ML20137P855
| ML20137P855 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/31/1997 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20137P828 | List: |
| References | |
| 92-008*Q-02, 92-8*Q-2, NUDOCS 9704100027 | |
| Download: ML20137P855 (72) | |
Text
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IWP NUMBER: Q9-008*O -02 Page_d_cf11 INSTALLATION WORK PLAN PBNP MINOR PROCEDURE ,
- Check As
- Applicable MAINTENANCE WORK REQUEST WORK PLAN h s
- ~-
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FOR MODIFICATION # 42-OMO ~~' M W 9'701le2
' INSTALLATION WORK PLAN TITLE ,
. Wr-ine. 'TAvik. %1dr> tor M&Ohrafb1 UNIT __.O_. b QA-SCOPE h NON QA SCOPE Originato Date /!3/!D Reviewe - Date El 3 AAs 9 7 Final Design , !' ^
Group Head ___' Date Quality Engineer Al/A -
Date to M ,
Date i _ _ _ _,,., \
Manager - p7 e -fe* - .
j t- Oport+ ions or DSS . ,,. 3 Date NOTE: Changes to this work plan must be with the concurrence of the responsible or team engineer and the installation surpevisor, or as delineated within the IWP.
DG-G02.5
- Revision 0 9704100027 970401 '"
1
m WO WORK PLAN IWP 92-008*Q-02 Brine Tank T-118 Standpipe Modification Non-QA January 31. Iw7 Originator: Elizabeth Hellman x
- 1. SCOPE .
1.1 This work plan directs the modification of the standpipe in the Water Treatment System brine tank (T-118). The modification consists of cutting a hole in the wall of the standpipe and attaching a U-shaped plastic or fiberglass tube to the outside surface of the standpipe.
1.2 The purpose of this modification is to improve the ability of the brine tank high-high level switch (LE-9212) to prevent brine from overflowing the tank.
1.3 The approach is to improve the accuracy with which the standpipe level reflects the bulk tank level during filling of the brine tank by facilitating level equalization between the bulk tank and the standpipe. The reason for installing a U-shaped tube instead of simply drilling a hole in the standpipe is to minimize salt entry into the standpipe. The tube is designed to contain liquid (brine or water) to act .is .i trap to prevent salt from entering the standpipe and coating the Ics el m ih h 1.4 This work is Non-QA Scope.
1.5 Support Requirements
1.5.1 Operations
Perform equipment isolation, install and remove Danger Tags, and support installation and testing of the modification.
1.5.2 Contemporary Products Incorporated (CPI, contractor): Install the modification.
I I&C: Support installation and testing of the modification. I 1.5.3
1.5.4 MTN-M
Support installation and testing of the modification.
- 2. PRE-INSTALLATION REOUIREMENTS 2'l
References:
2.1.1 Sketch SK 92-008*Q-04 Sheets 1. 2. and 3 2.1.2 Permanent Drawings:
A. Bechtel M-210 Sheet 3 Page 1 of 12
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. WO WORK PLAN IWP 92-008*Q-02 Brine Tank T-118 Standpipe Modification Non-QA Originator: Elizabeth Hellman January 31,1997 B. Gaco 41D Sheet 2 C. Plstki SK-Model Responsible engineer has assured that all references listed above are approved and are either with the installation group or attached and assigned to the installation group.
, _ Date_4/3[97 R.E_[____.__
'!.l.3 Supplemental Procedures A. NP 1.9.4 " Confined Spaces Procedure"
- 3. NP 8.4.10 " Exclusion of Foreign Material from Plant Components -)
and Systems" j 2.2 Installation Prenaration Activities:
2.2.1 The materials needed for this modification are to be supplied by the l contractor, Contemporary Products Incorporated, with the exception of
{
those listed in step 2.2.2.
2.2.2 PBNP is to supply a ladder, FME plug and other FME materials, and (if l needed) a 1/2" SS Swagelok cap (lot # 901-3709). l 2.2.3 No new champs identification numbers are required for this install.iii..n 2.3 Identification Of Permits Reouired 2.3.1 The work order (WO) for this work plan has been written and submitted to champs. The WO number is 9701182.
I R.E.
2.3.2 If necessary, a Confined Space Entry Permit has been obtained. (The alc This aiu . . .- . . .
permit is necessary if entry into the brine tank is required for installation of g
- g. p the modification.)
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I Page 2 of 12
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WO WORK P LAN IWP 92-008*Q-02 Brine Tank T-il8 Standpipe Modification Non-QA January 31,1997 Originator: Elizabeth Hellman 2.4 Pre-Installation Prerequisites:
2.4.1 A pre-installation discussion with the installation group representative, the testing group representative and the acceptance group representative has been performed.
R.E. Date .P/3/4 7 2.4.2 A field alkdown has been performed, if necessary, to verify that all aspects of the procedure may be perfopned as intended.
4 b Installation Supervisor (I.S.)__ _Date /77 2.5 PrcInstallation Work Note: The next two steps may be signed off anytime prior to step 3.1.x of this ,,wl.
plan.
2.5.1 Maintenance has pre-fabricated debris " trap" for catching debris and other materials during U-tube installation on brine tank standpipe. 9 Ulh 3 k}l '
R.d. or MTN 2.5.2 Contractor has pre-fabricated plastic / fiberglass U-tube.
R.E.
2.6 Oncrational Installation Prereauisites:
2.6.1 Plant Conditions: ;
l The installation of the U-tube is expected to take one shift; however, the )
i material used to join the U-tube to the standpipe requires four day s to cure Testing will also require ere additional <bift followine the curine renod I hc
, plant conditions required to support this installation are as follim s i
A. Salt shall not be delivered to the brine tank until after the completion of the installation, curing, and testing phases.
B. Prior to installation, the salt level in the brine tank shall be as low as possible.
Page 3 of 12 )
WO WORK PLAN IWP 92-008*Q-02 Brine Tank T-118 Standpipe Modification Non-QA January 31,1997 Originator: Elizabeth Hellrnan
'C. The liquid level should also be maintained as low as possible to minimize the I
quantity that must be drained from the tank.
D. During the installation, curing, and testing periods (approximately sis Jap total), Operations will not be able to perform any organic trap iegenei.on e Therefore, the organic trap resin should be freshly regenerated prioi a beginning the installation.
2.6.2 Prepare the following Danger Tags for the items listed below. Do not hang the tags until instructed to do so in the installation section.
A. Breakers B52-712B and B52-712D Off i
(Power for P-85A and P-85B)
B. Valve DI-68 Shut (DI water supply to brine tank)
C. Valve DI-69 Shut f (DI water supply to brine tank sprays) l D. Sliders TB3-47 and TB3-48 in C-211 Open l l
(Power to LE-9212) shed E . \/alve T A -14to o Ebble sgste.mD * *) l 2.6.3 Release For Installation 7
f' alec WT- 250A rxsef.c vaive sud WT-2 b bire SOS pu.os P45A'. t450 All of above opera dHal mstalIation prerequisites hase beeh met and $ gyp it is acceptable to proceed with the installation.
I DSS _. , ,
Date NT/12 Time /V,/
Note: Steps 2.5.1 and 2.5.2 do not have to be completed at this time, but they must be completedprior to step 3.1.8 of this work plan.
. Q.'1 o s -
-264 All other installation prerequisites have been met.
R.E._, __ Date 4/3/4 7 6
Page 4 of 12
WO WORK PLAN IWP 92-008"'Q-02 Brine Tank T-118 Standpipe Modification Non-QA January 31.1997 Originator: Elizabeth Hellman
- 3. INSTALLATION 3.1 Installation Descrintion:
i Note it Thefollowing is a detailed step-by-step listing of the actions necessary to perform this IWP. These steps can be completed in any logical order, as long as all necessary equipment isolation tags are hung at the appropriate times. If any ofthe steps cannot be completed as written or a change is necessary to complete the task, work must stop and the l situation must be discussed with the responsible engineer or the l installatwn supernsor. !
l l
Note 2: Foreign material exclusion (FME) work practices are in effht durin:t j
the performance of this procedure. Check all tuuls and equipmem for loose parts and dirt. Cover all openings when the system or unnpunem ,
is open. Perform visualinspectionsforforeign materialprior to assembling the system or components when access will be limited.
Note 3: Nottfy Terry Slack and'or Dennis Evers before draining T-118. (Brine sump l pump discharge goes to STP.) y4 m pc \
WN&RP *y n I 3.1.1 Drain tank T-118 by opening valve V'T-252 "T-118 Brine Tank Drain')\until g liquid !cvd b ebuut ene fcc: above +ep af;; rave! (about '"ce fee: abe'.e bot:an; af-
@W-sank 3- 4W 6 m Uquid hvd M 4k krtk. ,
OPS 3.1.2 Danger Tag breakers B52-712B and B52-712D into the OFF position to isolate power to brine pumps P-)(RIA/B.
OPS 3.1.3. A. Danger Tag open the fbliowing sliders to isolate power to high lugh few m.u ;
LE-9212:
, , w -
TB3-47 and TB3-48 located in C-211.
OPS 3.1.3,bt 1)cus ev 4tt SM laulMer s$s k 1 A ' N d'
- y h e Zh- % 0. IB.h CPS 3.l. 3. c h v dag shdg~akes 2608 DMB, M% Mb DJT- 60A and W 4 p(11 Page 5 of 12 g-
1 WO WORK PLAN .
1 IWP 92-008*Q-02 l i
Brine Tank T-118 Standpipe Modification Non-QA Originator: Elizabeth Hellman January 31,1997 Vev' divcuit foy lEM11 iS cle-enegifec l,-Sm 3.1.4 ,Using wire removal form, disconnect wiring from level switch LE-9212. Then, remnve Ire.,! st":tch fran; gange anJ me H 2f p! ; _n.o :: - n!!2t:m per %d thi: !"/P. Cicen Icvc! ve t ich pmb i*h va. ;f vuAd ,,ah ah. j Sic:ar lvwnvu. --
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Note: Before removing theflange, the stainless steel tubingfrom the bubbler system and the brinepump sealflush discharge may need to be disconnected. Make sure that the sealflush discharge tube can be re-connectedfollowing testing.
(9sf1. Add;& aa q ,+k ou.bble r 4 ave. ,0"41 A.) w:Il Alld k Lt.Ltrt- Ltafkd dAri ( m'vgl, 3.1.5 Unbolt and remove flange from top of brine tank standpipe. Mert. tragad hd5 in a. Sal <. F4ato anHl n-i Ashtlatrea pu -Hsts M. -
. CitM lud f.wi+<APrek # cJartd vi+A sa.lt tuM. wakr3 M. i lyg,)gt ) , Mala sve. 4hA+ Nt. Iwd pw. is verted. divq E43r4 j W l 3.1.6 Insert plug in standpipe N!ct" !: vel of exisung hoic in 2ndpipe va!!
933 , so 4%tt 4ep 4 pg is d kaS+ A," belev 46p 4 star 1dPyt.
NathU gg g g wQ 3.1.7 If disconnected, cap stainless steel line from bubbler level control system.
M i.-
Note: Vertfy that steps 2.5.1 and 2.5.2 of this work plan have been cmnpleted piiar to performing step 3.1.8.
3.1.8 Open manway on top of brine tank and insert ladder.
OPS hr CPI 3.1.9 Install temporary debris " trap" in brine tank. .
$&rN ( rU jf Note: Utilize good FMEpractices while ifrilling holes and installing U-tube, such as taping pockets and using lanyardsfor tools.
3.1.10 Per Sketch SK-92-008*Q-04, drill new hole or modify existing vent hole in wall of standpipe to accept new U-shaped tube. -
CPI Page 6 of 12
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WO WORK PLAN IWP 92-008-Q-02 Brine Tank T-118 Standpipe Modification Non-QA Originator: Elizabeth Hellman January 31,1997 3.1.11 if existing vent hole was modified in step 3.1.10, drill new 1/4" diameter vent hole in wall of standpipe as indicated by Sketch SK-92-008*Q-04. i hll/k '
CPI I 3.1.12 Install U-shaped tube in brine tank. Orientation shall be as indicated on Sketch SK-92-008
- Q-04.
kPI Mr* F "i ! ,
3.1.13 Remove temporary debris " trap"3 f rom brine tank. w.resM b cFL JEljt 3.1.14 FME Closeout: Check to make sure debris is cleaned up around location of noik Verify all tools and foreign materials have been removed from work area.
MTN l
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CPI l
3.1.15 Close manway and cover standpipe.
OPS or MTN 3.1.16 Allow installation to cure at room temperature for four days or as recommended I by CPI. (Note CPI's recommendations below.) I
> .2 4 h r3 - l l
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< ms o, Ri 3.2 As-Built Description ;
This IWP was installed by:,_ Date )
The installation was performed in accordance with this IWP and Sketch SK-92-008*Q-04.
Attach any additional documentation for the as-built description to this IWP.
Page 7 of 12
WO WORK PLAN IWP 92-008*Q-02 Brine Tank T-118 Standpipe Modification Non-QA Originator: Elizabeth Hellman January 31,1997 3.3 The installation of this IWP is complete.
R.E.
1.S .
Date Date gi a y'/ .//d[/97 I l
- 4. TESTING 4.1 Testing Prereauisites:
The intent of the testing is as follows:
1 A. To verify that the newly installed U-tube functions as expected, and '
l B. To verify that the ultraso'nic level switch is set up properly. 3 . g, .g 4.2 Level Equalization Testing tg,1 v.2.6 L,un- prpe. P% M4v ecu.umg 40, ris eff c4-4. qm" 4.2.) Remove danger tag for DI-69, open DI-69, and begin filling brine tank with water.
Monitor both bulk tank and standpipe levels during fill process and. if possible. l note (below) any difference between the two levels. l 3" din esn wl ~ D h 'lih > ,;{ lw&nL
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4.23 When liquid level is even with the uppermost horizontal surface of the I -tobe begin timing how long it takes tbr the standpipe level to reach the bulk tank les el.
Continue filling tank with water until liquid level is at least 2" above uppermost horizontal surface of U-tube (but not high enough to cause tank to overflow).
Verify that level in standpipe reaches bulk tank level within one minute. Record how long it takes for levels to equalize. k N'; 2/u u h o' M ttL 4:e#, W 6 n
.1 g Its 1 atM .JQA G- C'kk b b yt _
OPS or R.E.
4.3 Ultrasonic Level Switch Testinc ~
,,t
- i~ ll $41 V .4.3.1 MountlewLswitch LE-921; a brine tank >t$ndpipr flange. Place flar.ge on
/
standpipe but do not bolt flange to standpipe.
_l&C 4.3.2 Re-connect wiring to LE-9212 per wire removal form generated in ste9 } : 4 IM Page 8 of 12
WO WORK PLAN IWP 92-008-Q-02 Brine Tank T-118 Standpipe Modification Non-QA Originator: Elizabeth Hellman January 31,1997 4.3.3 Remove Danger Tags and close following sliders to provide power to LE-9212:
TB3-47 and TB3-48 located in C211.
~
OPS Note: In thefollowing step, Switch SWI on LE-9212 will be depressed to actuate a test of thefunctionality of the ultrasonic switch.
4.3.4 Depress the Test button SWI on LE-9212 and verify that the Green I ed hght powers on and Red Led light powers otT.
7 i5C 4.3.5 Verify that WT-9211-S is in auto (not in manual override).
~
Af Fff . .i lw & OPS 'I 4.3.6 Inform Control Room that testing of the brine tank high-high level switch is about to begin which will bring in an alarm on Pretreatment Control %mi C .00.
OPS or R.EI 4.3.7 Open valve DI-69 (Brine Tank Spray Supply).
~
OPS/
Note 1: OPS should be prepared to shut valve DI-69 af the newly installed wlenoid valve WT-9211-S does not shut when expected in thefollowing step.
Note 2: The next two steps may be accomplished by keeping LE-9212 mounted on the flange and having one person hold theflange above the standpipe while another person handles the container of water.
., w -
4.3.8 I&C: Dip the probe on the ultcasonic level switch slowly into a container of water so that the gap is submerged.
OPS: Verify that valve WT-9211-S shuts when the ultrasonic level switch gap is submerged.
Ol lS Page 9 of 12
WO WORK PLAN IWP 92-008*Q-02 Brine Tank T-118 Standpipe Modification Non-QA Originator: Elizabeth Hellman January 31,1997 4.3.9 J&C: Slowly take the ultrasonic level switch probe out of the watei OPS: Verify that valve WT-921 l-S opens when the ultiasome Ics I , h- .
is taken out of the water.
(A)S l 4.3.10 Shut valve DI-69.
UPS i 4.3.11 Inform Control Room that testing of the brine tank high-high level switch has been completed and all further alarms on Pretreatment Control Panel C-210 should be regarded. 1 I
6PS or R.E.
I 4.3.12 Perform FME closeout inspection for standpipe.
~'
\11N I
- CA UTION
- DO NOT OVERTIGilTEN Tile FLANGE ilOLTN.
OVERTIGilTENING Tile IlOLTS .41 AY DA\l AGI' I Ill FIBERGLASS STANDPIPE. l 4.3.13 Bolt flange back onto top of standpipe and reconnect tubing for brine pump seal flush discharge. ( Abbt</w., Ages rte + vtud 4 ht vt- aged.'"Ag syplg IML4o ba.bblu au.bs. elad ,d ruid 4e bt 4.- cutALLhd )
(S 4
MTN 4.4 Testine Results:
4.4.1 The testing of the installation has been completed and the results are described below:
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. 'ru t li lt ihd ~ll 1 thu t
a < :rti to t mn u kil Ade s o u iA 3ifnd.
4.4.2 The testing is completed and adequately tests the modification and the associated installation:
Testing Supervi,sor 1, Date 2h/97 R.E. Date,j/)6/97 Page 10 of 12
\
WO WORK PLAN IWP 92-008*Q-02 Brine Tank T-118 Standpipe Modification Non-QA January 31,1997 Originator: Elizabeth Hellman l
5.0 Restoration
5.1 Pre-Acceptance
Prior to acceptance, all ECRs shall have final approvals and all applicable control l
room and work control center drawings shall be updated.
All items that need to be completed prior to acceptance have been completed.
R.E. Date 2/JE//7 i
5.2 System Restoration. '
gg fg(- "> /ahl '
Note 1: , flanger Tags, remain hung on breakers BS2-712B and BS2-712D, valve Dl-68,
=! 2: D.' S" and can be removed at the discretion of the DSS.
valve NT-250A awd vctive wr-2Eo6, cmd JA f @oC gym
.fglC The salt level in T-118 is low and the liquid levelis high. Salt may need to be Note 2:
ordered soon. Before salt can be delivered to the tank, the liquid level will probably need to be lowered.
Realign system as required for normal operations /per DSS. System ready for release.
DSS -
Date WM/97 Time gjf.
rg
6.0 Restoration
6.1 Conditional Accentance d/h 2tm91 6.1.1 The following items cannot be accepted and require resolution of the listed conditions. Interim operating conditions are also listed belowIattach additional documentation as necessary).
6.1.2 Concurrence with Conditional Acceptance Mgr of Acceptance Group / DSS Date Page 11 of 12
WO WORK PLAN IWP 92-008*Q-02
- Brine Tank T-118 Standpipe Modification Non-QA Originator
- Elizabeth IIellman January 31.1997 6.2 Final Acceotance Realign system as required for normal operations /per DSS. System ready for release.
Mgr of Acceptance Group / DSS _j <_. Date X>r/ 9 7 RETURN TIIE COMPLETED IWP AND MODIFICATION REQUEST TO RESPONSIBLE ENGINEER.
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FILE: A5.7 ECRs l NUCl_ EAR POWER BUSINESS UNIT ENGINEERING CilANGE REQUEST sheet I ol ,3 ccRy97- 000 8 + suwssacac Project Manager: Mod #!Affected Document #: C QA l Elizabeth llellman MR 92-008*Q X Non-QA l Reference Documents:
IWP 92-008'Q Problem Description and Proposed Changes:
MR 92-008*Q was initiated in part to provide a means of overnow protection independent of the normal level control system for the Water Treatment System Brine Tank, T-Il8. The installation of an ultrasonic, gap sensor-type level switch in the brine tank standpipe and a high-high level alarm provided the independent overCow protection. However, questions remain as to how accurately the level in the standpipe reflects the level in the bulk of the tank. Thus, the ability of the high-high level switch to prevent brine from over0owing the tank is questionable.
Th proposed change is to implement some means ofimproving the accuracy with which the standpipe level redects the bulk tank level.
Preliminary Approval By/Date: N/A ,
Resolution- (ltt atfMdul M' Documentation Updates Required: 10 CFR 50.59 and 72.48 Evaluations (specs, procedures, drawings, etc.1 DUC Required: X Yes []No Drawing Plstki SK-Model Design Veri 0 cation Required: X Yes ^JNo_.
Peem. D*.
Initiation Hv/Date: Additional Reviews By/Date: j f, Technicaljle n 1/16'97
/,
/
Resolution By/Date; j/gg/g f Project Manager Review tfy/Date: l dx hv .. ,, .
dronn Head Approval By/Date: Implementation Completed By Date:
(/3(lf2 a
PilF 1$91 Reviwn 2 11/1$/96
1/29'97 l
Design Documentation MR 92-008*Q/ECR 97-0008 Brine Tank Standpipe Modification ECR 97-0008 Resolution:
In order to improve the accuracy with which the standpipe level reflects the bulk tank level, the brine tank standpipe will be modified to facilitate brine transfer from the bulk of the brine tank to the standpipe. This modification involves cutting a hole out of the wall of the standpipe and attaching a U-shaped tube to the outer wall of the standpipe at the location of the hole. The U-tube will contain water or brine at all times to trap and dissolve salt before it can enter the standpipe and coat the high-high level switch probe.
The U-tube will be fabricated (by a contractor) from fiberglass or plastic so that the tube will withstand corrosion and will be capable of bonding to the fiberglass standpipe. The l
diameter of the tube will be 3/4-inch nominal per Calculation # 97-coM . The dimensions of the tube will be as shown on Sketch SK-92-008*Q-04. The dimensions of the tube are based on the following criteria:
- The horizontal dimensions of the tube should be as small as possible to prevent the tube from becoming " weighted down" and to minimize its chances of getting in the way of any maintenance activities inside the tank.
- The vertical dimension of 2 inches was chosen to keep the tube small and unobtrusive and yet allow liquid to be maintained in the tube.
The hole and U-tube should be located low enough on the standpipe to ensure that level equalization occurs in time for the high-high level switch (LE-9212) to prevent overflow yet high enough so as to minimize the exposure to the salt mound. To ensure that the U-tube remains filled with liquid, the tube should be placed within the range of the de-ionized water spray in the tank. Since the high-high level setpoint is located 17 inches below the flange on the standpipe (which equates to about 2 inches below the straight side of the tank), the hole should be drilled at least 2 inches below the setpoint for an i extra margin of safety. (During a salt delivery to the brine tank, the liquid level in the tank takes at least one minute to rise 2 inches. Based on r 'alculation # 41-0C3 l , an 18-inch level difference can be made up within about %sewds) The hole may need to be lower depending on the spray water coverage. Therefore, the hole should be located 19 to 25 inches below the flange on standpipe (or 10 to 10.5 feet above the floor of the tank). If the existing vent bole in the side of the standpipe is in that range, it should be enlarged to accommodate the attachment of the U-tube and a new. smaller vent hole of approximat:ly 1/4 inch in diameter shall be drille Un the standpipe uali as indkated on .
I Sketch SK-92-008*Q-04.
i The U-tube will be provided and installed by Contemporary Products incorporated ot ;
Milwaukee. The installation is expected to take one day, and a curing time of about 4 l days will be required following attachment of the U-tube to the standpipe, i 4
Page,1 of 3 l I
l
1/29/97 Additional
References:
Sketch SK-92-008*Q-04 Permanent Drawing Plstki SK-Model Calculation #4 r-m31 h F j Page 3 of 3 m
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DESIGN VERIFICATION NOTICE k'itle cf Document 3 6nt TMtb bi b1dT h NAdibTr.A4ftvt Document No. Ef32 9 7-DOOA / MN b-COf*+O Rev. d Date I/29 [9'7 Design Verification Method: Design Review 0 Alternate cales qualification Testing REVIEWER CHECKLIST CONSIDERATIONS:
- Yn Eq E%
- 1. Were the irputs correctly selected and incorporated into design? /
- 3. Ar assumptions necessary to perform the design activity adequately described and reasonable? Where necessary, are the assumptions identified for subsequent reverifications when the detailed design activities are completed? /
- 3. Are the appropriate quality and quality assurance requirements specified?
/
4 Are the applicable codes, standards, and regulatory requirements including istue and addends properly identified and are their requirements for design met?
p
- 5. Have applicable constniction and operating experience been conside' red?
- 6. Have the design laterface requirements been satisfied?
- 7. Was an appropriate design method used?
/
- 8. Is the output reasonable compared to inputs 7
/
- 9. Are the specified parts, equipment and processes suitable for the required application? /
- 10. Are the specified materials compatible with each other and the design environmental conditions to which the material will be exposed? /
/
- 11. Have adequate maintenance features and requirements been specified?
- 12. Are accessibility and other design provisions adequate for performance of needed ,
/
maintenance and repair?
- 13. Has adequate accessibility been provided to perform the in-service inspection expected '
to be required during the plant hfe?
14 Has the design properly considered radiation exposure to the public and plant #
personnel?
- 15. Are the acceptance critena incorporated in the design documents sufficient to allow verification that design requirements have been satisfactorily accomplished?
/
- 16. Have adequate pre-operational and subsequent periodic test requirements been
./
j appropriately specified, including acceptance criteria?
- 17. Are adequate handling, storage, cleaning, and shipping requirements specified? '
- 18. Are adequate identification requirements specified? _ !
- 19. Are requirements for records adequately specified?
- 20. Will the change remain within the analyzed or specified capabilities of any affected j equipment?
- 21. Has a field inspection been done? /
27 Have impacts on other systems been identified? ,
l COMMENTS: None Attached (Use Fonn QP 17.1-2) l Design Prepared By: _
Date /!d9 /77 R:v r.wed By: -
Date lNN) i j
Approval By: Date ) 1 l
PB?.t$83 Page 1 of1 j Revision 0 07/14/94 i
L NUCLE AR POWER DEPARTMENT SER
Date:
2.
I Date:
MSS Review /Date: \1SN :
Manager- PBNP Approval: Date
_ l in lieu of MSS and Manager signature, attach PBF-0026d if serial review has been conducted (MSS and manager )
approvals are not necessary for a determination of non-applicability.)
Section 1 Screenine - Determination if Safety Evaluation is Reauired A. Describe the modification, procedure change, test, or experiment and its expected efTects. Include interim con 0gurations or conditions.
ECR 97 0008 seeks to improve the accuracy with which the brine tank (T 118) standpipe level reflects the level in the bulk of the tank. The proposed means ofimproving level equalization between the standpipe and the bulk of the tank is to cut a 3/4-inch diameter hole in the wall of the standpipe and attach a 3/4-inch diameter U-shaped tube to the outer wall of the standpipe at the location of the hole. The U-tube will contain wate; or brine at all times to trap and dissolve salt before P can enter the standpipe and coat the high-high level switch probe. The hole and U-tube will be located low enough on the standpipe to ensure that level equalization occurs in time for the high-high level switch (LE-9212) to prevent overCow yet high enough so as to minimize the exposure to the salt mound. To ensure that the U-tube remains filled with liquid, the tube will be placed within the range of the de-ionized water spray in the tank. Given those constraints, the hole and U-tube will be located within 10 to 10.5 feet above the floor of the tank, with the exact location to be determined in the field at the time of installation During the installation and for approximately four or five days afterward, the brme tank will be out of seruce .inJ no ou um trap regenerations will be possible. Additionally, salt shall not be dehsered to the brme tank until af ter the tesi ng en.iw ..' W.
installation has been completed.
B. List the FSAR sections or VSC 24-SAR sections where the system, structure, component, procedure, test or experiment is described.
None C. Does the change, test or experiment involve a change in the Technical Specification? O Yes (3 No if a change is required, briefly describe what the change should be and why it is required.
NOTD NRCapprovalis requiredprior to implementation.
PDF1515 Redion 5 9 26/96
i NUct FAR POWER DEPARTMENT SER SAFETY EVALUATION REPORT Page 2 i
Section 1 - Continuatlan ;
D, Screenina for 10 CFR 50.59 and 10 CFR 7148 Acolicability:
- 1. 10 CFR 50.59 Screenine
- a. Will any system, structure or component (SSC) described in the PBNP FSA R including its O Ye' ":' %
figures, be altered? (Refer to NP 10.3.1, step 3.1.2 for exception. This questmn may be answered "no" although the SSC is described in the PBNP FSAR.)
- b. Could, within reasonable possibility, the proposed change affect the intended design, operauon. O Ye' G% i
. function, or method of function, of an SSC important to safety which is described in the PBNP )
FSAR7 (This includes interim conditions.)
- c. Will any procedure described in the PBNP FSAR be altered? (Refer to NP 10.3.1, O Yes @ No Attachment A, Part E, for guidance.)
- d. Will a test or experiment be performed which is not described in the PBNP FSAR and affects the O Yes @ No design, operation, function, or method of function, of an SSC important to safety which is i described in the PBNP FSAR7
- e. Will implementation affect a prior documented regulatory commitment to the NRC pertaining to O Yes @ No the design, operation, function, or method of function, of an SSC important to safety which is !
)
described in the PBNP FSAR7
- f. Is a 10 CFR 50.59 cvaluation required (are any of the above questions answered yes)? O Yes @ No ]
NOTE: Ifno, then provide hashfor decision in Part D. l Ifyes, complete Sections 2 and.1.
- 2. 10 CFR 7148 Screenina for the Indeoendent Soent Fuel Storage Installation (ISFSit
- a. . Will any system, structure, or component (SSC) described in the ISFSI Licensing Basis O Yes OM document, including its figures, be altered? (Refer to Step 3.1.2 for exception. This question may be answered "no" although the SSC is described in the ISFSI Licensing Basis documents.)
- b. Could, within reasonable possibility, the proposed change affect the intended design, operation, O Yes @ No function, or method of function, of an SSC important to safety which is described in the ISFSI Licensing Basis documents? (This includes interim conditions.)
- c. Will any procedures described in the ISFSI Licensing Basis documents be altered? O Yes g No
- d. Will a test or experiment be performed which is not described in the ISFSI Licensing Basis O Yes O No documents and affects the design, operation, function, or method of function,'of an SSC important to safety which is described in the ISFSI Licensing Basis documents?
. 3+ > ~
- e. Will implementation affect a prior documented regulatory commitment to the NRC pertaining to O Yes @ No the design, operation, function, or method of function, of an SSC important to safety which is described in the ISFSI Licensing Basis documents?
- f. Is a 10 CFR 72.48 evaluation required (are any of the above questions answered yes)? O Yes O%
NOTE: llno, then provide basisfor decision in Part D.
Ifyes, complete Sections 4 and 5.
PBF.1515 Reviston 5 02W96
si H NUCI FAR POWER DEPARTMENT Page, SAFETY EVALUATION REPORT Section 1 - Continualign
~ D.
Basis for determination that a safety evaluation is not required:
This modification adds a U-tube to the standpipe in the Water Treatment System Drine Tank (T-118) to cqualization between the standpipe and the bulk of the tank and thereby improve the ability of th switch (LE-9212) to prevent the tank from overflowing. Thus, the modi 5 cation involves making a cha QA Scope, Non-Safety Related component which will not affect the ISFSI or any SSC important to Treatment System Drine Tank is not referenced in the PBNP FSAR or Technical Specincations. For these neither a 10CFR50.59 nor a 10CFR 72.48 evaluation is required.
1 1
l
, ., y IPF l$l$
Revbion 5 W26N6
POINT BEACH UNIT 2 RESTART COMMITMENT INDEPENDENT REVIEW RESULTS Commitment ID Number 70 Commitment Description Install a new level control system for the brine tank (T-118) per Modification 92-008 *Q.
The tank overflows because the installed automatic level control system is not effective, and there is no high-high level alarm for the tank. This has been a recurring human performance issue exasperated by design. This modification will minimize the human performance challenges.
Review Methodoloey Review modification with Responsible Engineer.
Review modification scope, and if scope was changed, determine change rationale and if there is any safety impact.
Review modification design and installation documents against scope. Identify and review documentation acceptance items.
(~_
Verify that the documentation is adequate and that the documentation acceptance items have been completed and documented.
Review the modification tests to verify that the tests are appropriate and were successfully completed.
~
Determine if Condition Reports (CR's) were generated in performance of this modification and verify that they are documented / tracked.
Review Results MR 92-008*Q is the Brine Tank Level Control Modification. The original design installed for MR 92-008'Q under IWP 92-008'Q did not provide an acceptable solution to the brine tank level indication control problem. Although the Work Plan was installed, tested, and restored to operability, only a portion of the physical work was conditio accepted for use. Restart Commitment #70 was initiated to address the elimination of the Operator Workaround for the brine tank (T-118) overflow. This commitment exists because IWP 92-008'Q was unable to install design solution. Therefore, to address Restart Commitment #70, ECR 97-0008 was initiated to modify the sta
+
with a U-shaped tube to provide an alternate fill method of the standpipe. This tube would quickly equalize the bulk tank Icvel with the standpipe level, thus ensuring an accurate reading for the high-high level alarm. Since the hig high level alann was successfully installed, tested and conditionally accepted under IWP 92-008'Q, this review will only consider the workscope related to modifying the standpipe under ECR 97-0008.
4 The scope of work associated with ECR 97-0008 was discussed with the Responsible Engineer (RE). No issues or concerns regarding installation or testing of the moditbai.n were identified by the RE.
\ ,.
Page1of2
t 1
POINT BEACH UNIT 2 RESTART COMMITMENT
, INDEPENDENT REVIEW RESULTS t
Commitment ID Number 70' j
-The Safety Evaluation screening, ECR 97-0008 and Installation Work Plan 92-008*Q-02 were reviewed. The
- j. evaluation screening matched the ECR and Work Plan (both it scope and content).
IWP 92-008*Q-02 has been completed and approved by the DSS. Work Order 9701182 is currently at a status 70 even though the work has been completed and tested Acceptance by the DSS of the Work Order nxds to be -
provided as an acceptance item to the Unit 2 restan.
4 The modification has been satisfactorily installed. The acceptance items identified in IWP 92-008 *Q-02 identified
) that ECR's and Control Room /WCC drawings need to be updated. Based on discussions with the RE, no ECRs were generated in support of this workscope, and no Control R.oontWCC drawing changes were required ' Therefore the .
j acceptance items identified in IWP 92-008'Q-02 were not required.
PMT consisted of functional testing of the stand pipe fill line and ultrasonic level switch. In addition, an operational ;
test of automatic isolation valves was performed. The PMT actions have been satisfactorily completed and signed 1 off. Based on the scope of this installation, these tests are appropriate PMT for the installation.
No Condition P.eports have been generated in performance of ECR 97-0008. This was concluded based on an interview with the Responsible Engineer and performing an electronic search of the NUTRK system using the 3 Modification number and Work Order number as search criteria.
)
Conclusion '
- Work Order 9701182 needs to be approved by the DSS. -
Based on this independent review, pending acceptance of the Work Order by the DSS, there are no items involved wi th Restan Commitment #70 which would impede Unit 2 stan up.
4 2
L 1
a 4
I e
Rev. ewer:
k m,.., .i -
Page 2 of 2 2 - . . . - . - . _. _--
2 ACTION ITEM STATUS REPORT PAGE 1 03/31/97
~******************************* Responsible Person.
- Trk$d: U2R22 RESTART
- Urgency: DONE
- Action Number: 74
- Work Priority: 99 Activity Pending is: DONE ASSOCIATED WITH A COMMITMENT
TITLE AND TASK DESCRIPTION-----~------------------------------------
Unit 2 Refueling 22 Startup Commitments Prio to criticality ensure each operating crew receives simulator trai ing to galn proficiency in casualty response, the expected response of t e newlv installed steam generators and reactor core, and placing the turbine on-line.
Sourge Record:.........-DATES----
01/10 /97 ******* Evaluation ********* ****** Correction ** ***
Commitment: Eval Due: Corr Act Due: 02 13 97 Act$on Create: 01 14 97 Oriq Eval Due: Orig CA Due: 02 13 97 Action Closed: 03 31 97 Eval Done: Corr Act Done:03 24 97
PEOPLE--------------------------------------------------------------
Responsible for Overall Action: . TROPS Responsible for Current Pending Activity: l Issue Manager:
Initiator:
Punchlipc Administrator:
..___.....non4TE------------------------------------------
(01/16/97 Changed Responsible Person: From ' .) to ). Bob is j currently cenducting this t. ra i ni ng . l (01/22/97 his TWR bas $cally constists of training upon 5 seperate items: 1. Brin the turbine online (from POAH to about Reviewingthe$2SerencesbetweenU1andU2SGs3. 15%) 2differences Identifying between U1 and U2 response on a normal trip,4. Addressing difterences between U1 and U2, response to instrument failuress. Conducting casualty l response to dynamic scenarios.
All are these
~
itemsinare contained being"Unitaddressed LP2522, 2 Startup in LOR trainiSGg cycle training 97-1.
Review" andItems is being 1-4 conducted IAW the LOR cycle 97-1 training cycle, a of this date OPS statf personnel,he rec:eved t required training. Crew A licensed operators and Crew C licensed operators have Item 5 is being covered as a seperate item through the administration of casualty scenarios each week of the training cycle on each specific crew:
- Ops staff norsonnel participated in a casualy scenario (SES-43) on 1/9/97
- Crew C licensed personnel met the (see attached reguirements atpendence of this item b sheet)icipa Eart ting in 2 casualty scenarios (SES-009A and SES30) on1/1E/)7duringthe INPO simulator evaulation (See attach attendance sheet)
Crew A li ensed personnel met the requirements of this item by artuicipating In 2 casualty scenarios (SES-009A and SES-47) on 1 uring the INPosimulator evaluation (See attached attendence shee/14/97 t)
(01/29/97 ) As of this date Crew E has attended LP2522, thereb completing Items 1-4 of this TWR. (See Attached attendance sheet) y (02/03/97 ..-.) As of this date Crew E has now completed item 5 of this TWR by participating in practice caenalty scen cion ,on 1/30/97 (See E tached sheett As of this date Crews D and F have attended LP2522, thereby (02/12/97 .%.)ing items 1-4 of this TWR.
satisfy 02 M ) as of this date crew D and crew F have completed item 5 of
.t (his/17/97twr by paricipating in practice scenar4os on 2/12/97 and 2/13/97 (see attached sheets)Also Crew B has completed items 1-4 of this TWR by attending LP2522 on 2/17/97 (see attached sheet) t(02/25 rainin/97g to )complete As of this date all required Oos personnel have attended items 1-4 of this TWR, Also Crew D ha.s completed item
- 5 of this Tha by participating in practice dynamics on 2/20/97 (SES-47 and SES 30).,see attached sheet.
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TOPIC: CREW DYNAMIC (PRACTICE MODE) CYCLE 97-1
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POINT BEACil UNIT 2 COMMITMENT INDEPENDENT REVIEW RESULTS Commitment ID Number 74 1
Commitment Description I Each operating crew will receive simulator training to gain proficiency in casualty response, the expected response of the newly installed steam generators and reactor core, and placing the turbine ;
on-line. '
This simulator training will consist of; Bringing the turbine on-line (from the POAH to about 15% power). l Reviewing the difTerences in steam generator response between Units I and 2. !
Conducting normal trips and identifying the differences in response between Units I and 2. I Addressing instrument failure response differences between Units I and 2.
Conducting casualty response dynamic scenarios in the training mode.
Review Methodology Review the simulator lesson plans that are used to conduct this simulator training and verify the above objectives are specified.
Observe this simulator training, to the extent possible, to qualitatively assess the crew's level of proficiency and adaptation to any observable differences in plant response due to the new steam generators.
Verify each operating crew has either had this specific simulator training or is scheduled to have this training in the near future.
O Page i of 4
POINT BEACII UNIT 2 COMMITMENT INDEPENDENT REVIEW RESULTS Commitment ID Number 74 Review Results Verified that lesson plan LP 2522 Rev. O contains the objectives of review stated in commitment number 74 with the following exceptions:
- 1. Bringing the turbine on line was initiated from about 5% power, not the point of adding heat (POAH), Discussions with the responsible person relative to this starting point revealed that he believed that initiating the scenario from 5% or from the POAH had little impact on the major part of the exercise which was rolling the turbine and electrically bringing the generator on line. Subsequent to this discussion, this issue was resolved by additional discussions with the Restart Issues Coordinator. The NRC Commitment was to conduct simulator training as described in the first sentence of the commitment. The training scenarios used to complete this training was at the discretion of the PBNP staff.
Therefore the starting point of the turbine roll exercise is no longer an open issue.
- 2. The training that conducts casualty response to dynamic scenarios is carried out in the training mode by using various pre-selected requalification simulator drills without the use oflesson plans. This also doet not represent an open issue to this reviewer.
l l
Observed the simulator training sessions in the morning of 2/10/97. This training exercised
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6 Operating Procedure, OP-1C, %w Power Operation To Normal Power Operation" starting from l an initial condition of about 5% Reactor Power and ending with the Turbine Generator on line l producing about 40 Mwe. During the exercise, there were several points of discussion with training material handouts, which reviewed the differencer in response between Unit I and Unit 2 i in the areas of steam generator, reactor and instrumentation responses. After the Turbine Generator had been put on line, the simulator was reset to 100% normal plant conditions. Again in the training mode, a B Steam Generator Feedwater control valve was failed open and the crew took action to take manual control of flow, resclect away from the failed instrument and restore the control valve to automatic. Following this exercise, the operators were given a normal reactor trip to which they responded appropriately to stabilize the plant at hot shutdown without Safety injection or Auxiliary Feedwater initiating. ,
During this simulator session, the following observations were discussed which may warrant further discussion and follow-up action by the Operations staff.
- 1. During the turbine roll and bencrator on line exercise, there were only two operators on the console and three really active stations. Oc.. operator was in charge of the turbine and steam generator water level control (SGWL) while the other operator was in control of the reactor. During this e-itical evolution, it would seem more appropriate to have these stations split among three operators to minimize the distractions and provide more focused
, attention to these critical stations. Discussions with the Operations Manager, who was also observini; this training, indicated that real plant start ups do involve extra operators on the control board who are brought out on overtime.
(
Page 2 of 4
1 POINT BEACH UNIT 2 COMMITMENT INDEPENDENT REVIEW RESULTS g
i Commitment ID Number 74
- 2. De operator controlling the turbine and SGWL had to turn his back to the control board to find adequate level trends t~ tat would support his needs in controlling S/G water level. The CRT which hed these trends available on the vertical control board facing the operator had degraded to the point that it was too difficult to read. From discussions, the trending CRT in the vertical panel in the actual control room does provide adequate indication. While the operator appeared to handle the added burden of operating both stations (turbine and SGWL) and working around the degraded indications of vital parameters, there is some concern for the impact of training in a manner that is not consistent with the manning and equipment status that exists in the actual control room.
It is noted that subsequent to this observation, this reviewer became aware of Enforcement Conference Commitment Item No. 21. This commitment requires consideration for improvements to the Control Operator's Work Station that would permit the operators to face the main control boards and have optimum access to the controls.
Using the " Continuing Training Cycle / Initial Training Course Schedule" Rev. 3 dated 1/24/97, the reviewer was able to identify and verify the 6 crew composition. With ihe 'Trauung Attendance Reports", the reviewer was able to verify those individuals on the crews who have attended the training which pertained to the first 4 of 5 objectives in this commitment. He results of this .
l review indicate that 6 of the 6 crews have attended this : raining as of 2/17/97.
To verify the 5th objective of this commitment, the reviewer attended the casualty response dynamic training performed on 2/13/97. During this training session, two separate scenarios were conducted to provide refresher training in casualty response. The first scenario was brief and was j meant to time the operators' response from Auxiliary Feedwater Actuation to the time the !
operators had manual control of AFW flow within the prescribed limits of the procedure. During this 2/13/97 performance as well as the 2/12/97 performance which was also witnessed, the operating crews demorutrated very timely recognition of AFW actuation with AFW flow control established well within one minute from the time AFW ac:uated.
i The second scenario was performed in about 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and involved an unexpected reactor trip; reactor coolant pump seal failure; loss of one engineered safeguards electrical bus (' A' Train), and the subsequent failure of'A' train Safety Injection. He crew, which was somewhat short handed, demonstrated proficiency in recognizing the casualty symptoms and taking the proper actions to stabilize the plant and maintain core cooling in accordance with their procedures. By reviewing the f I
" Training Attendance Reports", the reviewer was able to confirm tht 6 of 6 crews have attended this training as of 2/20/97. It is noted that orm individual from 'B' Shift Crew missed this portion of the training due to personal reasons. This particular case is familiar to the Trammg Department and plans are in place to get this individual trained on this commitment.
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-~ ~. . . . ~ -. -. .- . - . . . . . -
POINT BEACH UNIT 2 COMMITMENT
- INDEPENDENT REVIEW RESULTS Commitment ID Number 74 Reconimendations L
While there are observations noted on the need to keep the operator positioned to control the plant and to maintain the fidelity between the simulator training and the actual practices in tiu: Control Room, these observations are for consideration by the PBNP staff and should not hinder satisfactory completion of this commitment. l
. .I
.This independent review is considered complete with one open item to be tracked to completion by ;
the PBNP staff. The open item is the one individual from 'B' Shift Crew that needs the casualty i response simulator training.
When closure of the open item is documented by the PBNP staff, Restart Commitment No. 74 will l be completely satisfied. In recognition of this open item, and based on this independent review of !
the completed work, there are no other items associated with Restart Commitment No. 74 which would impede Unit 2 Restart.
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POINT BEACH NUCLEAR PLANT UNIT 2 STARTUP COMMITMENT LIST March 27,1997 Status Update IDENTIFICATION AND RESOLUTION OF ISSUES PERTINENT TO REACTOR SAFETY The following actions will be taken prior to Unit 2 criticality, except as specifically noted. The scope of reviews will be examining the identified documents or items for accuracy and compliance with requirements. Should any reviews identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of those reviews will be expanded. Where discrepancies are identified, appmpriate corrective and preventive actions will be taken commensurate with tb6: safety significance.
Ccmmitment Description Status ID Number Complete a detailed Unit 2 Containment Materiel Condition Assessment, addressing housekeeping, in progress.
I system walkdowns, materiel condition, and instrumentation. Extensive work inside Containment was conducted this outage due to the Steam Generator replacement project.
2 Walkdown all accessible Unit 2 and common Maintenance Rule systems for adequate visual in progress.
material condition.
Walkdown di accessible Unit 2 and common systems for outstanding work order tags. All work and verification 3 Note: The scope was expanded to include all accessible Unit I systems. completed. Documentation sent to NRC.
Conduct as-built inspections of the electrical and I&C components on the Unit 2 CVCS and CCW All work and verification 4 systems (Work Orders 9607322,9611140,9606548, and 9611139). completed. Documentation sent to NRC.
Complete Work Orders 9513222 through 9513225 to conduct inspections of Appendix R alternate All work and verification
- 5 power transfer switches. completed. Documentation sent to NRC.
Complete Work Order 9604151 to perform foreign material exclusion inspections on the Unit 2 All work and verification 6 4160V safeguards bus 2A-06 and breakers. completed. Documentation sent to NRC.
Complete a review of Unit 2 administrative controls implementing or referencing Technical All work and verification 7 Specifications to ensure Technical Specification requirements are appropriately reflected in the completed. Documentation in administrative controls. route to NRC.
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Review 20% of the Operations Technical Specification, Inservice Test, and Operations Refueling In progress. Schedulcti Test reltted surveillance procedures, with concentration on those involving major equipment. completion date is April 25, 8 Upgrade as necessary to include appropriate initial conditions, return to service lineups, properly 1997, specified in Spendent verification, reviewing acceptance criteria, and Technical Specification implementauon.
Review the in Service Testing (IST) acceptance criteria for the remaining IST pumps to ensure that All work and verification 9 the IST ace ptance criteria meets the design basis / accident analysis requirements. Make any completed. Documentation changes necessary as a result of this review. sent to NRC.
Review the In Service Testing acceptance criteria for all IST valves to ensure that the IST All work and verification 10 acceptance criteria meets the design basis / accident analysis requirements. Complete necessary completed. Documentation operability evaluations, revise procedures, and resolve Unit 2 equipment discrepancies. sent to NRC.
Complete the following regarding installed inst.mmentation used in the IST program: All work and verification completed. Documentation
. Identify the Unit 2 installed instruments used in the IST program. sent to NRC.
. Review the performance of the identified instruments over the last 3 years.
I1 . Review the suitability of the instrumentation for use in the IST program.
. Review all IST pump hydraulic data over the past y ear for adverse trends.
As necessary, make changes as a result of these actions.
Review 20% of the surveillance procedures associated with safety significant non-pump and valve in closeout verification components (such as heat exchangers and fans) to ensure that the surveillance acceptance criteria process.
12 satisfy the requirements of the plant design basis / accident analysis. Make changes as necessary as a result of this review.
Note: This has been expandt d to a 100% review.
13 Review other operating procedures that contain maintenance activities and revise as necessary to In closecut verification ensure PMT and QC are properly addressed by those procedures. process.
Review equipment return to service testing requirements prior to the following U2R22 mode Will occur approximately one 14 change readiness reviews to ensure the required equipment is operable prior to changing modes: week prior to each of the core reload, leaving cold shutdown, and the approach to criticality. mode changes.
Review 20% of the work orders performed since January 1,1995 on Unit 2 or common PSA safety All work and verification 15 significant systems (AFW, SW, EDG, IA,4.16 kv, gas turbine, and CCW) to verify adequate PMT completed. Documentation in was performed to ensure system / component safety function. route to NRC.
Complete all Unit 2 Maintenance Rule related work order post-work, pre-PMT reviews prior to the All work and verification 16 approach to criticality. completed. Documentation in route to NRC.
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Review 50.59 screenings conducted in 1996. Upgrade those determined to require a 50.59 Review completed.
17 evaluation. Upgrading in progress.
Scheduled completion date is March 31,1997.
Review outh'tanding JCO's. Perform operability determinations and 50.59 evaluations needed to In progress. Scheduled 18 address the issues. completion date is May 5, 1997.
Conduct a review of 50.59 evaluations from this outage. Ensure all conditions of the evaluations Initial review completed.
have been completed. Reviews of emergent 50.59 19 evaluations in progress.
. Tracking completion of conditions through the outage.
Review items from existing open item lists (e.g., NUTRK) to identify potentially degraded In progress. Scheduled 20 equipment. completion date is April 4, 1997.
Review open items from the Design Basis Document development program. In progress. Scheduled 21 completion date is April 4, 1997.
All open operability evaluations for Unit 2 and common equipment will be reviewed for acceptable In progress. This will 22 closure of the degraded equipment issue. Disposition outstanding issues in accordance with continue through the outage.
10CFR50.59 and Generic Letter 91-18.
Review 20% of the Condition Reports closed since January 1,1995 which are associated with P3A In closecut verification safety significant systems for degraded equipment operability issues to ensure that we have process.
23 adequately identified and dispositioned operability issues.
This has bee'n expanded to a 100% review of PSA safety significant systems.
Complete an additional Outage Safety Review for the startup phase of the outage, in progress. Scheduled 24 e completion date is April 4, 1997.
Conduct an integrated review of ah outage licensing commitments (50.59's, enforcement In progress. Scheduled 25 conference items, Technical Specification Change Requests, and Reload Safety Analysis). Ensure completion date is April 4, all requirements are met. 1997.
Revise ORT-3 and DCS 3.1.11 to ensure Technical Specification 15.4.6.A.2 testing includes All work and verification 26 dynamic loading of the EDG with sequenced loads. completed. Documentation sent to NRC.
27 Test all EDGs in accordance with revised ORT-3 and DCS-3.1.11. Return the electrical systems to Re-opened. QA is reviewing normal aligmnent prior to leaving cold shutdown. the ORT-3 documentation.
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2 Resolve the containment penetration commitments, including: In progress. Scheduled 28 completion date is April 30,
. CP-32 (Containment penetration for Auxiliary Charging line). 1997.
. Penetration thermal reliefissue.
Complete a 50.59 evaluation for the existing CCW supply to the RCP seals as a safety function. Re-opened. Does not appear 29 that a 50.59 is an appropriate vehicle to do this.
Considering alternatives.
Update the diesel generator loading calculation N-91-016 to properly reflect the loading of the In progress. Scheduled 30 Containment Fan Coolers. completion date is April 1, 1997.
Evaluate the adequacy of coordination on the 120 VAC instrument bus system through a 50.59 or in progress. Scheduled 31 operability review. completion date is April 4, 1997.
Implement interim improvements for the Condition Reporting process, based on a review of in progress. Scheduled 32 assessments and identified recommendations for improving that process. completion date is Mar. 31, 1997.
Implement interim improvements for the 50.59 process to require that all screenings be either All work and verification 13 authored or reviewed by a member of the multi-disciplinary review team. completed. Documentation in route to NRC.
Upgrade Uliit 2 operations checklists to include requirements for initiais, time, and date. During Re-opened. Scheduled 34 the review, verify that the checklists are technically correct. completion date is April 25, 1997.
Revise applicable IST program documents to prevent equipment from beiag returned to service All work and verification 15 (declared operable) with vibrations in the alert range. completed. Documentation sent to NRC.
Revise NP 8.1.1, Work Order Processing, and NP 8.1.3, Post-Maintenance Testing to ensure post- Re-opened. Additional 36 maintenance testing , operability testing, and surveillance test requirements are properly addressed. revisions appear necessary.
Include return to service testing in the plant schedule, both outage and nonoutage. All work and verification 37 completed. Documentation in route to NRC.
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COMPLETE PHYSICAL WORK WHICH SUPPORTS SAFE STARTUP AND POWER OPERATIONS Modifications which Point Beach Nuclear Plant has identified as being significant to safetf and scheduled for completion in U2R22 will be in an accerted status (i.e., the applicable physical work completed, post-maintenance testing completed satisfactorily, and the associated component / system beinb declared operable) prior to being required to be operable per Technical Specifications. These modifications are:
Commitment Description Status ID Number 38 hiodification 96-033 - replace control power transformers on hiotor Control Centers 2B32 and in progress. One remains to 2B42. be installed.
hiodification 90-048 - replace Boric Acid and Reactor hiakeup Water totalizers, replace the Awaiting PMT. Scheduled 39 CVCS control switch, replace flow indicators, and refurbish flow controllers. This resolves an completion date is May 10, Operator workaround issue. 1997.
hiodification 94-097 - remove six RCS loop drain valves. Awaitir.g Ph1T. Scheduled 40 completion date is May 13, 1997.
hiodification 92-141 - relocate the RilR flow control valve controllers on 2CO3 for human All work and verification 41 factoring. completed. Documentation in route to NRC.
Modification 96-073 - seismically upgrade CCW, SI, RilR, and RHR/ letdown piping supports All work and verification 42 and remove an AFW snubber. completed. Documentaticn sent to NRC.
hiodification 94-066 - install a soft seat in containment isolation valve 2SI-834D, and add a in closeout verification 43 relief valve and pressure regulator in the nitrogen supply line to the SI accumulators. This process.
, resolves an Operator workaround issue.
44 Modification 96-065B - seismically upgrade the Refueling Water Storage Tank recirculation In closeout verification line. process.
Modification 96-054 - install pressure gauges in the service water return header from the On hold. Waiting for plant 45 Emergency Diesel Generator GOI and GO2 glycol coolers, and reset the throttle valves in that condition changes.
line.
Modification 96-022 - install a new 125 VDC feed to 480V safeguards bus 2B03. All work and verification 46 completed. Documentation sent to NRC.
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r-Modification 94-055 - add scismic supports to the raceway betwecn risers 56 and 62 on C04 All work and verification -
47 (Reactor and Primary Plant Control Board). completed. Documentation sent to NRC.
Modific " ion 96-068B - eliminate containment heating steam and condensate return In progress. Scheduled 48 containn'ent isolation valves. completion date is Mar. 28, 1997.
Modific nion 96-053 - replace an elbow in the west service water header. In progress. Scheduled i 49 completion date is Apr. 4, 1997.
50 Modification 95-070 - seismically upgrade the containment cooling fans and tilters. In closeout verification process.
Modification 96-026 - install, delete, and modify supports for feedwater, main steam, and SI All work and verification 51 system piping for the 79-14 project. completed. Documentation sent to NRC.
Modification 96-058 - move Power Plant Computer System alarms to the exterior of C-20 All work and verification 52 panels. completed. Documentation sent to NRC.
Modification 94-095 - replace 8 Main Steam Condenser steam dump valves with improved Awaiting PMT (PMT will be 53 design. completed following reactor stanup).
Modification 95-029 - replace SI accumulator level transmitters. Awaiting PMT. Scheduled 54 completion date is Apr.1, 1997.
55 Modification 95-035 - modify Containment Spray additive tank controller circuit. In closeout verification proccas.
Modification 96-063 - replace 345 KV breakers (3-4,4-5, and 142). Anaiting PMT (PMT will not 56 be completed until Unit 2 is on-line).
57 Modification 96-069 - replace four breakers (lY-06-01,1Y-06-03,1Y-06-05, and 1Y-06-11) In closeout verification associated with instrument bus 1 Y-06. process.
Modification 95-058'O - repair Steam Generator intermediate leg supports. This may be Awaiting PMT (will not be 58 resolved through analysis. completed until the unit is heated-up).
59 Modification 96-070 - replace molded case circuit breakers associated with instrument buses In closeout verification 2Y-05 and 2Y-06. process.
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The work and testing associated with these Work Orders will be completed prior to the associated component / system being declared operable.
Emergent Work Orders associated with Maintenance. Rule Risk Significant Systems which Point Beach Nuclear Plant defines as priority level I to 4 will be completed prior to Unit 2 criticality.
Commitment Description Status ID Number Work Grders 9601506,9602502,9603921,9611267,9611278, and 9611755 - replace In progress. Scheduled 60 proximity switches and targets with an improved design and overhaul the Fuel Transfer Cart to completion date is April 4, enhance control system operation. This resolves an Operator workaround issue. 1997.
Work orders 9613568 and 9613569 - provide bonnet pressure locking relief for the SI-857A Work complete. Determining 61 and SI-857B valves (interface valves between RilR and liigh Head SI) on Unit 2. additional PhtT. Scheduled completion date is April 11, 1997.
Work Order 9611757 - correct the leakage which leads to boric acid buildup in the cylinder Awaiting PhtT. Scheduled 62 blocks of"B" Charging Pump. completion date is htay 12, 1997.
Work order 9603532 - repair the handswitch for 2P-2A, the "A" Charging Pump. Awaiting PhiT. Scheduled 63 completion date is Niay 12, 1997.
Work Orders 9611624 through 9611626 - replace existing pneumatic turbine generator Work is scheduled. The 64 circuitry time delay relays with plug-in, electronic time delay relays. scheduled completion date is hlar. 31,1997.
Work O der 9606626 - reinstall switches on the Unit 2 Containment hatch third deor to allow All work and verification 65 monitoring of door status. completed. Documentation sent to NRC.
Work Order 9611052 - replace the 2P-10B switch. the "B" RIIR Pump control switch. All work and verification 66 completed. Documentation sent to NRC.
Work Orders 9611198 and 9611199 - repair the body-to-bonnet boric acid leak on CV-307 B Awaiting PhiL Scheduled 67 (lowside tap for "B" RCP #1 seal d/p) and CV-308B (lap seal d/p for "B" RCP). completion date is April 8, 1997.
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The following actions will Le completed to correct Operator workarounds prior to Unit 2 criticality, except as specifically noted:
Commitment Description Status ID Number Repair valve AR-3511 per Work Order 9513340. The Unit 2 priming air ejector is blank Awaiting Ph1T. Scheduled 68 flanged due to air in-leakage through the condenser air removal isolation valve, AR-3511. completion date is hiay 12, 1997.
Repair the drain valve for the heating steam moisture separator per Work Order 9613451. The Work is scheduled.
69 Unit 2 heating stear _1 moisture separator level has been difficult to maintain during normal Scheduled completion date is operations, and frequent alarms were received due to low level. This will be tested following hiay 12,1997.
Unit 2 startup.
Install a new level control system for the brine tank (T-118) per hiodification 92-008*Q. The All work and verification 70 tank overflows because t'ne installed automatic level control system is not effective, and there is completed. Documentation in no high level alarm for the tank. route to NRC.
Repair h1S-249, the Unit 2 steam line sample valve, per Work Order 9603128. The valve had a Awaiting PhiT. Scheduled
-71 packing leak which required steam header samplitig to be shifted to the B steam header. completion date is hiay 12, 1997.
Repair alarm switch 2LS-2511 per Work Order 9605711. The Unit 2 D htSR level was being Awaiting Ph1T. Scheduled 72 maintained low in the band due to level oscillations and a steam leak from the alarm switch. completion date is hiay 12, 1997.
Repair ' P116, the Unit 2 Boric Acid Recirculation Pump, per Work Order 9603130. It has a Work is scheduled.
73 significant seal leak. Scheduled completion date is May 12,1997.
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PERSONNEL AND LICENSING READINESS The following actions will be completed prior to Unit 2 criticality:
Commitment Description Status ID Number Each operating crew will receive simulator training to gain proticiency in casualty response, All work and verification 74 the expected response of the newly installed steam generators and reactor core, and placing the completed. Documentation in turbine on-line. route to NRC.
Revise the initial and requalification operator training plans to include a review of the Re-opened. Need to better 75 administrative procedures identified as significant to daily operation of the plant during each define the administrative two year operations training plan. controls.
Conduct roundtable discussions with all MSS \SS\DTA personnel regarding conservative In progress. Three people decisionmaking, Technical Specification interpretations, and lessons learned from recent remain to receive the training.
76 regulatory communications and perspectives. Review outlier Technical Specification Scheduled completion date is interpretations for interim applications. April 4,1997.
Compic*e the procedure changes and training associated with the new Technical Specification in progress. Scheduled 77 on ECCS regarding the new Containment Integrity Analysis. completion date is April 15, 1997.
Communicate specific expectations regarding AFW and EDG status control to Operators. In progress. Scheduled 78 completion date is April 11, 1997.
Restore a proceduralized capability to operate the Containment Spray Pumps in the , in progress. Scheduled 79 recirculation mode of the ECCS. completion date is Apr.1, 1997.
Obtain amenc'ments requested by Change Requests IP' and 189 related to Steam Generator in progress. Scheduled replacement; 192 related to Service Water operability, and 194 related to Low Temperature completion date is May 7, 80 Overpressurization limits. This will include resolution ofissues related to Control Room and 1997.
ofTsite dose evaluations for the analyzed events.
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a .. ,
Submit the following requests for license amendments resulting from the review of existing in progress. Scheduled Technical Specification interpretations: completion date is May 7, 1997.
. Revice the maximum acceptable power level when crossover steam dumps are inoperable (TS '5.3.4.E).
81 . - Revii.e requirements for offsite power lines availability to address adequacy (TS 15.3.7.A.I .a).
- Remove allowances in TS 15.3.1.A.I.a for single reactor coolant pump operation.
. Appropriately modify the minimum required boron concentration in the Refueling Water Storage Tanks.
Status Explanation:
j In closeout verification process - work and PMT, as applicable, have been reported as complete. The independent review by Duke Engineering is
! either in progress or issues from that review are being addressed.
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