ML20154G754
| ML20154G754 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/12/1988 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| TAC-00090, TAC-45681, TAC-90, NUDOCS 8809210060 | |
| Download: ML20154G754 (55) | |
Text
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e "7ENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 1578 Lookout Place SEP 121988 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-260
)
50-296 BROHNS FERRY NUCLEAR PLANT (BFN) - RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION - AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) ACTUATION HODIFICATION (TAC NO. 45681)
This letter provides TVA's response to NRC request for additional information on the above subject dated August 10, 1988.
Enclosed for your review is the engineering change notice pa:kage (including the safety evaluation), and applicable drawings for the ADS actuation modification.
Please note that the timer is set per our Technical Specification # 248 (TAC 00090) submittal of July 29, 1988.
Please refer any questions concerning this submittal to Patrick Carier at (205) 729-2689.
Very truly yours, TE SE LLE1 AUTHORITY
/
R. Gridley, anager Nuclear Li nsing and Regulatory Affairs Enclosures cc:
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U.S. Nuclear Regulatory Commission.
SE!P 121988 cc (Enclosures):
Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear' Regulatory Commission One White Filnt, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. F. R. McCoy, Assistant Director for Inspection Programs TVA Projects Divi 'on U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Browns Fer'ry Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611
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. Record ENGINEEJtlhG OW#CC NOTICE COVER SHEET 3, 1. y. 3 t-nt/ Project and Unit ECN Nurrcer RIMS Accession Nweer 9
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' Ch*"9' Automatic Depressuria. ; ion System (ADS) Logie. Changes-0***#'
8 See Continuation Sheet #2.
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Justi fIcation/Poason for Change To comply with NUREC-0737 Item II.K.3.18-o e
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Safety Evaluation Number
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Yes SEBTECN880009 G rom lX No 9.
RIMS Accession No.
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- 12. FCR/SCR/MCR/DCR/DCN/CAQR Numoer Date of Document (s)
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DCR No. D3478
- 13. Other Document Idencifier Date of Document (s)
..,_ t 14 Special Requirements?
See
- 15. Potentiql Tech Spec See I 1 Yeg.,fXI No Sheet No.
Chance IXl Yes I 1 No Sheet No. 6
- 16. References
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1.
BMT TSAR Sections 6.4 and 7.4 2.
Technical Specifications 3.2 and 4.2 3.
ECN Data Sheets 1
GE Report RIMS #B22880519206 4
Ebasco Speed Letter f rom Gopal Aravapalli to Stephen Marschke dated 5-5-88 5.
6.
BWR Owners Group evaluation of NUREG-0737. Item II.K.3.18 "Modification of
~
Automatic Depressurization System logic" submitted to the NRC under cover letter dated 10-28-82, BWROG-8260.
7.
ECM_f,,..?. 17116. RO. Aepagdix R Checklist /Evaluatica,$hge
- 17. Description ot Proposed Activity (Change, Test, or Experiment)
This USQD evaluates the "design complete" package for E N E-2-P7116.
This ECN package modi-fies the Automatic Depressurization System (ADS) initiation logic in response to NRC NUREG 0737, "Clarification of IMI Action Plan Requirements" item II. A.3.18.
This IMI Actiert. Item codecssed the modification of the ADS initiation logic to include cases where a low reactor watcr level condition exists in the absence of a high drywell pressure condition. This scenctio could arise as a result of a pipe break outside centsinment.
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- - -four conditions must be met before automatic depressurization will occur, they Currcntly,TEJ cres (1) coincident signals of high dr low reactor vessel watcr level (378" above vessel zero inches)ywell pressure (2.5psig) and (2) A confirmatory low reactor vessel water icv 1 signal (+18 inches)
Any one of the four RER pumps or either division of the c:ra spray pumps running (4)(3)A 120 second timer must be timed out.
J'g, Tharcfore, the existing ADS initiation logic would require manual actuation of the ADS for c:rtain transient and accident events which do not directly produce a high drywell pressure cad cre degraded by the loss of high pressure injectiot. system (Reference 4).
...s p (1) Replaces the existing ADS timer This ECN makes two changes to the ADS initiation logict relc with a qualified one and changes the trip set point of the 100 second ADS timer from 120 5 seconds to 105 7 seconds in order to meet the BR4 FSAR Appendix N, section N.6.5.10 cc (Attachments): NF RIMS, SL 26 C-K 90-36sh
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AEys c SEBFECN880009 Sh2ct #2 *F fo "T7 Description of Proposed Activity (Continued) rr.quirement that, with a high drywell ressure c.ondition, the total maximum time delay for ADS initiation and MSRV movements be l!O seconds.
(2) It adds a new bypass timer which will provids for automatic initiation of ADS'without tha high drywell pressure.after approx 855 seconds..This 855 second time delay is the combination of the revised 105 second ADS timer plus the newThis change would provide for automatic. init 750 second timer.
ADS for certa whilo allowing the operator approximately 16 1/2 minutes to determine if ADS initiation is n:cossary.
including resetting the timer signal if.
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SAFETY EVALUATION FORM Jc Prsj;ct S7foty Evduation Number BMIPLUnit 2 SE3FEbl8 80000
- 18. Sys tem (s.', Structure (s ), or Component (s) Af f ected Automatic Depressurization System (ADS) - System 1
- 19. Safety Function (s) of System (s) Affected g
ADS provides for automatic nuclear system depressurization, if needed. for small breaks in the nuclear sy the Low Pressure Coolant Injection (LPCI) and the Core Spray System (CS$ stem so that) can operate to protect the fuel barrier from overheating which would r sult in the uncontrolled release of fission products f rom the reactor fuel barrier (Raference FSAR section 4.4.).
- 20. Effects on Safety qu'lified timer and changing the associated setpoint from.g ADS timer relay with a Class lE Th] first part of this ECN involves replacing the existin 120 5 seconds to 105 7 seconds.
This will provide assurance that the system time delays assumed in the BE LOCA accident annlysis are met.- B M FSAR Appendix N, section N.6.5.10 states that a time delay of L20 s'conds is the maximum practical delay time for ADS initiation.
Therefore this portion of the ECN improves safety by assuring ADS initiation within the time requ1 red.
Th] second part of thin ECN, the installation of a high drywell pressure bypass timer, provides a meanc of assuring adequate core cooling for certain transient and accident
< vents (i.e., pipe break outside primary containment) degraded by the loss of high pressure injection systems.
Basically, the delay setting for the bypass timer must allow for (1) avoidance of excess fuel cladding heacup, and (2) sufficient time to allow high pressure makeuo systems to recover the RPV water level or to allow the operator suf ficient time to prevent automatic depressurization f rom occuring during an AWS event (see Raference 4).
t Tha design basir event for the ADS high drywell pressure bypass timer is the main steam-line break outside containment (Ref 4).
This event results in the greatest inventory loss prior to break isolation.. Following break isolation, it is assumed that all high pressure makeup systems will be lost. The General Electric analysis (Ref L) concluded that the upper analytical limit f or the ADS bypass timer setting is 15 minutes and f urther concluded that the lower analytical limit for the ADS bypass timer setting is 10 minutes. These li-its provide assurance that excessive fuel cladding heatup will be avoided while allowing to allow hi h pressure makeuo or operator action to prevent automatic sufficient time 6
depressurization f rom occuring during an AWS event.
This ECN provides for the installation of a new bypass timer with a setpoint of 121/2 minutes.
This is midway between the upper and lower analytical limits provided by General Electric.
item II.K.3.18 the ADS modification also includes a manual inhibit To meet NUREG 0737[nitiation circult.
This change to the physical plant will help prevent switch to the ADS inidvertent ADS actuation due to operator error. The new manual inhibit is a key-lock switch, so two separate actions are required to install the inhibit.
This decreases the passibility cf inadvertent operator action to inhibit the ADS.
It will have negligble icp cts on ADS reliability since it is already possible for the operator to inhibit ADS.
How;ver, this f eature has several advantages over the current mechanism f or manually inhib-iting ADS actuation.
Presently, the 120 second (to be 105 seconds) must be reset before it times out (i.e.
every two minutes, not just one time) in order to prevent ADS initiation.
Tha new manual Inhibit frees the operator for other duties since the timer circuit does not rcquire resetting once the new inhibit is selected.
The present method of resseting the ADS 120 second (to be 105 seconds) timer will still be available.
Another means presently avcilable for inhibiting ADS initiation is to pull the fuses of the ADS Control Circuitry; how;ver this method of inhibiting ADS initiation is still available.
B:s;d on Reference 7. ECN P7116 will not affect the operation of any of the MSRVs nor the
' caro analysis performed for an Appendix R fire event.
Th] wiring and components for the circuit modification are similar to or better than those presently used so reliability of the new circuit is the same as the present circuit.
Although this modification provides more paths for ADS initiation (i.e., high drywell pressure r bypass timer timed out) the probability of an unnecessary RPV depressurizaten is not si nificantly af f ected by the proposed modification because any slight increase in th] proba 111ty of spuriot;s actuation is approximately off set by a decrease in the orobability of inadvertent manual depressurl:ation as described in the preceding paragraph IBWkOG report, page 56. Reference 6).
In sumary, this ECN increases the safety and reliability of the Core Standby Cooling Syrtem by uliminating the need for operator action during an off-normal event curentAy rcquiring manual depressurization and decreasing the pcssibility for unneeded depressuri-sations caused by operator error.
This modification satisfies the requirements of NUFIC 0737. "Clarifienti,on_of
".I Action Plan Require::Lepts" itsem 1 10 18.
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ASVe 0 SAFETY EVALUATION FORM Saf ety Evaluation Number Praject AFHP._.Unir._?.
_SI3 F.4CN880009
~ll. Would the proposed activity increase the probability of an accident previously evaluated in the FSAR7
( ] Yes (X) No Justifi. cation:
Th3 current modification of 'the ADS logic ~ eliminates the need~for"operator action to'depres:
~~
surize the reactor for certain scenarios (i.e., p pe break outside containment where de-pr:ssur zatioa. is warranted.
This modification a lows sufficient time (approx matel 14 1/2 cinutes for the o erator to inhibit ADS initiation for those situations where ADS i itia-tion is not desire (i.e.
ATWS event).' The probabilit of inadvertent manual initiatiin is higher for the current AD$ lod c because the operator, knowing that f or some events he is i
r:sponsible for manual depressurization, may be more apt to err in what he believes is the ccnservative direction by depressurizing the RIV to allow low pressure ecoling (Reference 6)
- 22. Would the proposed activity increase the consequences of an accident previously evaluated in the FSAR7
( ] Yes (X) No t
Justification:
Although this modification of the ADS initiation logic provides ths automatic initiation of th7 ADS for certain scenarios where a hi it d&Cs not change the f unction of the ADS.gh drywell pressure condition does not exist,The consequences of inad cre the same as previously evaluated.
- 23. Would the proposed activity increase the probability of a malf unction of equipment important to safety previously evaluated in the FSM7
( ] Yes (X] No Justi!! cation:
Alth: ugh this modification provides more paths for ADS initiation (i.e., high drywell oress-ure nr bypass timer) the probability of inadvertent initiation of ADS is essentially the same as previously analyzed.
This la because four hi h drywell pressure bypass timers are to bo installed, one in each channel of the ADS initi tion logic. Channels A and C comprise Tri ystem I, while channels 3 and D comprise Tri Both channels of one div s on are required to energize to initate ADS. p System II.Considering that other signals must be cres nt in each channel for ADS initiation (i.e., low water level confirmatory low water ini lation. pressure ECCS, the Iailure of an Icvol, ill not cause inadvertent 105 second timer, availabilit of low one bypass Multi le fai ures in each channe of a timer w division is necessary to provide inadvertent initia ion.
Based on the above the probability of c malf unction of eq ipment important to saf ety (ADS initiation logic) is essentially the 2k,~hou$f3viously_anaYzedd the proposed activity increase the consequences of a malf uencion of equipmen 3
---impor tan t-- to-saf e ty-previous ly-evalua t ed-in-the-FSAR7
( ] Yes (X] No Justification:
S;veral coincident signals are required for ADS initiation (i.e., high drpell pressure or b ass timer, low water level confirmator low water level 105 second clmer ECCS avail-a lity) as well as the energ zation of bo h channels in a rip System.
The ailure of any component in a logic chan el will not result in inadvertent initiation of ADS. Also, the fcilure of any component relay to close) will not result in the loss of ADS as the other Trip System is still available.
Therefore, the consequences of the f ailure or malf unction '
cf equipment important to safety is not incressed.
9
8 SAFSTY EVALUATION FORM Project Safety Evaluation Number
.BHl.E_!1ni t 2 SEBRCIS30009 25..Would the proposed activity create a possibility for an. accident of a different type than any evaluated previously in the FSAR7
( } Yes (X) No lgatifiention:
M:dification of the ADS initiation logic does not create the possibility of an accident of c different type.
The possibility of inadvertent ADS initiation axisted before and will still axist after this modification.
This modification pegvides automatic initiation"of --~
ADS where warranted while allowing sufficient time for the operator to inhibit ADS cp: rotor from havin6 to continuously inhibit D S initiation (i.e.,ylock switch to free the initiation when it is not desired. This change also provides a ke every two minutes) as was previously reqaired for situations where ADS initiation is not desired.
- 26. Would the proposed activity create a possibility f or at malfunction of equipment of a different type than any evaluated previously in the FSAR?
( } Yes (X) No Jus tifies tion :
Th2 possibility of the failure of the ADS initiation logic exisited before and still exist icilure of any one relay will not result in ADS initiation. quired for ADS initiation, the efter this modification.
Several coincident signals are re
- 27. Would the proposed activity? reduce any margin of safety as defined in the basis for any technical specification
( ) Yes (X] No jus t if ie.s tion :
nacioa-.,i.e.,gh pressure bypass timer increases the reliability of the system for Addition of a dryw 11 hi oipe break.outside. containment)-while. providing-suf ficient. tima--_
c rtcin.'
for ope-
>r action for situations where ADS initiation is not warranted.
The addition of a keylos switch to inhibit ADS initiation assist the o erator for these situations.
Based en the s' eve the margin of safety as defined in any tec spec is not reduced. (See R forence 2)
i 3
(4N r 6 /'7//4 EEvao Sheet 6 cp. 6 SATETY EVALUATION FORM l
Frsject.
Safety Evaluation Number EFNP Unit 2 SEEFECN880009 Check below (x) the subject for this page.
m.
Specimi Requirement (s) or Precautloo(s)
.__28b.
.Y Safety Evaluation
- ~ ~ ~~ -
28c.
Y Additional In f o rmm_ tion 29.
~
SAFETY EVALUATION B: sed upon the discussion provided under "Effects on Safety" and the response to the qu stions in Blocks 21 through 27 the changes contained in this ECN do not constitute an unr: viewed safety question.
6 ADDITIO!!AL INFORMATION This LCf involves a change to the Technical Specifiestions, this Tech Spec change and cas:ciated justification are being handled seperate from this USQD.
849 e
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ES IMPACT AND PREREOUIs11rs List EG/DCN#2 E-2-P7116
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ECNs/DCMs WRIG ARE FRDLEQUISITES TO IIIS Em / n No existing ECNs. DCNs. DDn. LDc?e-clou.
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I ECM ASSOCIATED DRAWINCS LIST ECN#;
E-2-77116 f.
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ALL DISCIPLDE:
IS DRAWTNG ATTACUED DMWD4CS NtJMBER REVISION TO PACMCE
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MODIF'ICATION CRITERIA DOCUMENT ECN#2 E-2-P7116 COVER SHEET REvi:
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'ALL UNIT:
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SYSTDt NU:iBER:
1 ECN TITLE: Automatic Deeressuri*ation Syseem (And T_ngie (*k an o n e s
ARSTRACT:.._.._
At eresent. the automatic deeressurI*seinn everem ( ABC asn an i s. Am 4ndedee=A
~
in the eres#ence of all of the fo11evine edgnale.
(th Hieh Drvve11 Fressure (3) Lev Reacter Unter level (Level li (3) conff - see*v teu u_escrer Vmeer fav.1 Itan.1 n (4) 16v Pressure coolmn* fn4eaadan svm41able (DMu /t or*' *"O
',9 ee-de#a -km aa ans***a*
ea-daa sad A modiffes? ten fs needed to reduce denende=a*
aa intent of the NRC Recuirement NUREG-0737 Item II.K.3.18.
This ECN revises the ADS 'loeie bv bvoassine high drvvell wressure oemissive en..
12.5 minute sustained low reactor water level (level 1) and addine inhibit eenerei I
I, switch to manually inhibit ADS.lotte.~~
.. ~
This ECN replaces the existing timers (120 see settine;,) vich 1E qualified timers (105 see setting).
t I
I RE7fSION RO R1 R2 R.3 R4 P3 R6 tinIrr D-I i
4 C.P4 FARED DY!
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C.0LCLG _ BY :
7 FORf1 No. E-201 A.13.1 l
MODITICATION CRITERIA DOCUMNr ECN/DCN#8 E-?-P7116 RE78:
0 pf,SICN EASIS/BASCS SH #: __ 2 __ 0 F. 3 _ _
TUA-BFNP y.
t
1.0 score
L.1 System (s)
Main S teant..SyAr.em Pick-un relavs and cene-n1 eu<erk..
1.2 Feature (s)
Addition of r<-.. n.1.y This modification revises the control e4re.,4 a
n 1.3 Scope of Criteria Au'tomatic Depressurization system (Ano 1.4 Is Quality Assurance Required? _vea t
List exf, sting design criteria doctment(s) with revision number 1.5 that cover this modification M50-727 RO. 3FN-50 728 70. B"6A0-736 R0, BrN-50-c 7105 R1 5
2.0 DESIGN BASIS / EASES
- (Frevide the following inf5rmation if it applies to this modification r
NOIZ:
If the required information can be found in existing design input doctments, give the document number and revision, number only.
Functional Requirements This modification enables to bveass high drvuell 2.1 a=--4ssive in ADS lette on 12.5 minutes sustained low reactor e
- -aemu-a um*** 1evel sn! inhibit ADS leefe manus 11v Desigu Basis Events _ As ref erred in desten erif eria 3FN-50-7001 RI 2.2 n n e8 d e.* e r n i electric Ansivnic for ADS hvnate a a n t ar a d e11 14 =* f * *
(nur-Ano-01090 2.3 Envitcomental RequircrMrots N/A
,,f0Rt1 NO C-201 8.13.* l
MODIFICATION CRITERIA DCCJMDfT ECN/DCN#3 E.2-?7116 QE M IS/EA$f.S REVf:
3 __ 0 F,_ 8 1
1.
2.0 DESIGN BASIS / EASES: (Continuation)
N/A 2.4 inntrweentation Requirements
- ~
2.5 Electrical Requirements The added TDPU -elive c '_ c c 7 t-e,3
'- -~~
Powered from 250VDC.
Electrical system lead e A4.e.1.......
n,oc affected.
N/A 2.6 Mechmaical Requirements t
This modification prevides seismic analvsis 2.7 Cid R ts of component mounting.
2.8 Regulatory Requirements NUREC-0737 Item II.t 1.10 2.9 Special logic for Op.eration~ This modifiesti'en revike, a k'a avde-4 7 ine logie 2.10 Special Maintenauce N/A As seecified hv hde e c'!
2.11 In s tall.a. ti.on R. e.S.n.i. remen ts..
2.12 Other None
'..'M8*
rom:1 No. E-201-8.t37 T I
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MODIFICATION CRITER LA PA>CCME<T ECN/ DC# 8 E-2-P7116 DESIGN BASIS / EASES REvi:
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TVA-BFNT SII 4:
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3.0 TEST AND INSPECTIM REOUIPR!ENT3:
FOTE:
If the required information can be found in existing TVA docinents, give the document niumber and revisions only.
3.1 Component
- Testing Thi a -nd4'<ce ie, initinn pen -nd484narinn
-a=e
,ecnnine doddment PMT 8188 q
3.2 Syst.em Testing This modification initiates a cost modifiestion test scooing s
document PMT 8188 3.3 Inservice Inspection N/A 4
4.0 OPEPA. BILI"1"f. Pl'LTARILITT. MAMATMA3ELT". ?_t"DMP**.ANCE ANALMIS:
linreviewed saf etv;ouestion dete nination for this ECN covers the analvsis.
..u
=.
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- +
5.0 cottin<T:i:
The keys of the Key-lock control switches added by this modification should be under orocer administrative control.
.;/
L FOP.9 NO.
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MODIFICATIOff CRITERIA DOCUMpdI ECN/DCNdi E-2-P7116 DESIGN DOctFTENTS CHECTJ IST REvi:
.O Sil 8:
OF.,8 TVA-B FFF AFFECIID Reference Document i
T/N/NA (if apolicable) 6.0 DESICN DC.QgEVE5 CHggMSI:
FSAR SECTIONS 6.4.2, 6.5.3.1, 6.1 Safety Analysis Report affected?
7.4.3.3.2 & 7.4.3.3.4 If yes Figure i Sect. #
Y TABLE 7.4-2 TABLE 3.2.B 6.2 Tech. Spec. Changet Section No.
PAGES 3.2/4.2-14,15 Is this equipment' covered by, or will Y
and 17 change af f eet Tech. Specs of CALC #CD-92030-882553 6.3 seismic analysis requiredt Does this y
and #CD-Q2030-882554 change have to be seismically qualifiedf i 4
6.4 Are ele,ctrical calculations affected?
N 6.5 Human factor review required? Control HED REPORT #200 and 7
Room modifications only.
- 150 CALC #ED-Q2001-88262 B.6 Impacts other analyses or calculations!
Supercedes Calc #
Will this ECN require a revision to c:::isting enalyses or calculationst Y
BTE7-El-86003-6.7 Revision to Environmental Impact Statement required? Does this ECf af f ect any ex:isting coenitmentst g
6.8 OSHA considerations 7 Should you have guards on rotating equignent and/or does a procedure require revis.4.op?
p
,,,fpRt1 No.
E-201 R.13.5 l
fMDITICATION CRIMfA DOCIMDrT EO/DCN#: E-2-P7116
.-J QEsJgp DoctMDers _r nEcrif sT RIvf:
n TVA-BFNF i 58 8:
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t Am;CTED Reference Document T/N/NA fif neoliemble) 6.0 RCS.!CN.r)OC N a_Q!ECfqJS_T*
(conti$valipn) 6.9 Revislou to state and/or' Federal licenses or permits? Does this ECN impact existing plant 11cer.ses or permits?
N 6.10 Envircomental analysis af fected.
(including; data drawings).'
N 6.11 Essentially alid enviroument calculations EQ binders, and for N
10CFP50.49 list affected?
I 6.12 EQ category and operating t3;mes affected (MCEL)?
N e-ACASTAT Catalog EMD-1 6.13 vendors involvedt and Amerace Corp DOC If yes, refen:nce Manuals or drswings.
Y fE7012/ E7022 6.16 New or existing bills of materials affected?
y 6.15 Construction specifications affect'ed? -
N CALC 0EDQ2001k88257;
-6.16 Setpoint affected?,
Y and AED02001 88*
6.17 Revision to design input documents
- MI BFN-50-7001 R1 y
6.18 Non-IE load isolators af fected?
6.19 Electrical penetration protective devices affetted?
N 6.20 ruse Identification Program af f ected?
N FORM Nn, r. ;o ] _,y, t y, (,
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F.CN/DcNt:
E-2-P7116 MODIFICATION (*RIMIA IYJ'V*rNT m f:
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SH #:
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TVA-EFN?.a.
,.c An a c.u Ref erence Document T/N/NA (If neoliemble)
,'y 6.0 QCS1.2f PQC.Vdf2fIS_.CEffJJSL*__{ Con 110ualiInd 6.21 Otber protective devices af fected?
N 6.22 Instrunent tabulations affected?
Y 47B601-001 6.23 Protective Relay Setting Sheets to be revised?
N s.
6.24 Fipe stress analysis / evaluation required?
Does this ECN have an impact on the
'N piping stress analysist 1
6.25 des this ECN have an impact on piping vibration and/or testing requirements?
N 6.26 Fipe rupture analysis required? Does rerouting of conduit, piping, etc.
N require a review for effects of a pipe
'g break, pipe whip, etc.'
Component / Equipment seismic qualification
~
~
6.27 required? Does this chniq;e increase the equipent nozzlet allowables or components
- ~
By Vendor Y
qualifications 6.28 Does the Ecf involve requirements foe cleanliness as specified in ANSI standardsf N
- ~~ ~
~
~ ~-* ' 6 r29 - Are protective-coatings _insida -
-,m u =..
containment af fected?
N 6.30 Flooding evaluation required? Will this modification increase the possibility of f loodingt Does iten require flood g
o ro t ec t ico ?
FOP 3 No. F-?nt_A,t3,7 {
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MODITICATION c1tfTF'RY_A DOCurEyr ECN/DCNde E-2-P7116 0
's. 4 DESIEMN UNIU SI'I 8
OF __ $ __
TVA-W F
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AHTAn w Ref erence Document I
T/N!NA (if neoliemhle) s.
~6.0 DESIGN DOClDD{IS CHECKLIST: (Con tinuation]
' ~
6.31 Radiation shielding and/or* AIARA
'l considered?
Is this a potential or located nea.r a potential radiation source?
p.,
6.32 10CFR50 Appendix
'R' required?,
If yes, Refer to Att. 9.12 y
- s This modification 6.33 Post modification scoping document required! If yes, refer to NEF 10.4 Y
initiates PMTf188 6.34 E1cetrical or physical separation analysis affected?
N 6.35 Security System modified?
N 6.36 Heavy Ioads considered?
NA
=
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EC249: r_? _a712 6 10L mL50 AFF9fDDE '1'_
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Remarks **
NO QUESTIONS
,, g,.
- r 1.
Do'es the.hange involve equipent on the,
BFN-BTS6-007 al Sh6 following Appendix 'R' documentsT:
a) Mechanical Equipment (Calculation N.
45B901 R1 Sh 8, 9, BEH-BF36-007)
X b) EJectrial Sopport Equipment (Drawing 45B901) snd 10 X
Does the change involve a cable on the Appendix 2.
'R' Cab'e List (Drawing 45B900)7 X
3.
Does the change involve any of the following fire protection systems, (Mechanical or Electrical)?: EFFP/An F(26), CO2 (39)
X
+
4.
Does the change involve a penetration, degradation, removal or modificatio2 of any of the following fire rated barriersT:
(Exclude supports / hanger modifications) s) Walls, floors, ceilings, including Reactor X
M Building floors 593, 621.25 snd 639 (47W11': Series).
9g X
b) Dampets (47W216-51. Table 4).
c) Doore (47W216-51, Table 3).
X d) Conduit / Cable fire vrap (45W807 Series).-
X 5.
Does the change affect emergency lighting units or shutdown access paths as shown on emergency lighting Ingress / Egress routes and major shutdown equipment drawings f45Wt00-RW)?
X l
l 1
FOR.M No. E-201-R.12,1 1
m of '
MO AFFD(DDC
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ECN#
E-2-P7110 tMrvr rt.f sT/E9AIMTroM swFFT REvi 0
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Oun eions
' '(.... IfJE lHQ EEIRA.di.E **
' *0 gn 6.1 Does the change add or delete any electrical 4;
distribution or control equipment (board panels,..
inverters, etc.) into or out of shutdown
'ooard roosas (* fire areas 4 thru 15 and 12 a
r thru 24) or Battery and Battery Board room (fire..
X
~
areas 17, 18, L.-19)f L
6.2 Does the change add or delete any cable into or,,
out of shutdown board room and battery board j
l ruou fits areas (4 thru 15, 22, thru 24,17 thru 19) except cables designated as C, CE. TE,'$
l i..
~
7.1 Does the change affect the pressure boundary of any comoonent within the indicated Appendix
'R' system X
M boundary drawings (47W230 Series).
t 7.2 Do-s the change affect the electrical logic of any component v1' thin the indicated Appendix.'E.'gr system boundary drawings (47W230 Series).
X 47W230-2 R0 8.1 Does the chsuge swd or move equipment con *=4a4ar combustible matraial (e.g. oil, grease, charcoal, electrical' panels, etc.) in s'ny of the fire areas as defined on compartmentation Drawingst (see Tables 1 and 2 on (47W116-51). (Exclude cables routed entirely in conduits or in trays without exceeding t.2 fill capacity. Also exclude equip-ment with las. than 0.5 gallou of oil, a pounds of plastic, 4 pounds of grease or an equivalent x
3 amount of other combustible material).
e FOPN NO. E-201 31.12.2 I
Agg m o_A M ND11 *M
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es 8.2 Does the change add cable trays in any of the fire 'Iff areas listed in drawint series 47W216 Table-lf
[-
X 9
Does the change involve security access systems in
~
Res.stor Bellding, Control Building Diesel Generator Euilding, or Intake Pump Stationt (Question to be deleted when security access control systes design criteria is issued).
X h
EVAIMATION 1
'", A "Yes" answer to any que.ition on the check list will b8 evaluated for Appendix 'R' impact, by the disciplines designated as follows:
Electrical - Questions # 1.b 2, 3, 4, 5, 6.1, 6.2, 7.2, and 8.2 Mechanical - Questions # 1.a, 3, 4, 7.1, 8.1, and 9 Nuclear
- Qoestions # 1.a. 6.1 and 6.2 s
Dur:ng the evalcation, consideration must be gius tb any changes to the fire protection aection of the ISAR. If necessary, use additional sheets for Apirr.slix R s aluatio.n.
- 11 fire areas / zones are defined in Drawings 47W216-51 through -62.
- Additional information/justif'ieation should be included in this column vben necessary. Additiona.1. sheets can be used if required. Questiins which cannot be answered st:anid be marked 'Later', but shall be resolved befort plant modification is authorized.
Electriemi /Meehwn 4 esl /Nuclaw Evaluation:
Automatic Depressu-1:ation S"stem (ADS) af f ects Six Main Stese Relief Valves of tag noJ. 2-PCV-1-5. 2-PCV-1-19. 2-PCV-1-22. 2-PCV-1-30, 2-PCV-1-31 and 2-PCV-1-34 to relieve the high pressure steam to the sueeressien oool.
To meet NUREG 0737 Item II.k.3.18. this Ect revises the loeie b.
oassinr,,,_
hig! dryvell pressure on 12.5 minute sustained los reactor water level (level D
\\epock control switches to allow onerr. tor to5nhibit the ADS initiating and addie.
logic.
i replac;- Me existing timers (120 see setting) vich (E caalified timer
<r
- 'r e;
,, the viring and comoonents for the circuit modific_aq p 1 Panels 9-3 a.m 9-30.
Control Ian
. e.
J are located in the Fire Area 16.
This ECN.f icher addI les nr. modif 1 t h e. existine cables.
rOR** 2 L F-701-F.12.3 I
CREcE.1, ign.u!ATI0ff SET.ET D EVf:
0
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OF 4
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Per, calculation BFN-BPS 6-013 Rev.
1~,' the operation of the UNIT 2 MSRVs. for * 's.
,..Sa f e Shutdown would requir's the manual operation from the Main Control Roos 3 (2-25-32),and at 250V RMOV Bd 28.
This ECN does 4 at the Backup Control Panal;l. of any of the MSRVs from either of these locations.
not affect the manual Contro f.E.
Although the BFN Appendix R submittal does not rely on the automatic depressurization feature of the MSRVs, a complete blowdown vis. ADS significantly earlier than 20 minutes upon an Appendix P. fire event (time at which manual blowdove and manual inj ection of RHR System.jecurs) could cause too much RPV inventory loss and possibly exceed the BFN Appendix P. fuel peak cladding temperature (PCT) limit of 15000 F g.
(refer NEDC 31119 dated January 1986, Emetion 3.0).
A review of the RPV vater level response curves for the vorst case Appendix R f f.re events (See Section 6.1 of NEDC 31119) indicates that a level 1 condition would not be reached any earlier than approximately 10 minutes. The new high dryvell pressu;e bypas:s timer is set at 12 minutes and the existing (in series) timer will be set at 105 seconds (1 3/4 minut es ).
Thus,over 20 uinutes would be required before an automat.ic blowdown occurred provided all circuits were operating properly.
If a spurious level 1 signal initiated the new high dry.tell pressure bypass timer, then 1) assuming all circuits worked automatically, ADS would blowdown and RHR vould inj ect adequate water into the RPV or 2) assuming no circuits worked automat.ically then ADS would not accusily initate since additional interlocks (low cater level perm 4.ssive, RHR/
Core Spray pumps running) would not allow the circuit to be 'uf.e up.
The above discussiw of spurious operation critaria is contained in calculation BFN-BFS6-013 R1 a.d well as NFDC 31119.
Based on the above, ICN E-2-P7116 vill not affect the operatica of any of the ESRVs or' tha, core analyses performed for en Appendix R fire euent.
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Prepared By:
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Checked By:
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ECN#3 F 9 P711A 10Cf'llL50.49 ENTf RotetENTAL 00ALIFIEATION RET *5 0
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DISCIFLINE(S):
yce No 1
(}
(XI.
Could the c'2ange af f ect, add, or delete equipment 1.
within the scope of 10CTA50.49 (10CITJ0.49 List)?
(X)
[]
Could the change af fect the basic function of a 2.
device or systes that performs or supports the performance of a safety function (such as accuracy or setpoidt; or interaction between a 1E and non-LE circuit)f
[]
fx]
3.
Could the change affect design cond.itions or requi.remencs such as process pressure, process temperature, fluid chemistry, device beating, boltage, and opm;uting cycles which ca.dd impact QttDS requirements or invalidate test dathf
[]
(K}
Could the change affect envixcomental conditions
- f..
in either harsh or mild areas such as pressurn, temperature, humidity, flooding, corrosiveness, site elevation, socicar radiation (both rate and total integrated dose), and duration of exposuref
()
k1 5.
Could the change affect location or operation of high energy piping systems, location or operation of radioactive piping systems, operatin a of envizcamental controls systems, or enviroamental barriers spch as walls, doors, relief panels, dacts, etc. (which could af fect environmental i
conditions in either harsh or slid Aseas)7 6.
Could the change involve clocating or reorien-(i
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tLig a device'or system which could-irrpact--
location-specific or shielding analyses or place the device o; system in an area with dif f erent coviroomental coaditio:sf i
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FO P ** NO. F-201 A ll I I
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en. l.1 the chnne,e af f ect materint s such as lier i t:nn t n. rcai r. ; etc.. -hirh coi 1 1 Impact systni ruquiremer.ts, qualif icot. iou analyscc, and invalidate test dataf
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Does the change involve non-1E or 1E non-50.49 8.
devices /circu.its which b. ave creditale interaction
~~
failure modes with 50.49 devices /cie u.its?
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Remarks (Frovide justification for each itens mark 2.
This chance vill not chance the kn=4e siie - w of tha e' d 4-da 4--
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although it ddes change the time setting.of two existing time delav reinv.
(one for each Logic) and adds four time delay relays (evo eer 1.ocie! ene ee-cnannel).
The additional aime delay relays allow for the initiation of e$.
ADS without the high dryveM pressure signal. The time settine chance te the tuci exist'ing relays (Tag 6s 2E-K34 and 2E-K35) is to insure that the relays can function within the system upp.er analytical 11=1: 120 see. and leve-analytical limit 90 se'. considering aIf the inaccuracies.
c and de act. " - -
All the modifications of this ECN are in the mild environment 10CTR50.49 list.
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BMWNS FERRY NUCLEI SANT DISCIPLINE 7 IAC o
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. REVISION O
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2 EA 8083 Key removable free auto position only. Key teeth R2 pointed down when inserted. CE type CR2960VN203D1 180 S s T I c eJ gj7gg Auto awwtli 1
-2 x
3-4 x
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8083 12 NC Xg.j.l% A Plate sinet 0.73" x 3" Efi LOGIC A tWHi&li.5W E6*I"I charactor ADS L%IC B INH 15f7 5#
Stset 0.t:a 1
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NC Control Roon Anunciator Window #31 8083 ACS LOGIC lhAl'6 A oR 0 Window'Earraving as
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(p ls o /M 000 CF b/M Fot. cosikoi. -:M fy d pal A-S DRAFTED CHECKED i
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i THIS CHANGE IS k SAFETY RELATED NOT RELATED TO NUCLEAR SAFETY
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EA ? 711 G - 07.o 000 O
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880WNS TERRY NUCLEAR 2, ANT DISCIH.INE Vo I
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NO 14 5/C Type SIS 600V 41 Strand, 90'. cross-linked 200 FT WJC-6 C
1E polyethylene.
Timo Delay Pick-up Relay Agastat E7012 Sil, 3 to 30 4
CA rs RFP -
gg 8083 r.2 min.250V DC.DPUT.
BrP -
gg Tir.o Delay Pick-up Relay Agastat E7012SE, 20 to 200 2
EA PS 8083R2 Sec. 250V DC. OPDT.
C ye 3'-31/2" Unistrut Channel P-4000 size, 1'5/8" x 10 IT RKB
13/16" x16 Cauge cold enameled.
Machine screw Hex slotted.1/4" x 3/4" 8
gA NC C
Hex Head Calvanized. Unistrut HSHS025075tc.
EA C
NC Unistrut.
1/4" 20 UNT Spring Nut P-4006-1420.
8 EA C
NC Unistrut, #8-32 UNT Sp-ing Nut F-4006-0832.
24 EA C
NC Unistrut, f 8-32 UNT Standard Screw HRT 5008087 CP.
24 D-RKn BPP8-NC Flat Plate Fitting, Bolt size 5/16'j ll/32" Hole Site, 24 194 R1 Unis t rut P-1062.
8778-NC Splice Plate, 2 holcs, Calvanized. Unistrut P-1065 4
EA FXX-1 194 R1 25 IT if!A-1 insulation, color i:oded, shielded, and 90*polyethlene Cable 2/C, twisted, stranded. Xe. 10 Avt.
C lg.
c minimum LOCA black' 11ght stabilized chlorosulf o.ated, type P.S.
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'M @M 000 % Foc. /ax WTA R.M (U O P4 L 9 -to 4-$ 88,
b/lo/CA WN MMD REV' BY BY THIS CHANGE IS
[SAFETYRELATED NOT RELATED TO NUCLEAR SAFETY BASE DRAWING REV.
DCA N'JnEER REV.
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DCA NUM3ER REV
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MASTAT TYPE E70lt5H RELAY TABVLATl0E AUTO m!iBT' 6E TYPE CR294i
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KCT LOCK 2 PCS (TDPU)
M AINTAINE D
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OCA NU-*EER RE V.
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THE TOLLOVING NOTES ARE 5-[AF S A 4 F-4E FI A - 4j APPLICABLE TD ECN:P7:16 6-0U 59 ~
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ECM E 7-P71I(o Ro ADDED Ap5 LOGIC A 48 faw m g q b 20 > $%-- "
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S-/7-d6 C-i 7 4f ORAFTED CMECKE0 REV.;
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THE FOLLOVING NOTES ARE 22 d-i APPLICABLE TO' ECN:77116 N oas.
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REV.
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DOC"MC** t.00A!f 0N N0!fCE
+
2 V*.w E P706 EC2/DC# Number Revision 6
.=
The following original Drawing Change Authorizatijn's (DCA's) are located "h]:.i.
in C-Module. Engineering Design Building and are filed by D A number. The
. :k master DCA has been filmed as an oversited document in the Records and 0,.
Information Management ystea (RIE*) and can be retrieved by EON /DCN T'
number.
)
6J'- 8 7//d - do / -
E)D dea R.vtston M3 Revision --
,.b.
I D:A E
DCA 8
Revision
((
Revision DOA
,d DCA 007 Revision I
N Revision
./
DCA OO Revision DOA t'.y..
M Revision DOA O/
Revision DCA
/!
Revision D:A d/3 Revision DOA h/
Revision DOA 0:1 O/
Reviition
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"-== r 00A Revision 001 Revision IROU Ciert M
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l l OVERSIZE l DOCUMENT
! PAGE PULLED
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NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS i
i f
1 i
l APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC FTS 492-8989 i
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