LCV-62-135 and 1 & 2-LCV-62-136 was incorporated by marking the computer printouts. These valves are stopped within 15 seconds and do not affect the critical load steps.
The following errors were corrected:
- 1. The demand horsepower for the centrifugal charging pump was changed from 640HP to 690HP. See PIR l SQNNEB8643.
i TV A I0834 (SN eSS 4 7e)
l REVISION LOG
Title:
Diesel Generator Analysis
[
e.
" DESCRIPTION OF REVISION o%,o l
1
- 2. The input power to the vital power system was changed from 214.8 +j70.6Kva to 119.4 +j70.9 ,
I Kva. See sheet 8a.
- 3. The data for the diesel gen.srator engine water ,
hester/ lube oil pump motor was corrected. See !
sheet 8a.
- 4. The hydrogen analyzer, hydrogen recombiner, and permanent hydrogen mitigat2on system loads were added to the steady-state analysis. See sheets 161 and 162.
- 5. Unit two B train load descriptions were changed to match the standardized load descriptions.
Valve stroke times were corrected where they I differed from survelliance data.
- 6. Time delays for 1 & 2-FCV-3-126A and 1 &
2FCV-3-126B were changed from 25 seconds to 29 seconds. Time delays for 1 & 2-FCV-3-179A and 1 &
2-FCV-3-179B were changed for the delayed SI cases.
W ih1/47 Pages added - 8a, 8b, 8c,103a,103b,103c,+Ge, Jt,q , 2 c.,, l59,o bed shtiti Pages deleted - Me,10f, 80af, MS.
Pages changed - 1, 3, 4, 5, 7, 8, 10a, 10b, 10c, 10d, 17, 18, 23, 26, 27, 28, 29, 30, 32, 33, 45, 46, 47, 56, 57, 58, 59, 77, 78, 79, 80, 80s, 80b, 80c, 80d, 80e, 80f, 80s, 80h, 801, 80j, 80k, 801, 80s, 80n, 80o, 80p, 80q, 80r, 80s, 80t, 30u, 807, 80w, 80s, 80y, 80z, 80aa, 80ab, 80ac, 80sd, 80ae, 81, 85, 90, 95, 96a, 96b, 96c, 96d, 96e,161,162, 22j al,(Oe,16,3
- DNE1 - 0289W l
r TVA 19834 (EN 0E54 70)
i sou-ES-oot g REVISION LOG Die s e. L Genera.To r Amly sls rivi. .
Revision Da
n o. DESCRIPTION OF REVISION AD9f0Ved
- hY ** .*
'!'H" -
is nuady$'
Mart)b 18 aubb JAsa tk Judo it k&h' d 'j.fg &o a a d adL k sw ya d 6 a a amuL &
madd, f16 g ski 16 sy% y 6 nd a h, at am .
uulay/nJ udL &%i A fwws s '
(an n ou, m). \
I 1
1 1
l 1
i TV A 10$34 (EN DES-4 78)
_ . _ q
' $. , /
e s
~
$<a 4 - E 3 - C)D7L TABLE OF CONTENTS Page I 1. Purpose 3
- 2. Assumptions 3
- 3. Documentation of Assumptions 4 f
- 4. References 4 R% d
- 5. Special Considerations -7
- 6. Computations / Analyses 9
- 7. Summary of Results 101
- 8. Conclusions 10d gq
- 9. Personnel' Involved in Research & Verification Process 10d
- 10. Attachments A Definitions and Codes 12 B Load List (D-G Powered Boards) 15 l
- C Diesel Generator Loading at: 35
- a. Loss of off-site power (BO)
- b. 90 with Phase A Isolation
, c. BO with Phase B Isolation
- d. 2B Loss of off-site power (BO) l
- e. 2B BO with Phase A Isolation l l
- f. 2B BO with Phase B Isolation
- g. 2B BO with delayed Phase A Isolation ,
- h. 2B BO with delayed Phase B Isolation l D Diesel Generator Loading Total (Summary) ats 82 I a. Loss of off-site power (BO)
- b. BO with Phase A Isolation
- c. BO with Phase B Isolation '
- d. 2B Loss of of f-site power (BO)
- e. 2B BO with Phase A Isolation t
- f. 2B BO with Phase B Isolation
- g. 2B BO with delayed' Phase A Isolation
- h. 2B BO with delayed Phasa B Isolation .
E Diesel Generator Sequence 97 evaluated by Morrison-Knudsen Co.
- a. 90 on Power Train 2B
, b. 30 & SI-Phase A on Power Train 2B
- c. BO & SI-Phase B on Power Train 2B F Diesel Generator Ratingr. 103 International Power Systems, Inc (Morrison-Knudsen Co.3 '
TVA Contract No. 71cht-92652 Sequoyah Nuclear Diesel Generator Load Sequence (Diesel Engine) Report No. 6957 (Generator) Report No.
O Dbase III Plus Diesel Load Pro' gram Listing 117 Preparcti M l [ (p[$"7 choc:=d sh',0 1/n /87 Rw 4 l Date g
- . . . ~ . - . . - . . , . - . - - . . - . . . . . . - . .
SQN E3 002 1 H Worst Case Leading at Condition 5 135 l
- a. Frequency dip l b. Ucitage dip I Special Cases 151
- a. SI on Unit 1 and Loss of Offsite Power on Unit 2 J Running Loads after Sequenced Leading 158 is complete for the 5 accident conditions i
I t
m, a QkB ~
enea AIS ,
m; _t
/ *- . , _
' " ~ + - - .,_ . . , , , _ ___
SQ bl- E3-OO 2.
EWB29fE i To determine the kW and kVAR loading at each sequence step of
[ each Standby Diesel Generator. The loading is compared with the diesel-generator capabilities to determine if acceptable voltage l and frequency limits are maintained. The fifth Standby Diesel l Generator and its support auxiliaries are excluded. ,
I essyngIlgNS
- 1. Alternate feed connections are not used. (Thi s is an R4 unverified assumption)
- 2. Loads without a specific cutoff time are assumed to run I
continuously through the loading sequence.
- 3. All receptacles, cranes, hoists, tank agitators, and .
evacuation alarms were considered not in use for the five accident transients.
- 4. All space heaters, unit heaters, and duct heaters were considered off (except pressurizer heaters and humidity control heaters). Air conditioning equipment was considered on.
- 5. All lighting transformer loads are 100 percent demand at .9 power factor (pf). All heat trace transformer loads are 100 percent demand at 1.0 pf.
I 6. No planned entrance inside containment was considered.
- 7. The shutdown board room air conditioning systems are tripped on a loss of off-site power and a delayed SI with phase B containment isolation and restarted after the containment spray pump starts. This assumption applies to condition 5 only. (This is an unverified assumption) 84 l
S. The Reactor Vent Boards and Control and Auxiliary Vent l Boards 2A2-A & 2B2-B are tripped by a loss of off-site power and a delayed phase B containment isolation. This assumption applies to condition 5 only. (This is an unverified assumption)
- 9. The main feeder cable from the diesel generator to the shutdown board carries the generator rated current. The losses due to the cable are included as losses of one of the transformers. Losses due to the shutdown transformers are based on their nameplate full load losses.
- 10. Unit 1 is in cold shutdown and cannot experience a LOCA.
i Prepared INM} lkp/87 I
Checked JA P lh]l$]
p, y / / 3 Date
S Q N- E 3- 032 l
1 D9Gud[NI@IlgN_gf_95SyDEIlgNS R4
- 2. For worst case condition, loads were considered to run continuously unless cycle times were known.
- 3. Cranes are not used during normal operation of the pla'nt Hoists are operated infrequently. Receptacles are designed for welding. Typically, no more than one welding machine might be used during normal operation. A loss of off-site power would i interrupt any welding that might be in progress. Evacuation alarms are not used during the OG loading transient. i
- 4. Summer seasonal loads exceed winter seasonal loads; I I
therefore, all space heaters, unit heaters, duct heaters, etc.,
were considered off except for humidity control heaters. Waste .
heat from the reactor and turbine building, supplies most of the l required heat in winter. The diesel generators output capability )
is also reduced by high outside temperatures.
- 5. Since no other information other than rating of transformers was available, nameplate data was used for transformer loading (small transformers 480V or lower). This is a conservative assumption.
- 6. Planned entrances into containment are isolated conditions and not considered normal operations. gq
- 9. The main feeder cable losses used (based on the diesel generator rated current) and transformer losses used (based on i their nameplate data are conservative.
l
- 10. This study considers only unit 2 in operation. Unit 1 l loads that support unit 2 operation have also been considered.
While unit 1 is in cold shutdown its SI signal is blocked. ;
l BEEEBgNQES Lotus 123 Lotus Development Corporation (IBM) Version 1A ;
AC APS Loading Analysis DE2EEBCALOO1 R3 (B43 860409 920) l Dbase III Plus (IBM) Version 1.0 l l
As-designed Single-Line Drawings:
______Disttz_Bgatd______
Dwgt_Ngz ggvg 6.9KV Shtdn Bd 1A-A 45N724-1 R21 6.9KV Shtdn Bd 1B-B 45N724-2 R21
{ 6.9KV Shtdn Bd 2A-A 45N724-3 R19 ,
6.9KV Shtdn Bd 2B-B 45N724-4 R19 Prepared W\ h l((,{g")
chek.d s&uo th7/87 ,l Rev Q# #
Date !
,___ ,_ -_ _ _ _ _, . , _ _ - _, , _ _ , , _ _ , _ _ _ _,_,-,,,_,___,n. _
SQN-ES-oo2 480V Shtdn Bd 1(2)A1-A 45N749-1 R2O 480V Shtdn Bd 1(2)A2-A 45N749-2 R22 e 480V Shtdn Bd 1(2)B1-B 45N749-3 R19 4 GOV Shtdn Bd 1(2)B2-B 45N749-4 R19 480V Reac Mov Bd 1(2)Al-A 45N751-1 R21 480V Reac Mov Bd 1(2)A1-A 45N751-2 R19 480V Reac Mov Bd 1(2)A2-A 45N751-3 R18 480V Reac Mov Bd 1(2)A2-A 45N751-4 R18 480V Reac Mov Bd 1(2)B1-B 45N751-5 R22 480V Reac Mov Bd 1(2)B1-B *45N751-6 R16 400V Reac Mov Bd 1(2)B2-B 45n751-7 R1 4 GOV Reac Mov Bd 1(2)B2-B 45N751-8 R1 480V C&A Bldg Vent Bd 1(2)A1-A 45N756-1 R21 4 GOV C&A Bldg Vent Bd 1(2)Al-A 45N756-2 R17 400V C&A Bldg Vent Bd 1(2)B1-B 45N756-5 R19 480V C&A B1dg Vent Bd 1(2)B1-B 45N756-6 Rt9l4 lRQ 400V Dal Aux Bd 1(2)Al-A,1(2)B1-B 45N732-1 R19 -
480V Ds1 Aux Bd 1(2)A2-A,1(2)B2-B 45N732-2 R15 480V ERCW MCC 1(2)A-A 45N716-1 R10 480V ERCW MCC 1(2)B-B 45N716-2 R8 480V ERCW MCC 1(2)A-A,1(2)B-B 45N716-3 R2 61:stS190R$_EEDEeftig_Qtgg[Qgs Qggg_Ngz 83y3 Echtentic_ggties 6.9KV Shtdn Aux Pwr 45N765-1 R13 45N765-2 R15 I 45N765-3 R17 45N765-4 R11 45N765-5 R13 45N765-6 R15 45N765-7 R14
@s qquigegd_ggbgggiig_Qtggiggs pygg_Ngg 83y3 Esbesatis_Etti=5 45N765-8 R12 45N765-9 R10 45N765-10 R12 45N765-11 R13 45N765-12 R7 45N765-13 R13 45N765-14 R13 45N765-15 R15 45N765-16 R13 45N765-17 R9 l 45N765-18 R5 l 4 GOV Shtdn Aux Pwr 45N779-1 R14 (4BOV Shtdn Bds 45N779-2 R19 i 480V RMOV Bds 45N779-3 R12 480V C&A Bldg Vent Bds No. 1) 45N779-4 R9 )
45N779-5 R24 45N779-6 Rio 45N779-7 R12 45N779-g R23
{ 45N779-9 R2O
- 'recared %% lls1/%1 cnecked &AP llg7/87 Rev # #
3,,,
SQM- E 3 -OO 2 45N779-10 R17 i 45N779-11 R17 l g 45N779-12' R24 45N779-13 R25 45N779-14 R20 45N779-15 R21 45N779-16 R18 '
45N779-17 R17 45N779-18 R16 45N779-19 R1B 480V Shtdn Aux Pwr 45N779-20 R24 45N779-21 R21 45N779-22 R25 l 45N779-23 R22 45N779-24 R19 l 45N779-25 R21 45N779-26 R15 .
] 45N779-29 Rio R15 45N779-30 45N779-31 R18 45N779-32 R12 45N779-33 R13 45N779-34 Rio 45N779-35 Rio 45N779-36 R11 45N779-37 R11 I 45N779-38 R8 45N779-39 R1
- 45N779-40 R3 45N779-41 R4 45N779-42 R1 A E -dEH190fg_ggbegatig_Dtgy10gs Dygz_Ngz Bgyz schtentig_sstien 45N779-43 RO 45N779-44 RO Turbo-Gen Aux 45N647-4 R9 480V Dal Aux Pwr 45N771-1 R18 45N771-2 R14 45N771-3 R18 45N771-4 R16 45N771-5 R2 35W726-1 480V ERCW MCC R11 35W726-2 R8 l Shtdn Bd Rm Chiller Compr Contract No. 75K35-83709-1 -
Schematic C5-DGM1405(X1425)A/B i l
Installati on, Operation Manual Form No. 6139A Cont Rm, Elec Rm A/C Compr Contract No. 72C35-92693 Installation, Operation Manual Form No. 6143
( !
Prepared 44W4 t ((1[gpr Checked M90 )/p/g Il ne< ._ y 6 D:te
- . ~._ .-. . . - . . _ _ . , _ . . . _ . . ~ _ . . , . _ . . _ - . . . _ _ . _ . . . . _ . . _. .~..._.m._ .
S QN - E3 - OO2 l
i segCle6_C98siggaeI198s l
l Fire accidunts were considered for loss of off-site power only, a fire coupled with a SI phase A or B is not considered a design basis event. !
l 1
The AFW pump will experience a loading of 540 brake horsepower seven seconds following a pump start under worst case steam generator conditions (see Post Mod Test PMT-53). The load torque l will vary as the square of the shaft speed with ramp delay effect gq l due to pump and pipeline fluid hydraulics. This delay should '
place the additional horsepower subsequent to the next load step. I The contractor has re-analyzed with the increased acceleration .
time and has found it to have no impact on diesel generator 4 loading.
I The air conditioning systems for the control room, electric board )
rooms, and shutdown boards require special explanation of their time and sequence of operation.
The equipment (hp) is arranged for power train assignment as is ;
shown belows
( egwe8 Iselu le 1B 2e 2B uets Cent Rm A/C Compr 125 125 C gy Cont Rm AHU 60 60 C Elec Bd Rm A/C Compr 125 125 A i Elec Bd Rm AHU 75 75 A l Shtdn Bd Rm Chiller Compr 250 250 B RH l Shtdn Bd Rm AHU 75 75 75 75 B
]
l Notes: )
A. For a loss of offsite power, and a concurrent SI with a phase l B containment isolation, the power ci~rcuit breakers for the A/C compressor, and AHU opena.
After the diesel-generator restores , voltage, the following occurs R4 .
- 1. Electric Board Room AHU starts automatically 220 seconds after power is restored and runs continuously.
- 2. Electric Board Room A/C Compressor starts if the following conditions exist.
[ a. The AHU must be running.
Prepared _ %Q ll(, {gy Checked &$ gjg7ly Rev ; y # ' ~
Unt*__
SQ N - 6 3 -CK32
- b. The internal timer must have timed out. This can occur at a minimum of 200 seconds after the AHU starts.
- c. The thermal control switch for the room temperature-must be closed. The compressor cycles on and off as called for by the thermal control switch.
For a loss of of f site power ,and a delayed SI with a phase B containment isolation, the power circuit breaker for the AHU opens when the phase B containment isolation signal occurs
( assumption 7 ). The Electric Board Room AHU starts automatically 220 seconds after the phase B containment isolation signal occurs. The Electric Board Room A/C Compressor starts automatically when the three conditions identified previously exist. .
B. For a loss of of f site power and a concurrent SI with a phase B containment isolation, the power circuit breakers for the A/C compressor and AHus open. 84 After the Diesel-Generator restores voltage, the following procedure should be followed:
- 1. Ensure that the Diesel-Generator has available capacity.
- 2. Verify that the electric board room compressor is running. This will preclude simultaneous starts of the electric room compressor and the shutdown board room chiller package.
- 3. Reset the chiller compressor manually. The chiller package and AHUs will then start simultaneously after a 21 i minute time delay. The AHus and compressor run continuously l after they are started. l For a loss of offsite power and a delayed SI with a phase B containment isolation, the power circuit breakers are assumed to open when the phase B containment isolation signal occurs (
assumption 7 ). The same procedure that was previously given should be followed to return this air conditioning system to operation. .
C.', Unit 1 only, therefore not considered in this revision. )
I i
Preps.ea & ; /61 /1 8 7
( cnum113p , j,7,p y hv ,_ y/ e -
gl Dete_
8 1
~ --
SQ N - E3 -007.
. The input power to the vital power system is as follows; 2 - Vital Power Inverters 42.0 +J 42.8 kVA (a) 1 - Battery Charger 23.0 +J 27.9 kVA (a) 1 - Power Distribution Panel 54.8 +j O kVA (b) total 119.8 +j 70.7 kVA
- a. See OE2-EEBCALOO1 RS-, Appendix C
- b. The power distribution panel is a single phase load. It is supplied power by a 50kVA transformer. 15kVA of the transformer is reserved to back-up an inverter. Therefore the maximum input power to the transformer is
( 50kVA - 15kVA )
- 1/.96eff = 36.5kVA.
This load is carried by two phases of the 480V system
( 18.25kVA per phase ). The unbalanced condition makes 18.25kVA unavailable from the third phase. Therefore the total three phase load is 3
- 18.25kVA = 54.75kVA. The loading is mostly instrumentation therefore unity power factor is used.
DG Eng Water Heater / Lube Oil Pump data f This load consists of a 1HP motor and a 15kW heater. From DG-E2.4.6 the worst-case 1HP motor has the following characteristics: If1 = 2.4A , pf = .56 , Ilr = 15A ,
pfir = .62 . Therefore, kWr = 3
- 2.4A * .46kV * .56 = 1.07kW kVARr = 1.07kW * (1/.56^2) -1 = 1.58kVAR kWs = 3* 15A * .46kV * .62 = 7.41kW kVARs = 7.41kW * (1/.62^2) -1 = 9.38kVAR motor start plus heater 7.41 +j 9.38 kVA 15.0 'j O kVA
-_---------=_____
22.41 +j 9.38 kVA = 24.3 [_22.7 kVA I = 24.3 / (. 3* .46 ) = 30.5A , pf = .923 motor run plus heater 1.07 +j 1.58 kVA 15.0 +J O kVA 16.07 +j 1.58 kVA = 16.1 /5.6 kVA I = 16.1 / ( 3* .46 ) = 20.2A , pf = .995 Prcpnd N M lljyfg7 cwa M th7/87 '
Ru Q 4* 8 ct .
Dass
. . - . . _ _ , - . . ~ . . . - . . . . _ - , .
Tva os9H (.N DES 2 7s, TENNECCEE VALLEY AUTHSRITY On t b or S
d +0< CAo- L r
,u,,,eSce ca l:n R m ,..ase,qM SG- rJ E 3 - oo 2.
. a d ElecJr:c BJ R ,.ioiniaak:lla e.....,
.. ~ ,.. ., e n sCollow:-, q;m her a.P o&L a~r.
....,..a
^
Re v;e w 09 +1,e con-Irel sehe mad:es % b s LJJow- L vm ckalce p,c6fe reveale f +4aJ upon locs of con 4 rol powe< ( +1,:s isould accar da r ;r,g a loss o.P ofC.s:Le powe r) +he con.}<oI (P
c: rov 4 pould h ne .}s be inanually re.se.) to allseu spera4:ea wke~ pe,we r- is res Joyed. 74e ,
dalelocu~ bd rm Alkl, ar< slaved ho de c k:ller s, herefo r e, dey weald be cPC un):t -d e ek:ite rs y come on.
Re v:ew o f +1,< con 4rol schema 4:e s 9. r &
d ll z ~ elee,r:c. hJ rm eLnla r pach r e revaa t.ecl thaJ upon loss o-? conJrol po~er , +k e ca nd ro l c;rca:4 is avio rnad.'c ally resed upon po ur basus res4cred. The cA:ller cornes &cr en afbr he
+t me r i mpieJer ;+.s -k m :ny % c4:o t ;
0 Sea U m e h L l % ojocro b.'o n h k a.l Flam)swlle l.
,u uu ,.a a ,.~s s i.,,.e.a:n ;
po ~< r .
= = = --
~ ~ ~ ~ ~ ~ ^ ~ ~ ~ ~ ~ ~ " ~ ~ ~~~
^ ~~ ^l" ~ ;;C_L^} -- -~ -- ~
I
'i ,_
.I l
l l
r r ,
' ik' d 3f5 .) ' & V 4^'*q ,
f,' o-l- a of' s.' ': 4.L
'] *f "*? T" C i J f:' JJ" T'" "'
')w ft "" ~
(9 >: y ~/ ~ ty q + f:#s sp a * ~ +7.st s s q m ( 11: y :a q 9: op 3 q efi* S Q fl d?up ^vg
.s: y; a n )rt4/ ms JpS~
- s. n y p s.5 y n -e e y y:~>
WA > &p:;p G
vino Jffi d o loS' dj1
- a mo
("O ?l 2/ 2 ~ 34 ?ll;[J w) a..q uja y-a m (y
-opnp ay ~y
//JP of /AA9f P1 SERYYi NOI13Y f 9l] OQ tMSSMSIG I
YA[ 5#
- L() /' ' 'g : Hold l
98/0'M & giq) '*I JJ V N"d w:J' :an 3
31TG 1 INYdH03
.3HYN, I i
N003 TAI as+nM7 100 - E3 - N69 l
G y nt to wwh COMPUTATIONS / ANALYSES t A computer data base was prepared using lotus, showing allfloads connected to power distribution boards that would be powered by the Diesel Generator following a loss of off-site power condition CBlackout-80). These loads were arranged on a power train basis CIA, 1B, 2A or 28) and then operation coded by applying the codes '
of Attachment A after interpretation of circuit operation. From as-designed logic and schematic drawings.
The time of start and/or stop, where known, was entered for each load.
4 Possible accident conditions are blackout only, blackout with ,
safety injection signal and phase A isolation, blackout with safety injection signal and phase B isolation, and blackout with delayed safety injection and containment isolation.
The data base was then sorted for the three accident cases: -
Blackout, Blackout with Safety Injection Signal Phase A, and Blackout with Safety Injection Signal Phase B. l Initial sorts for the 3 system conditions were sorted using the load list data base (see Attachment B) as follows:
- a. Blackout (see Attachment C.a.)
Sorted on Time B0 column. Loads that are not used following a blackout are deleted.
- b. Blackout with Safety Injection and Phase A Isolation (see Attachment C.b.)
i Sorted on Time SI column. Loads that are not used during a blackout with concurrent Phase A isolation are deleted.
a Sorted on number in SI time on Phase A. This gives load step when Icad is applied. Those with only Phase B designation were deleted. ,
I
- c. Blackout with Safety Injection Phase B Isolation (see Attachment C.c.)
Sorted on Time SI column. Loads that are not used during a blackout with concurrent phase B isolation are deleted. i Sorted on number in SI time on Phase B. This gives load step i when load is applied. Those with only Phase A designation were deleted.
The loads were summed in horsepower, XW, starting and running XW and XUAR, by time for each of the four power trains for the three canditions listed below Csee Attachment D).
The worst casa power train was selected for each condition and a load profile (see Attachment E) was established for evaluation by the frequency drop at each of ten (10) steps
{; CO, 2, 5, 10, 15, 20, 25, 30, 90, and 120 seconds).
enouee Y '
cm.e ATS S mm. J' 9 am _ 9-z 7- 96
Condition Worst Case Power Train j Blackout CBO) 2B g
BO plus SI-A 2B BO plus SI-B 28 Loads determined to start and run randomly were coded as:'such, summed separately, and were to be applied at each step. Starting
&- running XW and XUAR for each load was calculated using- load data information contained in AC APS Loading Analysis Program Small 120V ac loads were neglected for this OE2EEBCAL001.
, calculation because of very small starting and running XW's.
Loads were summed for HP, XW, and starting and running XW and XUAR for each step and each accident conditien Csse Attachment C).
A computse , data base was than prepared using Dbase III Plus, j showing $11 loads connected to power distribution boards that
- would be powered by the 28 Diesel Generator.
Sorts for the F-;ve accident cases were then run, using the Dbase ,
j program with transformer and diesel feeder cable losses included. j Valve stroke modeling was also considered. j a
- a. Blackout (see Attachment C.d.)
j Sorted by TMBO column. Loads that are blank in the TMBO !
column are deleted.
(
- b. Blackout with Safety Injection Phase A Isolation (see Attachment C.e.)
Sorted by TMSIA column. Loads that are blank in the TMSIA column are deleted. l
- c. Blackout with Safety Injection and a Phase B Isolation (see Attachment C.F.)
Sorted by TMSIB column. Loads that are blank in the TMSIB column are deleted.
- d. Blackout with a delayed Safety Injection Phase A i Isolation (see Attachment C.g.) l Sorted by TMBO column until t=x then by TMSIA column.
Loads blank in the TMBO & TMSIB columns are deleted.
- m. Blackout with a delayed Safety Injection with Phase B Isolation. (see Attachment C.h.)
Sorted by TMBO column until t x then by TMSIB column.
Loads blank in the TMBO & TMSIB columns are deleted.
( The times for the delayed cases d. and e. were determined by trial and error to give the worst case loading on the diesel k epareo M cn.ca.e f 7'$
10 ,:
sw. [Fq _
D*_ 9 86 - _
l Jga g - E 3- ou e engine during the automatic load sequence. These times were determined to be 3:10 minutes for d. and 2:00 minutes for e.
The computer program used in dBase III Plus did not have the capability to automatically determine additional random loads after t=0 or the random loads prior to the delayed accident cases. These random loads were added manually for those cases.
(see attachment D d. thru h.)
Verification of the dBase III Plus sub-program outputs have been hand calculated.
Revision 4 of this study used the OA'd SON data base. SON-APS-006. The data used was prepared, checked, and controlled although the data base study was not issued when revision 4 was issued.
Using the data from this data base the dBase III Plus program (Attachment G) was run by preparer. The preparer did a line-by line check of the output against the revision 3 output to ensure they were the same except for the intended changes. Random loads added after t=0 or prior to the delayed accident were added manually. The checker reviewed changes from revision 3 programs and manually added steps with revisions as a check to the dBase hN program.
sytteBLof_5ESW6I5 The results of this study are correct for Train 2B only. The I other trains have not been updated for loading changes made since revision 2. At that time it was determined that Train 2B was the worst case for loadino and all study revisions since that time have been made to Train 2B only. Equipment changes made to reduce the transient loadino were made on both Train 25 and Train 2A.
therefore Train 2B still envelopes the worst-case loading.
I. TRAN5IENT LOADIhF The Load Analysis included an analysis of the automatically applied loads for the occurence of a safety injection during a loss of offsite power. Previous analyses had assumed that the heaviest loading transient would occur f or a simultaneous safety injection and a loss of offsite power. In this revision of the study, it was determined that 1) the heaviest loading of the automatically applied loads occurs in the event of a safety injection after a loss of offsite power, and 2) the transient power demand caused by simultaneous motor starting can e::ceed the j peak value of transient power the diesel oenerator can provide. .
Therefore, chang:.s in motor control logic were developed to ensure that the transient power demands will not exceed the diesel engine's cold and hot capabilities. Evaluation of the five conditions will be given in reverse order. gy f
im,ae4Aht i/23/g7 cc.us P I/23/g7 ' '
Ra & l00 C#:
W N L_O,-UUL i
! Qggditige__51- Loss of offsite power followed by safety injection i
with containment isolation phase B i
- The following is proposed to ensure the transient power - demand R4 does not exceed the diesel engine's capabilities.
- 1) To ensure that the transient power. demand does not e 'xceed the diesel engines capability during the containment spray pump start:
A. Trip the shutdown board room air conditioning system on afdi loss of off-site power and containment isolation phase signal and restart after the containment spray pump start. Bl4N l B. Trip reactor vent boards and control & auxiliary vent
- boards 2B2-B and 2A2-A on a loss of offsite power and a safety
{ injection. These boards are not required to mitigate an
, accident. Loads on these boards can be manually actuated that j can cause the transient kW to exceed the diesel generator
- limits if they are not tripped. Tripping the reactor vent board for a LOCA after a loss of off-site power is given as an operator action in AOI-35. An automatic trip is preferrable e
to ensure that the board is tripped before the accident loads are started. g4
- ! With the preceding changes implemented
- ,
?
1 l
An SI and phase B containment isolation at t = 2:OOsngives the heaviest transient loading. .
The maximum transient load (kW) that can occur while the i diesel engine is still cold:( t <'3 OOm) occurs at t = 2:10m
. It is equal to 4220kW and is within the diesel engine's cold l transient kW capability (4482kW).
The maximum transient load (kW) that can occur while the diesel engine is hot ( t => 3:004 occurs at t = 5:OOrtIt is i 495BkW. This exceeds the diesel generator hot transient ,
- rating, 4951kW, by 7kW. This is considered acceptable j because of the margin built into the load data. This margin consists oft a
- 1. The 3 shutdown transformer room exhaust fans will not start at the same time after t = 0:00 because their temperature switches are set at different temperatures. .
The heaviest loading of shutdown transformer exhaust l f
fans after t = 0:00 occurs with 2 fans running'and 1 fan starting. This is a 21kW reduction in the random load.
- 2. The boric acid transfer pump is shown as starting at high speed in the random loads. This could only occur
{ at t = 0:00. After t = 0:00 the motor will at least be
< pr d %M i//M67 cnocuee & D 1h7lh7 gcb ,!
3 n., . '-l o.=
s99-ts-aoz running at low speed.- The kW inrush on switching to high speed is 9kW less than the inrush used in the random loads.
- 3. The losses in the two 6900/480 volt shutdown pq transformers are modelled at full-load current. As shown in the steady-state diesel loading analysis. EN2-DS193RP, sheets C115 and Cll6, the losses are approximately 9.3kW. In this study the losses are modelled at 39.4kW.
These inaccuracies provide more margin than is needed to demonstrate the acceptability of this loading profile.
Frequency dip is calculated to be 2.58H:. Voltage dip is calculated to be 21.8%. (see Attachment H) ggaditige__41 Loss of offsite power followed by a safety injection and phase A containment isolation.
An SI and phase A isolation at t = 3:10 gives the heaviest transient loading.
The maximum transient load (kW) that can occur while the diesel engine is still cold ( t < 3:00 ) occurs at t = 1:30.
It is 4035.5kW, and is within the diesel engine's cold transient kW capability (4482kW).
l The maximum transient load (kW) that can occur while the diesel engine is het ( t > 3:00 > occurs at t = 3:20. It is equal to 4693.9kW and is within the engine's hot transient kW capability (4951kW).
R4 Gggditige__31 Loss of offsite power and a safety injection with a phase B containment isolation occuring simultaneously The maximum transient load (kW) that can occur while the diesel engine is still cold ( t< 3:00 ) occurs at t = 0:25.
It is equal to 3890.2kW and is within the diesel engine's cold transient kW capability (4482kW).
The maximum transient load (kW) that can occur while the i diesel engine is hot ( t => 3:00 ) occurs at t = 3:00. It is J equal to 4943kW and is with'in the engine's hot transient kW capability (4951kW). .
gggqitige__21 Loss of offsite power and a safety injection with a phase A containment isolation occuring simultaneously The maximum transient load (kW) that can occur while the diesel engine is still cold ( t < 3:00 ) occurs at t = 0:25. ~
( It is equal to 4182.9kW and is within the diesel engine's cold transient kW capability (4482kW).
Prepared MM I //7 [97 ,)
Checked d ea d 1/M,/A
, 7
- lO o nw' .4 kW ,
1 i
59 tJ- E d-OOZ.
The maximum transient loads (kW) that can occur while the diesel generator is hot ( t => 3:00 ) occurs at t = 120:00.
It is equal to 4540.4kW and is within the engine's hot !
transient kW capability (4951kW).
I ggeditign__11 Loss of offsite power i The maximum transient load (kW) that can occur while the QQ diesel engine is still cold ( t < 3:00 ) occurs at t = 2:00. I It is equal to 4210.6kW and is within the diesel engine's cold transient kW capability (4482kW). l The maximum transient load (kW) that can occur while the diesel engine is hot ( t => 3:00 ) occurs at t = 120:00. It is equal to 4621.3kW and is within the engine's hot trans. ant kW capability (4951kW). 4
- 1 If a safetv-injection (SI) signal from unit 2 occurs 10 seconds after a loss of off-site power in unit 1. the 15 second timer for j the uniti ERCW pump is reset by the SI signal. This causes the i ERCW pump to start 25 seconds after the loss of off-site power, at the same time as the aux feed water pump. The starting kW for this condition is 3115kW. which is within the diesel generator engines capability. The starting kVAR is 9026kVAR, which will cause the voltage dip to exceed the 25% limit by 5% per Reg.
( Guide 1.9.(see Attachment I)
II. STEADY STATE LOADING It was found that all of the ' steady state loadings are acceptable. Operator actions may be required under conditions 3 g
and 5. See attachment J for details.
GQUGbW51905 Diesel Generator 2B has acceptable loading for the 5 accident cases with the following;
- 1. Implementing the modifications that are listed as assumptions 7 and B ensures.that the transient loading for condition 5 does not exceed the diesel generator rating, kN- -
- 2. Operations may have to take action to reduce the steady-state loading for conditions 3 and 5.
Based on the previous conclusion of 2B being heaviest-loaded, then train 2A will be acceptable if similar modifications are
{ made to its loads.
vtentes $4hh ll17l67 checked 4 4 1/i7/M 0 Ret .Y 1 I t'.5- 10 i Date
The approach ( see memo from W.S.Raughley to D.W. Wilson dated September 29,1986 B43 860930 901 ) for Sequoyah. N.P. is to implement .any necessary changes for the cases of loss-of-offsite power, and loss-of-offsite power concurrent with a safetv injection signal ( cases 1.2. and 3 in this study ). The SON FSAR kN and Design Criteria are being revised to remove the commitment of a loss-of-offsite power with a delayed safety injection sign.al (
cases 4 and 5 in this study ). Therefore the changes recommended on page IOd for condition 5 (loss-of-of f site power with delayed SI and phase B containment isolation ) do not need to be implemented.
1 EE8590056 10YQLYgD .IU EESEGECH @ND Mg61ElC@IlgN ESQCggs
, PTB-Peter T Bowman RRF-Ralph R Fernande CRM-C Randall McIntosh JAP-James A Purser RPR-Robert P Reese RJM-Richard J Mages f HMF-Howard M Frederick AIS-Awad I Shenouda DFL-David F Loveless SAP-Susan A Pannell IkN 1
e,emo %%9 ih3 /e 7
{ c.mua da # //13/87 au 4 ' !
. Osts & lQL l
OMp to ww'
-s ATTACHMENT A
Definitions and Codes t
r i
e l
)
l 1 l SQN E3 002 12 l
ATTACHMENT A J
DEFINITIONS AND CODES l Definitions:
I SI - Safety Injection Signal 4
80 - Blackout (Loss of off-site power)
SI-A - Safety Injection Signal - Phase A SI-B - Safety Injection Signal - Phase B CRI - Control Room Isolation ABI - Auxiliary Building Isolation CVI - Containment Ventilation Isolation D-G - Diesel-Generator j A/C - Air Conditioner ANU - Air Handling Unit
( TIME 80 - Time of energization once diesel generator breaker has closed on a blackout only (Letter designations are given under time
! codes).
i TIME SI - Time of energization once diesel generator breaker has closed i on a blackout with a safety-injection signal (letter i designations are given under time codes).
! CPT - Board compartment designation.
I 1 i CONT CONB - Control Combination Code (code designations are given under cont comb codes),
i PRASE A or B - Designates if load is energized or de-energized for a Phase A or Phase B Isolation (I-energize 0-de-energize).
I OPER TIME - Cycle time of a device.
COMPONENT UNID - End device unique identifier.
i
! KVA - Kilo-Volt-Amperes HP - Horespower KW - Kilo-Watts 1
i 4
e
=
l ,
1 1
f i
0712G l
SQN E3 002 13 Codes:
Time Codes Random variables (may be energized at any time by automatic process control)
T - temperature dependant P - pressure dependent L - level dependent S - special process dependant F - flow dependent Time is expressed in minutes, seconds.
4 1
i t
l l
-l l
l I
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l
,.- --. - --r,___.,_ - ~ , , - . - . . ._ - - , _ , , . . ~ . . . - ~ . - . . _
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dQN E3 002 14 Cont Comb Codes TM - Force Tripped-Manual restart TL - Force Tripped-Locked out TA - Force Tripped-Auto restart permitted-TAD - Force Tripped-Auto restart by diesel sequential timer TAS - Force Tripped - Auto restart by SI, SI-A, SI-B, CRI, ABI, or CVI (Engineered Safeguard Signal)
TP - Force Tripped-Process restart TPD - Force Tripped-Process restart after time delay UMS - Untripped-Nanual-on-with seal-in contacts (AC Control)
UNW - Untripped-Manual-on-without seal-in contacts UNO - Untripped-Nanual-off UAD - Untripped-Auto Diesel start UA - Untripped-Auto process on UAS - Untripped-Auto-process with run, standby and switchover UA0 - Untripped-Auto-process off UAI - Untripped-Auto on by SI signal CD - De-comissioned OP - Power removed
(
I O
l 0712G
SQN E3 002 ATTACHMENT B
Load list (for D-G Powered Boards)
Comp 1 Attachment B was:
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l 1 .N TVA 10697 (ONE-0A-6-86) ONE CALCULATIONS l Title [ Plant / Unit l 8 Diesel Generator load Analysis l Sequoyah UI and U2 i "eparing Organization lKEYNOUNS(ConsultRIMSOgscriptorsList)
(
l ONE-EEB-ECG I Diesel Geneseae M e7 l l Branch /Projectidentifiers lEach time these calculations are issued, preparers must ensure that the l J
l original (RO) RIMS accession nater is filled in. l lRev (for RIMS' use) rims accession noter l l SQN-E3-002 l l l I l .
l l R0 1 86020700131 1 825 860204 300 l lAppiicaoie Design Doci,nent(s) l. bms &II & 'R$ W 0127 90A j l
lSARSection(s) l UNID System (s) l 2. l l l lFJ '87 0217 l
92il l l l l R3 l l l Revision 0 l R4 l R S- I R l Safety-related? Yes (X) No ( ) l l
lECNNo.(orIndicateNotApplicable)l l N/A l N/A lMN l I
lStatementofProblem l Evaluate the transient sequenced load l
I l Prepared l y.Q / l applied automatically to each 0-G power l Peter T. Bowen* $4L4
' l l train for the following conditions:
l Checked l C. R. McIntosh*
N l jg* j l l
l l
1.
2.
Blackout loss of offsite power (80).
80withSafetyinjectionSignal(SI) contairvnent isolation phase A.
_ f/ p) l Reviewed g ,l l l R. P. Reese* i N,ANA/E l 3. 80 with Si contairvnent isolation
.T Hall /R b (_ -
l 4. t delayed $1 containment isolation phase A.
(-
10 ate 7l/ I 7 /l7 "A 7871 l l l S. 80 with delayed Si containment
,E FORM l List all pages added l 'ru 15EE REV,l l isolation phase 8.
,lVA10534lbythisrevision 1 / ,v. L . I Lo ff. l l llFMORE lListallpagesdeleted Ih ' l $ EE KEY.l l l$ PACE lbythisrevision 14, s. / ,e l LO G. l l l REQUIRED l List all pages changed lm ' l$EE REY.l l l l lby this revision 14y.4. . I LOG. l l
l ABSTRACT [These calculations contain an unverified asstsmtion(s) that nwst be verified later. Yes (X) No ( )]
l l Each Class IE OG power train was evaluated for the first three conditions stated above. The loads on each i l board powered by the OG of each power train were evaluated for operation sequence and operation time. The l l loads were then stamed by starting and running IQi and KVARs for each loading time beginning with 0 seconds I, l to 120 minutes. From this sismation, the worst case sequential loading on any power train for each of the ll l three conditions was determined to be power train 28. This worst case loading was evaluated by the diesel '1 l generator to determine capability to accept and carry sequenced and random loads within allowed voltage l l and frequency limits (attached). I I
l The contractor subsequently determined sufficient capability with a reduced load. Power train 28 was l reevaluated for conditions 4 and 5.
l 10cl l If ERCW pum is started at saw time as auxiliary foodwater pts @ (see =d!'Ir ' page 40e), diesel will be -
l In violation of voltage variance per Reg Guide 1.9.
I I
I
- 0riginal signed by: p)n&l[r/67
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SQN E3 002
(
ATTACHMENT i
C Diesel Generator Loading at:
l
- a. Blackout (BO)
- b. 80 with Phase A Isolation
- c. 80 with Phase B Isolation i
i Comp e Attachment C was:
Prepared by Js Mb na te N a /& jf//.
Checked by /
dse Date I- '8d V f i
.i f
- 13230
bQN E3 002 35m t
ATTACHf1ENT C
i Diesel Generator Leading at
- a. Loss of off-site powerC30)
- b. 30 with Phase A ! solation .
- c. 30 with Phase B Isolation
- d. EB Loss of off-site powerCBC) Boa
! s. EB B0 with Phase A ! solation Boa l
F. 23 30 with Phase B ! solation 30j Sor
- g. 28 30 with delayed Phase A ! solation j h. 25 30 with delswed Phase 3 ! solation SQx 1
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