ML20215K718
| ML20215K718 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/11/1986 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8610280274 | |
| Download: ML20215K718 (34) | |
Text
{{#Wiki_filter:r o s. , g , SECONDARY CONTAINMENT LEAK-RATE TEST
.) ' . . BROWNS FERRY NUCLEAR PLANT (BFN) 1.0 BFN Secondary Containment Leak-rate Test Report per Technical Specification 6.7.3.C.I'.a. ~
2.0 Purpose This report describes the results and analysis of the test data taken c during leak-rate testing of the BFN secondary containment system. This test was performed to verify the status of the secondary containment prior to commencement of refueling operations on unit 3. 3.0 Procedure _ SI 4.7.C outlines the procedure followed during secondary containment leak-rate testing. 4.0 Data The SI was performed concurrently on all zones. SI 4.7.C data sheets list the following test data.
- 1. Standby gas treatment system -
flowrate (from pitot tube): 11,043 CFM
- 2. ~ Reactor building differential pressures " '
~
Unit 1 Reactor Zo'ne .37 , in H 2O Unit 2 Reactor Zone .31 in H 2O Unit 3 Reactor Zone .25 in H 2O Unit 1 Refuel Zone .31 in H 2O Unit 2 Refuel Zone .31 in H 2O Unit 3 Refuel Zone -
.31 in H 2O - '
- 3. Wind Speed 2.7 MPH
- 4. Wind Direction 254*
- 5. Analysis and Interpretation SI 4.7.C demonstrates secondary containment capability to maintain 1/4" water vacuum under calm wind ($ 5 MPH) conditions with a system leakage rate of not more than 12,000 CFM. The technical specification allowable inleakage value of 12,000 CFM has been conservatively reduced by 500 CFM. This reduction was administratively imposed because of previously identified conditions concerning the seismic qualification of auxiliary boiler penetrations into secondary containment (LER 259 84025). The secondary containment leak-rate (all three tested reactor on July zones and the common refuel zone) was 9, 1986. The test was satisfactorily performed, showing secondary containment capability of maintaining a vacuum of .25" H2O with less than 11,500 CFM of inleakage.
8610280274 860911 9 DR ADOCK 0500
o -
'/ . ..
-f i5 AUG 0 7 I?85
* ~' ' e*Page 1 Tennessee Valley Authority e o rm B,,,-5 r .
.. Stevns Ferry Nuclear pgant BT 1.2 6 2.3
- STn;DARD PRACTICE /PERMM1ENT INSUUCTION CHANGE INFOR".ATICN W ST-4. 7. c -- CODION Standard Practice / Instruction' Titie SECONDARY CONTAIm!ENT '"WM" "" -
l _ _ _ _ _ - - - - - - - ~ ~ ~ - - - - -
~
PEF 0dE1ENT INS ~EUCTION CMMJCE
~} .
Is this a wor'eplan-initiated change? Yes _ (Workplan No. ) No. X Oces this implement, delete, or change a reference Yec X No t; to a vendor manual? If yes, CCC Vendor Manual Coordinator signature is required.
, ~
A) # / ' ~
'lendor Manual C ordinator 0., M Coes this implement, delete, or change an SI data cover sheet? X j c' d .'
If yes, Planning and Scheduling upervisor O swnature is .f'uired7~ I & - /nd?b ec I' q , g( Plinning & Scheduling V Date
, 'j If item added, deleted, or frequency changed on IE (or CSSC) PM requirements.
complete SF-111. ___ l STANDARD PRAC"* ICE CHANGE
;fe%M<t
- 1 Is QA review required p. ior to issuance? No- _
Is PCRC review required prior to issuance? 4 s " No
~: (See attach =ent 2 of standard practice BF-1. - b.
s d Quality Assurance. program requirements have 2nbeen pr.e erly incluced.
-h t' A /
s g;$Y.9h'*N{$Quality Assurance Supv. Date
.t '
__ __-_________--____--__.,_:.a_---___--___-__- _. -__-___-_-_ IntentchangeinproceduraldeNMil"ofFSARorotherlicensingdocument?
'~ -
Yes No X New Instruction? Yes No y
- - If yes to either of these. questions, a USQD is required.
Is this change in response to an LER IE bulletin, NRC inspection report,
? management / supervisor inspection, CQAS audit, etc? If yes, specify document .-
~
. under reason for revision. Yes No V
as this change made to meet an NRC ccmmitment? - Yes No X g
If yes to either question. refer to BF-2.3 for proper identification of the enange. Does this revistun implement a source <1ocument? Yes No X
-- If yes, attach form BF-4 Due date of form BF-4 is ^> A ,
Security System involved?- NO Fire Protection System involved? NO NA NA .
~: / I Fire Protectton Engineer Date Public Safety Supervisor Date K.L. Welch ,Rx Enar / 2-6-86 / 2494.
-
- Submttced by Sect en 0 e Phone Num er Reviewed by See BF-1.2 for standard practices.
h34 L /X/6f _mm 7 / (.9 / 86
/ _/
Responsible Section Supv. / Dase R12te h R '1 ".; Eii PCTC Cha rman Date P'lant Manager Date 860212 07 DPSCU Job No.
. *Revtston ,
i I s I L .
*" ~
p' ' Tennessee Valley Authority _
'Page 2 Browns Ferry Nuclear Plant form BF-5 '
*SF-1.2, & 2.3 ..
~
April 10, 1985 .. STANDARD PRACTICE / PERMANENT INSTRUCTION CHANGE INFORMATI REVISION LOG Standard Practice / Instruction SI-4.7.C PAGES AFFECTED REASON FOR REVISION APPROVAL DATE 5/15/84 6 5/25/84 - 15 - 6/15/84 1,7 2/08/85 1,5,6,7,9; add 9A; Clarification (841031-07)
- 11,16,19-27; add 28 04/10/85 13,15 Clarity to comply with .
. ,y standard practices.
~
-<4 y (850226-16) 1,7,8,3.3,q5,26 nb)
Mtb Update flow limit after ~ 06/19/85 mout recent performance of
*'hMf no>,I:p # SI-4.7.C. Nonintent .
i# changes to citrify the source of data used and to
- correct typographical errors. (850506-17) 08/07/85 21,22,23,25,26,27* Change to Tedh Speca which - '
deletes static pressure limiters. Limiters have been physically removed , from secondary containment system. (850705-03) 09/17/85 24 Delete reference to charcoal filter heStors, which have been
'deenergized. (850815-05) 12/17/85 4,7,9,9A,11,25,26,28 Clarification. (851125:-12) 15 Non-intent to correct OR 12 535 "Pages Required" list on
- cover sheet. (860212-07)
DP&CU Job No. 860212-07 Total Number of Pages in Procedure: 31 Lifetimo Responsibility: DP&CU Supervisor i Retention Period:
- Revision
- - _ _ . --__ - . _ _ _ . .a.
,. ~ '. ,
Page 1
* ' BF SI-4 7.C
- . ., q . .
JUN 19 W35 Qljj., ., ?D:] n ,
' I SI-4.7.C - Secondarv ContMr ment f ,L.%.)'g .
~ _,
Descrintien ,, This surveillance is used to ccmply with the requiresents of portions of technical specification 4 7.C. The folicwing table lists the requirements 9 satisfied by this instruction.
. Tech. Spec. -
Frecuenev Referenced Surveillance Recniremants At each refueling out- 4.7. C.1. a Demonstrate the capability of
- age prior to refueling secondary contai:: ment to maintain
-1/4" water pressure with a system inleakage of not more than 12,000 cfm under calm wind conditions 15 mph. SI-4 7.C uill be used to satisfy this requirement.
.- Anytime the integrity 4.7.C.2 Isolate the affected zone frcm tho of one zon.e has been other zones and demonstrate violated .
- secondary containment capability to maintain -1/4" water pressure ..
,under calm wind conditions using the SGTS. SI-4.7.C will te used ,
to satisfy the requirements of the - zone!. The reactor building is broken up into four zones, each of which can be isolated independently. These zones are.the unit I reactor zono (U15Z), _. the unit 2 reactor zone (U2RZ), the unit 3 reactor zone (U3RZ), and the
- refueling zone (RFZ) which is ccamon to all three units. This surveillance -
instruction is written to use the SGTS fan A and C, B and C, c:' A and B, cr i '
- a single fan to demonstrate that at a flow of 111,500 cfm frem all four cf the secondary containment zones can be maintained at a static pressure of -1/4" water under calm wind conditions
- Manualisc'lat).chofthozonas will be used since it is fast and uill help prevent stecs lin'o tunnel temperature increases, which may cause a unit trip.
l e Revision
' 1_ ...
~~E ._ ._... .... i y.
Page 2
/
'2"If ." - BF SI ,4.7.C Vl')a a uv]J>g y ,p .n;;..
n'g u.4:y y ,,, APR.001983 SI 4.7.C - Secondary Containment - Descriotion (Continued) SI 4.7.C will be used to dcconstrato accondary contairanent. ontenbli II./. This is to be accomplished by isolating the secondary containment for the reactor building or the required zones, starting the standby gas treat =ent ,,
' trains, adjusting t.he flew to less than the allowable ficw and verifying the static pressure of the tested zone (s) is .25 in H O2 (or greater cs required by Table 1 for varyins wind speeds) core negative than any non-tes.ted zone. This prosedure will normally be used to test the secondary contaicsent capability of the reactor building prior to refueling.
EQII: Wind speed and direction ceasurements will be taken from the site.
. meteorological tower instrumentation and will be assumed to be acceptably accurate representation for the conditions at the reactor building.
C A UTIO'h This testing should bs limited to 30 minutes if at all possible since the main steam line tunnel temperatures may trip an operating unit. m o 8
.o .i
'~
/' .
Paga 3 .' ./ j. - e': . ~ ~ . - - . . . . BF SI 4.7.C . n *j .r . ~- - (i;aa,a.qu -ud.,-da
> '.b w c',
. . APR 081983 SI 4.7.c - Secondsev Centainhent
- 1. PURPOSS e
This procedure is used to isolate the sones to be Icak tested to
' verify secondary contain=ent capability to maintain - 1/4" H 2O with allowable system in-leakage.
- 2. REFEFENCES 2.1 Technical-specifications for unita 1, 2, and 3, Section 4.7.c.
2.2 The following drawings: , 451:614-5 47W610-64 45N614-6 47U610-65 2 3 .FSAR Volu=e 5, Section 12.2.2.9 3 .EESRecursrTEs . . - 31 The following personnel are required to perfo.rm this test:
~
3 1.1 The unit operator for each unit to be tested to monitor MSL tunnel temperature; 3 1.2 The ASE for each' unit. to be tested or a qualified substi-tute to monitor the status 'f the ventilation system and and restore ventilation as required; . 3 1.3 Two AUO's stationed in the SBGT building to adjust dacper
. positions as required; 3 1.4 An engineering aide stationed in the stack to taka manometer readings as required.
3 1.5 Sufficient techanical engineering unit personnel to per-form the required pitot traverse of.the SEGT systen - tuo to four traverses will be required in a 10-15 minute period; I
**o* WC , - -%
. .i f
1
.f $1DI';G :'
- Y j .m} ]
Page 4 l ' 'A U .i
-4
(?". 62~. r .., , BE SI-4.7.C G ../,; # O'"O 17 ;!;5 [ SI 4.7.C - Secondar't Containment CanabilitY
- 3. PREREQUISITES (Continued)~ ,
3.1.6 Test personnel stationed at panels 25-213-1, 25-213-2, and 25-213-3, respectively and o the refuel floor to get readings from panels 25-219-1, 25-215-2, and 25-215-3; 3.1.7 An AUO stationed at the reactor building 480 V vent board in case any breakers need to be reset during the test; 3.1.8 An ASE and nuclear engineer to coordinate the testing and. communications. 3.2 Verify that the reactor building. ventilation system.is in a normal operational status per OI 30. 3.3 Verify that the SGTS is in standby readines per OI 65. 3.4 Verify that each units' main steam line tunnel temperature is not above 160 F.
~
2 3.5 Verify switch 16A-S34 (Panel 9-5) is :ot in DRYWELL BYPASS or TORUS BYPASS on each unit or the unit that le to be tested. 3.6 Station a man at the Roactor Building 480V Veat Board of all units to be tested in case any breakers need to be reset during this test, and in the SGTS building to adjust manual dampers. 3.7 Set up communication between panel 9-25-1 and 9-25-2 and the following panels: 25-219-1 25-215-2 25-215-3 25-213-1 25-213-2 - 25-213-3 .
- Revision 0240Q L_ _ _ _ _ _ _ _ _
.- Page 5 fL ,'l . .- . '3
-,3q BF SI-4 7.C
,.(
b.u ,' [ .-[..' .* /.!d'I.h - FE9 8 1935 SI-4.7.C Saccedar" ContairHAnt Caanbilitv 3 Prar?cuisites (Continued) . 33 verify that the folicwina process instruments to be within a - current calibration period. FI-6 5-50 1 -PdIC-6 4-2
. FI-6 5-71 2-PdIC-6 4-2
' 1-PdIC-6 4-1 3-PdIC-6 4-2 '
2-PdIC-6 4-1 3-PdIC-6 4-1 EDIE:. Calibrated canocoters installed at stack may be used in lieu of FI-65-50 and 71. Verification of installation by f:echanical Engineering or Instrument Maintenance is required. 39 Verify the inboard equipment access lock doors closed uith seals inflated. _ 3 10 -Vorify that a drywell or suppression chamber purge is not in process or planned during this test. . - 3 11 Verify on Data Sheet SI-4.7.C that each.of the doors are closed - for the respectivo sones to be tested or the doors indicated by nu=ber (sco table 3 11 of Data Sheet SI-4.7.C) for all four so n$s. . - C HDII: Uhen all reactor sones arc to be tested, it is not
- necessary to closa all doors indicated in tabla 3 11,
- and step 3 11 may be omitted.
3 12 Verify !'echanical Engincoring is prepared to parforc requi.~cd G traverses on SGTS. _ 313 Notify each unit operator and assistant shift engineer so that they may cot =unicate and be aware of the ventilaticn_ and SGT3 , status during this test. JR3 vision
,,-z- - - e e -a g.f,,-e n c g. -ew. ve , 4++ , ,++e ce
A .
, j,1
, .,r Page 6
,s
, -. 7--*. f EF SI-4.7.C
, . a. . a; r y 9 v* s g g g/.. .a,m w-
.. .; ,y ,
}<=.
SI-4.7.C - Secondary Contain eet C.$.nnhility ( Continuad) o
- 4. Pr7enutione 4.1 Do not alleu the main steam line tunnel te=parature to onceco 1800F on the unit for which this instruction is perforced.
If this temperature is approached to uithin SoF, stop the test and reestablish normal-ventilation par QI-30 or provido another ccans fcr ventilating the cain steam line tunn31 to prevent a unit trip (trip point is 19407). 0 EQIE: If necessary, the main stea: line tunnel temparatu're e isolation function may be bypassad for up to four hen.s - a ,- per technical specification 3 2. A, table 3 2. A, note
- 12. If this is done, do not allou steam tunnel 2 temperature to exceed 220oF to protect equipment. ,
4.2 ittempt to restrict testing tics to 30 minutes. 43 Evacuate all nonessential personnel from the reactor building and li=it cove:cnt into and within the reactor building during the test. . ..
- EDIE: When all reactor zones are to be tested, it 10 not
' necessary to evacuate personnel from the reactor 8 building, and step 4.3 car be onitted. .
5 Limitatiers 7 net. Actions 5.1 If this test is being perfor=ed prior to refueling, notify t!}c Engineering Section Supervisor or Reactor Engineer to revicu results prior to breaking primary containment. [~~ 5 . 2 For tha secondary containment onos uhich are not toing tected I;F.0/0 the ;ressure controller should be set to control at the loa:t
.leportl 62-23 negative presourc uhich can be caintained. The cons (s) being tested cust have pressure established at least 0.25 in H 2O (30 corrected in accordance uith table .) corc negative than the ucct negative nontested cono.
.......i..
e o- . . . e --c~ -
- n. _ m ~
.:n------~---.
/
> . /
*l
/ 3:8 ~ : -= ,.n. -,
,, Page 7 *
" i /9 -, .. I h ,s "
SF SI-4.7.C N ' t. a L ,.;.'"!.3..2.2d y If
. VEa,2:
g
'; p s ,ilj . \ jl' g;
_g.,l. 3 3.G .._ Nf SI-4.7.C - Secondary Containment Cacability
?
- 6. Procedure -
6.1 Obtain from the cognizant engineer the secondary containment zones o which are to be tested. Check those zones to be testad. In order to satisfy technical specification 4.7.C-1.a this proceduro must be performed a sufficient numbe'r of times so that the combination of zones tested result in each zone being challenged at least once. 6.2 Theflowlim,itatorbelowwhichtheSGTSsystgmshouldbesetfor. this test is the summation of the expected inleakages for the zonos tested, which for all four zones is 11,150 cfm. See Appendix A for expected inloakage rates. Calculate and record the SGTS flow limit. NOTE: The flow limit for all four zones has been red'uced to . 11,150 cfm based on NCR BFNNEB8404 R1. The value by
. which the technical specification. limit of 12,000 cfm
- is reduced is based upon the maximum a P across secondary containment achieved by the most recent - '
secondary containment test an'd must be reevaluated after each successive performance of this SI. 6.3 For all zones which are not to be tested adjust the pressure setpoint controllers to the minimum negative pressure at which the zones enn be maintained or secure the ventilation for zones which do not (Do not secure ventilation for an operating unit at this require it. time.) Secure refuol zone ventilation. The controllers for the zones are: PANEL Unit 1 Reactor Zone 1-PdIC-64-2 1-25-213 Unit 2 Reactor Zone 2-PdIC-64-2
- 2-25-213 _
Unit 3 Reactor Zone 3-PdIC-64-2 3-25-213 Unit 1 Refuel Zone 1-PdIC-64-1 l-25-219 Unit 2 Refuel Zone 2-Pd.C-64-1 2-25-215 Unit 3 Refuel Zone 3-PdIC-64-1 3-25-215
- Revision 0240Q
$ - - .- ...=.== = = x
_ SC . . , E.~ :: ': .7. 0
~
JUN 19 CU
* ,/ SI 4.7. C - Secondary Contaim ent Caoability
./ L.D. ?%% ' 9
- 6. PROCEDURS (Continued)
Nb
- y >
/
* !i . - L3 .,
y 1: 6.4 Record tne wind direction (IR-90-102-2)'and h61ocitp m ,. -
~
o (I3-90-102-1) at the 33 feet level. Data may be ta.6n.frch Enn:'S a cc:nputer located in unit 1 and in T.S.C. q l 6.5 Cenplete Table 6.5 which details the zones to be tosted and not tested. Record tne static pressure for all zones which' are nct to be tested. ' Calculate the required delta P using Table 1 for the most negative zones which is not being tested. (S3GT treins cutc be off while recording this data).
. 6.6 Perrer:n preliminary adjustments on .3BGT system in accordance witn
. . < .. 6.6.1 to 6.6.4.
6.6.1 Line SBGT system to take auction frcm tne refuel floor and/ or ficm any sor'es for which the normal ventilation is off ,
. using 1 or 2 SBGT fand. Adjust tne discharge damper poci-tions to set flow at slightly less than the required flou
. limit. This will require manually opening one of tne SEGT crosstie danpers. Maintain the SEGT discharge da:nper ,
positions wita an AUO stationed tnere in communication witu the SI communicator. 6.6.2 Close tne SBGT crosatie dn .per opened in step 6.6.1. ' 6.6.3 Close or verify closed SEGT crosstie dampers (FCV-64-40,
~
64-41 for reactor zones, FCV-64-44, 64-45 for refuel =one) for zones which are not .being tested /. ' ' 6.6.4 Reestablish reactor building normal ventiidtion fcr all cones to be tested. !!ormal ventilation must be in service in order to test the isolation condition.
' Revision l _ _ _ _ _ _ . _ _ _ _ _ -
. F
/
[ . - ..
, 'f l x *": d L *%
- e,s *pa69 9 g". 2, i
' ,;- BF SI-4.7.C
[, a,/SI-4.7.C - Secondar7 Containment Caoability " w.c
~ ,& C/ a u c c t 7 33 ,
., ~
- 6. procedure (Continuad) 6.6.5. If this test is to be perfo'rmed with the main steam line -
tunnel temperature isolation function bypassed, four jumper cables will be required to make the follouing connections. O In panel 9-15 (auxiliary instrument room), connect terminal BB-3 to BB-4, and terminal DD-3 to DD-4; in panel 9-17, connect terminal BB-3' to 88-4, and terminal DD-3 to DD-4. .1 second-partT verification is required for this step.
' NOTE: Steps' 6.7 through 6.16 should be performed as quickly as possible to minimize the time each zone is without normal ventilation (< 15 minutes).
Monitor steam tunnel temperatures closely and observe temperature limits. In the past a rapid increase in MSL tunnel temperature to ~1659F followed by a more gradual increase has been experienced. Units have survived 15 minutes
~
without ventilation. 6.7 Initiate secondary centainment isolations for zones being tested. - - NOTE: HS-64-117, 120, 119, 122 are keylock suitchei which spring return to NORMAL after being - operated to the TEST position. In the TEST position these switches will drop out a 1 second time delay relay, and hence must be held in the TEST position until the corresponding uhite zone isolation light on panel 9-25 is illucinated. .- (See 45N614-5, 6 for details). 6.7.1 For each reactor zone to be tested: . place HS-64-117 (panel 9-25 on the unit) in the TEST position to isolate the zone (inboard and common valves) and place HS-64-120 (panel 9-25 on that unit) in the TEST position to isolate the zone (outboard valve). 6.7.2 For the refueling zone, if it is to be. tested, ., place HS-64-119 (panel 9-25-1) in the IEST position (in' board and common valves) and HS-64-122 (panel 9-25-1) intheT5STposition (outboard valves). - 6.7.3 Start SGTS fans manually as follows: Train A uith HS-65-18A (panel 9-25-1), train B with HS-65-40A (panel 9-25-1), train C with HS-65-69A (panel 9-25-2). Start only fans needed to l attain required flow. l
- Revision .
i 0240Q
- -, ,- _ - - ~ - - , , - -
, , , . - - , -,,,+,-vy-s --.+ww. ,-4w,,.-,,-,-ew,-,,,-- , - , , , - - -
. *Pago 9A BF SI-4.7.C -
./ CEO17 '23
- 1. Secondary Containment Capability i SI-4.7.C - .
- 6. Procedure _ (Continued) 6.8 Adjust the total flow indicated on FI-65-50 and FI-65-71 (panel .
9-25-2) to less than or equal to the flow limit from step 6.2 if ne:essary. This can be accomplished by closing a SGTS fan discharge da::;per, or if two' fans are running, by' shutting off one fan.
-a . .'
i '. - 2 g- i
. . r :3
. se " , ,_ , . , . , ' .: 2
~
9 ..,;?
.;Qa.Tia. ..>
.1 '
' Revision for pgination 0240Q
~
L
~~"T.vare m_&-- ._.._..
Page 10 _
- - ~' '1 n a.., .,
,. DE S1 4.7.C
't ; C v . . a .. .
L' . APR 081983 j . g r. . if
SI 4.7.C - Secendarv Centaine.ent C396bility .
- 6. PROCEDURE (Continued)
EQIE: Let the flow stabilize for 5 minutes.
. EQIS:
Calibrated mance.eters may be used in lieu of FI-65-50 and 65-71 if desired as long as their installatio' n is ,, yerified by P.echanical Engineering or Instru=ent Maintenance. In this case, record canoccter delta Ps and the conversion equation. EDIE: Steps 6.9, 6.10, and 6.11 should be perforced - , concurrently and as quickly as possible. 6.9 Record. flows indicated on FI-65-50 and FI-65-71 (Panel 9-25-2)(or . ~
. flow calculated from canometer readings) and total flow. $otify
~ -
cechanical engineering to perform traverses of SBGT lines for the refuel zone (if the refuel zone is being tested) and unit 1 reactor zone. Perform traverses for the unit 2 and unit 3 reactor zones also if personnel ~are available. 6.10 Record the static pressures at the differential pressure indicator locations. IQUE INSTRUMENT PANEh U1 RZ 1-PdIC-64-2 1-25-213 U2RZ 2-PdIC-64-2 2-25-213 U3RZ 3-PdIC-64-2 3-25-213 U1RFZ 1-PdIC-64-1 1-25-219 U2RFZ 2-PdIC-64-1 2-25-215-03RFZ , 3-PdIC-64-1 3-25-215
- - ~ ^ ^ - -
- a. ___e___2_-_. _ . _ _ _ _ . . . _
_ _ _ - _ _ . _ ,..e # ,em-.._ _,.. . _
...m,--- - . . . .mm _ _ . _
./ -
~ ~7
, , Pa69 11
; a Q:.d " [
-4 C l
% u a u da.'
f[ r SI-4.7.C - Secondary Containment Canability
- 6. procedure _ (Continued)
~
6.11 Verify the isolation damper positions from the indicator lights on a panel 9-25 for the units and zones tested.
- 6.12 Secure all SGTS trains by operating the blower handswitch to STOP
- an'd then to AUTO, and reset the isolation signals for the zones that were tested by placing HS-64-11A in the OFF position (for isolated reactor zones) and HS-64-3A in the OFF position (for isolated refueling zone).
6.13 Record the static pressures for all secondary containment. isolation zones which were not tested. _ NOTE: When verifying secondary containment it may be necessary to
. perform this procedure more than once. It is not necessary -
to reset zone pressure controllers (ref. step 6.15) to 0.25 or comple':e return to normal steps for the refuel floor. (ref. step 6.14) until all necessary zones have been testod.
~
6.14 Verify on data sheet those actions listed under RETURN TO !!ORMAL for
-- the zones tested.
6.15 Verify all zone pressure controllers set to 0.25 and' verify manometers are removed (if used), returned to storage, and l instrument channel is returned to normal. 6.15.A Verify that the steam tunnel temperature isolation function,
~
if bypassed in step 6.6.5, is returned to'an unbypassed state by removing jumper cables from panels 9-15 and 9-17. A second-party verification is required for i;his stop. 6.16 flotify the UO, ASEs, and SEs that the test is complete and systems returned to normal.
- Revision 0240Q O -*wme .* w%r --++ = - - .
o me
% +ei.% *,se g owess wem* w eg g, e wdghwe m,_ e e,m-em. ep. e4 s e.a..,e.Mg4e. m, . g,
ss-'WAM W"** ~ ...-. - - ... . .. . . .. . . . - . . . Y
' Page 12 .
./ BF SI 4.7.C g' .
APR 081983 SI 4.7.C - Secendary Containment Cacability
- 6. PROCEDURE (Continued) c 6.17 Verify that the least negative static pressure of the zones tested (from step 6.10) is core negative than the cost negative static pressure of the zones not tested (from step 6.6 and step ,_
6.1.3) ty the required delta P in Table 1. ff{0IE: It is only necessary to complete step 6.18 af ter all zones have been challenged. 6.18 Technical Specification 4.7.C-1.a is satisfied when all' enes have
~
been tested and the required delta P for each zone has been established at a ficw I to the sum of the baccline flow for - ~ appropriate combinations of mones tested. Prior to breaking pricary containment the approval c. Engineering Supervicor er Reactor Engineering supervisor nust be obtained. D { * *- m y,C " .f r
, , o ,
l \l &T.dYS ' e
p.,-- y, , .. y Page l_a
+f EF SI-4.7.C Y M i 0 1535 -
. .c. y
;;,. 3.q - '
'qd I ..
TABLE 1
";g;'i Zone Static Pressuro Raquirements for Given Wind 7elocit*/ at 33 feet
- P f. - 0.25 -{3 44 x 10-4 (V2 - 25)iCi} Required a P (in ho) -
Wind Velocity _
.250 0-5 (HFH)
~.254 6
.258 7
.26 3 8
* .26 9 9
. .276 to
. .2 83 33 .- _ ,- *
* .. ')
'u .2 91
.- 12 3
,e' N3
;;7 ' .299 -
13
.: q, <a '7 .
,a 9 ;&~'y .309
. ";;d -
.319 15 .
329 16
.341 17 ,
18
.353
~
19
.365 .
20 .379 21 .3 93 22 .40 8
# # 23 ,' .423 24 .43 9 25 .4 55
>25 Calculato using the formula a'covo (1) Zquation developed from reference 2.3 e Revision
' - ' ' --~ '- ' ~~ -" ** - - -
{._.__.._.....-
. -l /.
- ' ,/
7 Page 14 . !
/ -
I
, y-EF SI 4.7.C APR 081983 fit .e. ,d
~
e.E 4:;h APPENDIX A
., (~[,ly.h) ~
j '_;f.,.: Se&ondary Containcent Leak Rate Test Criteria r! % '* ) > g Dur{ng>preoperationaltestingforunit3thefollowingin-leakageratesat
-1/4" H 2O static pressure were docudented.
~
Docu=ented Inleakaste Percentate Coccon refuel -floor (units 1, 2. .& 3) 6250 64% Unit 1 reactor zone . 1239 12.7%
- ' Unit 2 reactor zone 1064 10.9%
, Unit 9 reactor cone 1211 12 . M s
Total secondary containment 9764 CFM 100% Leak rate testing will normally be done on all zones but not.necessarily . .. simultaneously. After a secondary containment violation, the total inleakage cust not be greater than the total of the allcwable inleakage for
~
each individual zone as indicated be1ow. Zone Allowable Lenkarte Refuel Floor CFM - Unit 1 Reactor Zone CFM (To be l Unit 2 Reactor Zone CFM . supp[ lied l l Unit 3 Reactor Zone CFM later) l l l l l
\
l
. _ . . . ....m. .
~. --
m Tcnnsssza Vallsy Authority
;
- Form SF-206 Browns Ferry Nuclear Plant BF-17.9 -
f BROWNS FERRY NUCLEAR P W T:' REV 0000 SURVEILWICE INSTRhCTION RE7IEW COVER SHEET
.. NOTE: If insufficient entry space is provided reference the secticn and c i continue on back of this form.
3* 1.0 SI NUMBER Y. 7. C. RE%SION Tk2lfb
- n "/
0 2.0 Is there a temporary change,in~effect for.this SI? A/g (1)
; 3.0 If "Yes," has the temporary change been included in this package?
E . Complete Steps 1-3 prior to performance of SI. 9 4.0 Problems with Procedures: Sree /,.I1 3 - I' e o - 48f. Y ; h e64ee s FW Ia . L - i -
~
.i .
1 _ i 5.0 Is a revision required to correct deficiencies identified by performance of this SI? YES NOM' _ _ . _ _ . Performed by: /2 / p/q [q,4 U
'Og c e Revision Initiated (if required) -
h/b"
/
3 - Date
~
l (1) Infor=ation may be obtained by calling Document Processing and Control
~
I s Unit (2489 or 2072). NOTE: i Planning and Scheduling to complete steps 1, 2, and 3 for SI packages, l Performing individual ecmpletes steps 4 and S. t-Performing individual will complete entire form for sis not received from Planning and Scheduling.' -
- General Revision .
1 f 0032p
Page 15 . . BF SI_4.7.C , f.!AR 12 '333 DATA COVER SHEET SI-4.7.C Secondary Containment Capability - UNIT /,2, 3 re , t d b6th &A
' ' ASE
- - /
/
) /b
/ Guclear Engineer a
~
('37 3e / 7 #6 Finish /630 / 7/O b Performance: Start Time Ifate i Time # D6te. Delays or problems Yes No f yes, explain in remarks. Technical specifications, as-found, criteh sa.tisfied. / Yes No Technical specifications, as-left, criteri9 satisfied. / .Yes No
./ Yes no Surveillance instruction criterig easig diId.
Ifanyoftheabovethreeynskkhsno,theshiftengineerwillreviewthodatato determine if an LCO is,.;fi'oIeg. LCO violated. No / TYes Reason for test:
"%[* Shift Engineer Date
'After maintenance (Record MR Plant condition Other (explain -
, number and explain in remarks) (explain in remarks) in remark::)
/ Required by schedule Another system inoperable
- J_ 4 _______ _::= :: == e
/ '
Results reviewed' -
/
, Date 7- /# - M
!!ffilf t Engineer ea'ctor Engineering Supervisor .
/ .
Signature attests that I understand the scope and purpose of this inctruction and that, to the best of my knowledge, it was properly performed in accordance with instructions in that: the recording, reduction, and evaluation of data were complete and correct; acceptance criteria were met or justification for exceptions provided; . - portions of the test performed were appropriate for specified test conditions or reasons for test; deficiencies were evaluated with respect:to potential for futuro problems based on operating experience and regulatory. requirements; and instruction was fully complete except as noted. - Cognizant Reviewer - NE '1% //
- m #/ 3/m / Date 7 -/# - %
' ' ' ' ' ' ' ~
f__~ _________________________________..__ ___ Scheduling " Date -
- = :::::::::::::::::::::::: ::::::: ::::::: :: :::_
Remarks: c A . s.oAri .w of L 23 - Pole. - 6 4 - 1, z vtanich BY SEC - OP/NE COG - NE m R. 4 76 4. P 3 6 s.z h a, ;z- n, co m e r FaEQ - 0/0C, price to 20fuelin; Raracu an o tL=12.pr , a sg en uz rREq zu go_ XEY: 432 RTYPE: pt.02 M Signature signifies procedure has been follo.,ed ac written unless othoruiso noted.
- Revision 0240Q
r . - - - - --
.m,w. _& s s {.m . gg._g,e ___.5 _c----a : ._. .: ._ _ _ . . . . - - . --
Page 16 4 -
.>., .1 BF SI-4.7.C
- a FF9 3 1985
," ,'-./
-.. 'g.;,,- ..
. Q '"
.,.[l# DATA SICET SI-4.7.C Verify and/or Record I, itintn/Date h Cenoorent/ Process vnriable Availabic f ,Z u) ~B,/ h /YO 3' .1 Minicus test personnel Normal (w) 7/ /k6 32 Rx. building ventilation system vi /
Standby Readiness /100 j' 7/9 6 o r 33 SGTS _ f.,,160 0F ILW 7[9N6 34 !!ain steza line tunnel , temperatuare for units being tested Not in dryuell or 35 16A-S34 for units tested torus bypass Id 7 z i- 6 38 FI-55-5'o or cano=eter install Sd and calibrated at stack Currently Calibrated i,/c O .7,!6,f[6 - -. FI-6 5-71 ' or mano:;gta.- '"-talled and Currently Calibrated//2/ M 7 5 calibrated at stack Currently Calibrated (# 7!?' PdIC-64 ~1 ( All three units) PdIC-54-2 ( All three units) Currently Calibrated v W 7- b Inboard equipment access lock Closed and Seal 6 39 doors Inflated [lM 7 M6 Dryuell or suppression chamber Purge Not In Process , M 7 6 3 10 3 11 Doors in the follouing table for the tested':one(s) or the number A/lA ~ of docra for all zonas Clocad f
# 11QI3: If all reactor zones are to be tested this st,ep 2 may be ommited.
Machanical E:.,lineering prepared 3 12 to perfers SGTS traversos. LM 7 ~ 6
/
5.1 Engineering Section suparvicor
)gW notified prior to breaking pri=ary ykjfd contatn=ent. ,, -
C & c*.*i sic a
e a
~ Page 17 BF SI 4.7.C
, %. PR 081983 TABLE.3 11 -
DATA SHEET SI 4.7.C c= PFZ U2RZ U"4R2
, Elevation U1R2 34, 36 40 519 0 30 ,
35, 37 41 31 , 43, 44 45 541.5 42 0236, 0241 0249 255 565.0 0221 0250 242 0231 0237 0251 226 224 0238
~
240 255 231 0229
.s f[4 0228 242
' 0232 ( dD t'
0230 ,
') h,vgb .
0230a
.,' .M, . ..[
0298 0826, 0827 533 0 0538 0497; 501- 506 593 0 , .. 0539 0540 #513 490 0541 0514 621.25 0634 640, 647 651 . 0637 0648 0657 635 0649 0658 ,_ 639 0 670 672 675 673 664.0 704 700 713 7 17 724 715 700, 702, 724, 715, 713 705 701 714 725 716 701, 703, 725, 716, 714 706 712 715 722 717 704, 720, 722, 705, 717i 707 708 716 723 705, 721, 723, 708, 707
- 712 l
l
y e
- e
* ! .h? ::13. ; . C DATA SHEET S:M./.U J."! 1 6 .' D
/
./ Verify -
Initials /Date
,[g Oc=ecrant/Promsn Variable ard/er Peccad Uniti 1 Rx Zone Ae e S 74
./ 6.1 Cbtain frca cogr.1: ant er4;!.neer"the '
-a- Unit 2 Rx Zens ,d'/M 7, -
$,[ndary contain:ent cnsa unich to ba testad. . Unit 3 Ex Zono 6t A Refusi Zeno #. . t d 7
7A '/ 7"N
//,Soo CFM Az e. > ~7/4/It 6.2 RecTd the SSGT fica linig 6.3 Adjust toe pressure centrcliers for '
all =cnes which are not to be n tested to tne =ini=un negative setpcint at which they can be -
.q
=aintaimd. Eacord setpoints. , _
, Jf .
- Settotnt3 , -
N'; Y \f d' ' . 1-PdIC-64-2 U1 E .//A in H2 'b 2-PdIC-64-2 U2E d4 in H2
~
3-MIC-64-2 U3E s/4 in H2 i Secure refuel ficer ventilatien ##O 7- 7' iZ e 6.4 Wind direction (fras RRRMS 7. S ' M 7 ' e ca:puter)- ~ . Directica
- 33 feet level /windspeed (from D7 /M
~
hN4
= RRes cocputer) MPs TurR 6.5 6.5 Test Zece fien-Test Zone Static Pressure Ren. o9 Unit 1 Rx Z V l-PdIC-64-2 N/4 in H2 O .25 Unit 2 Rx Z / '2-PdIC-64-2 '
AsA' in H2O M - Unit 2 Rx Z d 3-PdIC-64-2 1//4 in H2O M Unit 1 RF Z / 1-PdIC-64-1 v/4 in H2O 25 Unit 2 RF.Z v 2-PdIC-64-1 Id4 in HoO 25 Unit 3 RF 2 s 3-PdIC-64-1 j/A in H2O .T8 5 6.6.1 Start necessary S3GT trains (1 or 2) rMnB gA 4 suction fran refuel ficer cnd/or senes which I gi nctual ventilation is*cff and adjust to slightly less tnan tne face limit in step 6.2. Efed ~ 7 'i-St Ihis will ratuire nanually opening one cf the SEGT crosstle canpers befTe adjusting ficw (1-FCM4-44 ' cc -45 fcr refuel f1ccr, FCM4-40 cc -41 fcr reactor senas.) 6.6.2 cLcce SEGT crosatie d:npers opened in secp 6.6.1. //w 7.[9/k6
'Revisica .
r -. _ - _ _ ._.. . .
.F
,/ Gap ;)
2F SI-4 .", C
- , IT9 0
- 05
/
DATA SHEET SI-4.7. C
/
,A.* Verify nM/c" Recad Irt t' 91 r /n- N
; steo C~-monent/Proce=s v a rte.t le 6.6.3 Cloce/vorify cloce the folle:<ing ,
dampers for nontosted zones as applicable. 1-FCV-64-40 Close N/A U1 Reactor Zone 4/A 1-FCV-64-41 . Close 2-FCV-64-40 Close M/A U2 Reactor Zone A/A FCV-6 4-41 Close Close M/A U3 Reactor Zone 3-FCV-64-40 CLose AWA 3-FCV-6 4-41 Cl os'e X//A Refuel Zone N'/A
~
FCV-64-44 FCV-6 4'-45 ' -C '
'j.), lose Roostablish nercal ventilation'f.or all zones /
6.6.4 to be tested. ,, ) fiv) f9ff$ i Main stoss tunnal temperat,ure isolation function (optional) 6.6.5 J
>:4 g -
Ju::1per .A: Panel .9-t5, BB-3 to EB-4 Installed Time Nm
~ /
3 F Second percon Jt.=2per 3: Panel 9-15, DD-3 to DD-4 Installed Time A//S - Sacend porcon Ju=per C: Panel 9-17, BB-3 to BB-4 Installed Time A/,/A Secpad pct:on Ju per D: Panel 9-17, DD-3 to DD-4 Installed Time N/A
/
- Sacond persen ..
lIO,n: Steps 6.7 through 6.16 should be perforced as quickly as possible to minicise the time each zone is without normal ventila tion. Monitor steam tunnel temperatures closoly and observo temperaturo limits. If this test is being perfor:: led with the main steam line tunnel temperature isolation functica in bypass, and a rapid increase in tunnel temperaturo is obcorved (indicative of steam lina break), the operatcr ch:11 prc=ptly close the main steam line isolation valvoc. Da supo test personnel are ready before precceding to ctep 6.'/. 6.7 Cc=plete only for the secondary containment none(s) listed (rcquired linsup). 6 .7 .1 1-HS-64-117 (Unit 1 Reactor Zone) TEST Position [fd 7 T-5% 1-F3-64-120 ( Unit 1 Dancter Zona) TEST Position ff/3 7- 9-R
! /
2-HS-54-117 (Unit 2 Roactor Zona) TEST Position NLw l' 7dl'f6 2-!!S-64-120 (U .it 2 Reactor Zono) TEST Position [
,dW "/lyjf 3-HS-64-117 (Unit 3 Reacto: Zona) TEST Position ,6h 7h6 3-RS-64-120 ( ' Heactor Zcnc) TEST Position W 7 I t -
p- w1 ~--
.. ..... ~. ~ .. -
, .. -' . .t o 2 t
~
SF dI-' . i . ' 70 G 195 DATA SMEET SI-4.7.C (Continued) 7' r
/ Verify I,i t'. C a. / D.' M Co-aonent/ProMnn yneinble- and/or Reecert
[ g 6.7.2 -HS-64-119 (Refuel Zore) Test Pocition [4d 7-T-E 1-ES-64-122 (Refuel Zena) TEST Pccition fl0 hId 6.7.3 HS-65-10A (SGTS bicuer A) STanT M j jh6 c fiqIS: Only if SGTS train A is used. , HS-65-40A (SGTS bicuer 3) START ]zw 11 II6 EQIE: Only if S;.iTS train B is used. HS-65-69A (S37S bicuer C) START N< J.'QIS: Only if SGTS train C is used. .\ s 'g SGTS f1cu adjusted. - -* M 7' 6.8 . .. t W /)
.. .\.. ',[NM fiQE: Stepsg6g 9,i {10',4nd 6.11 chould ba perfor ::cd concurranniv and as ouickly an oossible.
6.9 FI 65-50 N/4 CM1 [0A.) 7!? M '
~
/'
(or
/I
- b5 Equation - '
4?/f 59 Cm . FI 65 - Af'd CFM \/ (o nccoter)
/See* NN Eq us tion - '
67oD Fu C Aw rhks Ms# // //.6 2.. '#k If =anocoters used, verified by Mechanical Engineering cr Ill sections. J 7[9 f6 v-Mach. F gr. .. I Ins %usenta tion $ 5 [gf 6'O 35W ,
!'.anc=eter identification number and calibration v's 3944 g/se/[(C duc date. ID no. ~ C21. E D F.J Total SGTS flcu for test. // 0 /4 b CMihv _[tw I 9fjfg'J,.
U1 SGTS fic i frc: M5 traverse. /4.3 F Cat I Refuel sone SGTS f1cu feca ME / , f i traverse (rcquired only if refuel zone is boins teste'd), bT72. cat l j
- Revision
p .m c +mgp2mmpg n.
.ym.,y.g ,, .e .; . _
r 7-- -- - - - - - - - .
- j
. *Page 21 -
l
< BF SI-4.7.C AUG 0 71933 DATA SHEET SI-4.7.C (Continued) ,
/ ~
Verify Steo Ccmoonent/ Process Variable and/or Record Initials /Dato Additional Traverses - U2 SGTS flow from HE traver:3e. /Ze3 CFM [N 71
/
0 U3 SGTS flow from ME traverse. -
/ 7/h CFM &
6.10 Static pressure readings 1-PdIC-64-2 UIRZ
. /._
e.37 in H O 2 l'M 7N/f4 2-PdIC-64-2 U2RZ r^ ' "
- 3 I in H 20 .
- c. a.w ~.s. .-
3-PdIC-64-2 U3RZ (O .2 6 in H 20
- 4. .
- u. . ..
1-PdIC-64-1 UIRFZ.M 'a f
- f .3/ in H 0 x ,.
2 2-PdIC-64-1 -U2RF4 . 31 in H 0 - p"g 2
.3I 3-PdIC-64-1 3RFZ in H O '
/
2 6.11 Verify damper positions and conditions for ::enes tested. . Unit 1 Reactor 2cno and Refuel Zone (Panel 9-25-1) - 1-FCO-64-9 RFZ CLOSED __ N. W ~ 7[9[f(7 r
-?CO-4*-10 ) ,
2FZ 21.0 S ]
/
r . l
.' ?CO-4.-3 2F2 LOSED
_-?CD-44-43 IC f JLOSED I
', -?CO -4 4- i 2 H2 ;LOSED ~
.- !CC-44-o ??: J
- LOSED
'. - 700 -4 * --2 UZ lLOSED I
' ?C0-44-i*
.- 2' Z LOSED t
.-!C0-04-40 IC OPEN !
.'!OTE :
3ces act : pen .: 3 3GT': rain act used; :nust 'e f a opened . manually
- 'or es . f
.-?CO-o*--a 2F2 :PEU
-'.ni::en
- U/
V
- .c0
-, r -
Pege 22 BF SI-4.7.C .
' AtJG 0 71555 DATA SHEET SI-4.7.C (Continued)
J ~ Verify - and/or Record Initials /Dato Stoo Comeonent/ Process Variable - (Continued) a 6.11 NOTE: Does not open if B SGTS train not used; must be opened manually for test. RIZ _ OPEN cd ?g 1-FCO-64-41 . ually NOTE: Does not ogen if A SGTS train not used; must..be.' opened man
,_. f, ' *b for test.~ ~
(i. $j?. M.* 3 tg RFZ W 1-FCO-64-45 . ,- g~>l OPEN.M% j NOTE: Does not open if A.SGTSEt' raid $ot used; must be opened mar;ually
~
j for test. f c, 2 -( 0 " ' = V f j l Equipment Access Lock ; _ SHUTDOWN Ezhaust Fan (HS-64-65A) ; i j U1 Stair Hall. Supply . i. SHUTDOWN Fan (HS-64-60A) U1 Reactor Zone M Ventilation System (ZI-64-123)' SHUTDOWN .
'J1 Refuel Zone [cw 7[?
6 Terif / lamper: .ositions inc :encitions for :enes :astec. t In:t ' ?asetor *:ne me Tet' mi Cone ' Pnnel 4-??-.') ' - ' 2-!CC-44-3 IF2 :LOSED [t cN 7,h,h6 2-?CO-4.-10 2FI ILCSED
- -iC0-44-i 2F': t'LOSED .
- -!CD-44-43 .C:' ILOSED
- -1C0-44-13 III LOSED t I
- -iCC-du-o IF :LOSED
- -!CO -4 4-- 2 2X:: LOSED f .
! :-iCC-4s-1s U
.' CLOSED
.0TE: Joas loc 2 pen if 3 JGTO : rain act usec; must :e apenou maauall; l
I far ast. 9PEU' g/ i :-!CO-44-41 .1XZ l lCTE: Does not open if .1 3GT3 : a:n not usec; must ce openec manually for tast. , O ew . 4 . 20.WO
4
. 1
/,
Pago 23 BF SI-4.7.C
/ AUG0 7 !!!5 _
. DATA SHEET SI-4.7.C (Continued) .
/. ..
Verify Initials /Dato f and/or Record d Steo Cemeonent/ Process Variable 6.11 (Continued) .
/ /
U2 Reactor Zone Ventilation 2/M 7/7 /f5 System (ZI-64-123) . SHUIDOWI 0
. 'I.]) 4 ,ft.v 7.'9h6 U2 Refuel Zone Ventilation
~
Unit 3 Reactor Zone and Refuel Zone (Panb1'%25-3) ...w j/ 3-FCO-64-9 95 2 , cf.,\ CLOSED & W P4 ii 76
\
I 3-FCO-64-10 - .tFZ .
'? ' . ds .:.CLOSED
' s.
' ip..
3-FCO-64-5 RFL ' , '6" CLOSED f 3-FCO-64-43 CLOSED f RXZ)' A ! 3-FCO-64-13 RXZ CLOSED 3-FCO-64-6 RFZ CLOSED 3-FCO-64-42 E'CZ CLOSED
~
3-FC0-64-14 RXZ CLOSED % NOTE: Does not open if 'B SGTS train not used; must be opened manually for test. 3-FCO-64-41 'RXZ OPEN o Z,w 7/ 8 - o #*fW [I '
'!0TE : ~)oes not' open if .i CGIS train not 'ised: must *:e Opened :anually for ast.
T 73 Otair sail Jupply .
, ff . -
in (HS-44-40A) 3HUIDCWJ /b4 7./7 74
,a
'!3 2eactor one 7entilation /
Jystem ':!-44-123) CHUIDOWI .M w 79.[8 13 2ciuei 'one 7entilation ly taa II-44-1:4i 23UTDCW! ,bW ~1!1.t(( ,
~
.1 2eset :ne .aolation i:;naic for :enes astou inc :ecure : G'"" .
?inoi ? - M *.
' :iS-h-11A JFF [gv 7hk(
-a-a-!A aFF "ps d &c
.-.10-o4 .17 dwo W9/g.
~
.!0E.AL
.-iS-44-;;9 .!0RMAL ,/,ew h/9, gg
' Revision
.2 .10
j
., i Page 24 ~
BF SI-4.7.C J
' SEP 17 !!55
.;p DATA-SHEET SI-4.7.C -(Continued)
Verify Initials /Date Stso Comeonent/ Process Variable and/or Record o 1-HS-64-119 - NORMAL /G,s 7/4Ac 1-HS-64-122 NORMAL 'A fo7fg HS-65-18A . .- AUTO HS-65-40A AUTO __ FCO-65-3 CLOSED _ _ , , i A-SGTS Hu:aidity Control Heater (HS-65-12) 0FF i t h.. a j ,g
,,.y" $
B-SGTS Hur.tidiEyIo t1 ~ Heater (HSg34Y OFF
, . ~
SGTS Fan A (HS-65-18A) 0FF SGTS Fan B (HS-65-40A) 0FF s/ Panel 9-25-2 2-HS-64-1[a- 0FF ILW 7'#V 2-HS-64-3A . OFF _ 'O w /1fs .- 2-HS-64-117 NORMAL 2-HS-64-120 NORHAL _p'e"o$[g'4
,.,o -// ,/# t HS-65-69A AUTO /~ _
C-SGTS Humidity Control Heater (HS-65-60) 0FF 2 2 SGTS Fan C (HS-65-69A) 0FF -g
' Revision 0240Q
' ^
..->e--- .
- 5. . . _ _
Page 25 _- BF SI-4.7.C DE017 C3 DATA SHEET SI-4.7.C (Continued) Verify
' snd/or Record Initials /Dato Sg Cocoonent/ Process Variable C
6.12 (Continued) NW 7/ /L
"
- i Panel 9-25-3 4N6 3-HS-64-11A 0FF >
s
- 3-HS-64-3A cj N OFF 8ts 7[?/k 4" .
- 3-HS-64-117 ,
NORMAL des 7/ if4 y
~
3-HS-64-120 ., p NORMAL few [6 6.13 1-PdIC-64-2y~IRY,U #[A in H 20 die 7/9/f6 e a 2RZ N/A in H20 dt.o /,//fg 9 2-PdIC[Ng y M 3-PdIC-64'-2 U3RZ A//A in H20 7/9 /f6 1-PdIC.64-1 .U1RFZ NA/ in H 20 ./C ;/S/$ f 2-PdIC-64-1 U2RFZ N/A in H 0 2 AD 7/S[#4,
> o-3-PdIC-64-1 U3RFZ
#A 'nH0 i
2 11.J
~h/4
- 7. -
6.14 RETURN TO NORMAL - Refer to procedural note prior to step 6.14. Complete the appropriate portions of this sheet (for cones tested).
- Return the SBGT discharge dampers, which were manually adjusted p in _ j f,, ..
- step 6.6.1, to their original position. Ots V 7,9/40 Unit 1 Reactor Zone and Refuel Zone (Panel 9-25-1) .
U-1 Reactor Zone Ventilation In operation as System required Y/ ul 7!
// . /
U-1 Refuel Zone Vontilation In operation as l System required l 1-FCO-64-9 RFZ OPEN 1-FCO-64-10 RFZ - OPEN 1-FCO-64-5 RFZ OPEN \ )
' Revision '
0240Q .
i o - -- - - - - ;- - -- ___- x . .. . - . . . _ . _. _ _ - . . _ _ _ _ _ _ .,.-. y__....-.--~- l
. 2,
- Page 26 _
BF SI-4.7.C CCC1 7 EI,"a DATA SHEET SI-4.7.C (Continued) Verify Comoonent/ Process 7arinblo and/or Record fnitiala/Date M , fj j/ " 6.14 (Continued) ae W 7/9'[d RXZ OPEN 1-FCO-64-43 f/~ l ) RXZ OPEh 1-FCO-64-13 1-FCO-64-6 RFZ . OPEN 1-FCO-64-42 RXZ OPEN _ .A 1-FCO-64-14 RIZ ,... .' QPEN
. c.,u .h 1-FCO-64-40 RXZ ,
V CLOSED 1-FCO-64-44 RFt .' ,[
- CLOSED _
, .,.g A .y#
CLOSED 1-FCO-64-410
- SIF. -
.;+.y ;>
1-FCO-64-y ' RFZ CLOSED
~
Unit 1 Stair Hall Supply. Fan In operation as (HS-64-60A) required Equipment Access Loch Exhaust In operation as Fan (HS-64-65A) required 4./ Unit 2 Reactor Zone and Refuel Zone (Panel 9-25-2) ,. U-2 Reactor Zone Ventilation In operation as System required [L# J' 7 9/
\b ;
h - U-2 Refuel Zone Ventilation In operation as System required 2-FCO-64-9 RFZ OPEN 2-FCO-64-10 RFZ OPEN
- 2-FCO-64-5 RFZ OPEN 2-FCO-64-43 RXZ OPEN l
j 2-FCO-64-13 RXZ OPEN l 2-FCO-64-6 RFZ OF 'N O
- Revision .
l 0240Q
r l o ,. r>. , ,n ,
, . . . l
,d' '
Page 27 l
/ BF SI-4.7.C -
AUG0 7 M55 7 DATA SHEET SI-4.7.C (Continued) e:
- Verify i I
Stop Cocoonent/ Process Variable and/or Record Ini r.ial3 /Dete l 6.14 (Continued) o Unit 2 Reactor Zone and Refuel Zone (Panel 9-25-2)
* //
2-FCO-64-42 RXZ OPEN ib. v r 7./t?f ; 2-FCO-64-14 RXZ _ OPEN CLOSED ! 2-FCO-64-40 RXZ 2-FCO-64-41 RXZ CLOSr.0 / 2 Unit 3 Reactor Zone and Refuel Zone (Panel 9-25-2)
<.y 9
'U23 Reactor Zone 7entilation 6TInoperationas 'I System Vrequired ,tc#>~77M
[, - U-3RefuelZoneVentila,ti'bak,p In operation as System fx\#2 required
. g*f* ..
3-FCO-64-9 % OPEN
%.-.* )
3-FCO-64-10 b2 OPEN
- -?CC-44-3 1F" OPEN
-?CC-4.- 3 .12Z ) PEN ,.
- -?CO- m-13 U" -] PEN ,
I
- -?CD-4*-4 ZF" GPEN i
- 7CO-44-42 2X" CPEN I l
- -!CO-4 -14 .U" ) PEN i e ~
l-?CD- w--O 2:C ::.0::"D ! i
- 2C0-4.- 1 '?" !*0 SED I T
Jnit : .:t tic fal_ !appi/ Fan _~n 19eration ts MS-4a-iOA) required \/
'Revinen b
. : ..10 5
w.
r v-
,f
'~
.a s s. -
, f' '
,/ Page 28 ,
,e BF SI-4.7.C DATA SHEET SI-4.7.C (Continued) CEO 17 EU Verify Component / process 7ariable and/or Recerd Initials /Dato g _
6.15 Verify all zone pressure controllers jf U1RZ .26 in H 2O /W 7/o/T8
" //
U2RZ in H 2O ' U3RZ J in H 2O U1RFZ f in H90 !
- U2RFZ inHjo i U3RFZ ag__ in H 2O //
If manometers are used, verify they are removed and s'tored and instrument channel p is returned to normal. Mt t.J 1[9[O l' f *
- 6.15.A Main steam tunnel temperature isolation function p- % . ,
Jumper A: Panel 9-15, BB-3 to BB-* Laoved time N /A i
,.y';..f d person t
Removed time Secop/A Jumper B: Panel 9-15, DD-3*to D -4 nf M+&Y d .W , Secpnd person - Jumper C: Panel 9p'7l,';@f3 to BB-4 Removed time N/A x> ., 9 g d;? 5 Second person - Jumper D: Paney 17, DD-3 to DD-4 Removed time A /A Second person Test complete, operators, ASE's, and
~
6.16. / SEs notified. .
,tW 7/9,Ed. -
6.17 Least negative zone a P of those tested (from step 6.10). U "5 R X "4 . Z #.= in H 2O fis 7/qd7g
/
Zone
~
Most negative zone a P of those not tested (from step 6.6 and 6.13). N/A NfA_ in Hg0 NfA _ Zone Required differenco from Table 1. 26 in H2 O iI.zs 7,[.7,/G - 6.18 Technical specification 4.7.C-1 is satisfied. (All zonas have boon tested and the required a P for each zone tested has been established with flou 5 sum of the baseline flows for the appropriato ccm'inction o of zones tested.) Engineering Supervisor or Roactor Engineering W W supervisor approval to break, primary containment. /7/7/86 I) ate
' Revision
-)$ , A
- A T l 6 O 'l O lu s T*l k r 7b Te P.ChovC Me-enfr e tc 5 o e' H sCri+r5 tt-c.C t~.
I ~ O ~ - __ _ _ . . . . _ _ _ _ _ . _ a
e' f .s ,, , o TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374o1 Lookout Place 8 5 S E P l a- A D 15 3 S P 111986 U.S. Nuclear Regulatory Commission Region II ATTN: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, Suite 2900 Atlarta, Georgia 30323
Dear Dr. Grace:
BROWNS FERRY HUCLEAR PLANT - REACTOR BUILDING CONTAINMENT LEAK RATE TEST - 90-DAY REPORT Enclosed is the report on secondary containment leak rate testing for the Browns Ferry Nuclear Plant. The secondary containment for all three reactor zones and the common refuel zone was leak rate tested on July 9, 1986. This report is submitted pursuant to Browns Ferry Technical Specifications Section 6.7.3.C.l.a. If you have any questions, please call M. J. May at (205) 729-3570. To the best of my knowledge, I declare the statements contained herein are complete and true. Very truly yours, TENNESSEE VALLEY AUTHORITY R. L. Gridley Director Nuclear Safet and Licensing Enclosure cc (Enclosure): Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. R. J. Clark Browns Ferry Project Manager l U.S. Nuclear Regulatory Commission ! 7920 Norfolk Avenue Bethesda, Maryland 20814 l
.m ..-.-vr~
l [ n', ,wm- v.r , w - *
$.,. WA g) {/(
l An Equa: Opportunity Employer __ _ _ _ _ . . _ . _ _ _ _ _ ,}}