ML20140G532
| ML20140G532 | |
| Person / Time | |
|---|---|
| Issue date: | 11/09/1977 |
| From: | Aycock M NRC |
| To: | Boyd R, Harold Denton, Mattson R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20140F372 | List:
|
| References | |
| FOIA-85-665 NUDOCS 8604020452 | |
| Download: ML20140G532 (15) | |
Text
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'o, UNITED STATES
, E ?),,
- 7, NUCLEAR REGULATORY COMMISSION
$7 u
o., %g c.'f WASHING TON. D. C. 20555 p
's HOV 0 3 1377
. MEMORANDUM FOR:
R. Boyd, Director, DPM H. Denton, Director, DSE R. Mattson, Director, DSS V.
Stello, Director, DOR FROM:
Michael B. Aycock, Secretary Technical Activities Steering Committee
SUBJECT:
PROCEDURES FOR SCHEDULE CHANGES AND REVISIONS TO TASK ACTION PLANS As promised at the last Steering Committee meeting, attached is a draft memorandum containing procedures for schedule changes and revisions to Task Action Plans for your review and comment. I encourage you to solicit corments from Task Managers within your divisions in conducting your review.
i Please provide any comments you have to me by COB Tuesday, November 15, 1977 h
f, s
Michae B. Aycock, Secretary Technical Activities Steering Committee
Enclosure:
As stated cc:
E. Case L. Crocker
[ Guibert 4=W. Minners D. Wigginton 4
B604020452 360114 PDR FOIA FIRESTDBS-665 PDR
b Draft M
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bf d MAyccck:mmt 1l-4-77 MEMORANDUM FOR:
R. Boyd, Director, DPM.
H. Denton, Director, DSE R. Mattson, Director, DSS V. Stello, Director, 00R FROM:
Edson G. Case, Acting Director, NRR
SUBJECT:
PROCEDURES AND RESPONSIBILITIES FOR SCHEDULING 0F GENERIC TECHNICAL ACTIVITIES AND REVISING TASK ACTION PLANS The statements of procedures and responsibilities provided in Enclosures 1 and ? should be utilized for all future actions related to scheduling of generic technical activities and revising Task Action Plans.
Edson G. Case, Acting Director, NRR e
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'53D'u((d ENCLOSURE 1 SCHEDULING PROCEDURES AND RESP 0MSIBILITIES FOR GENERIC TECHNICAL ACTIVITIES Development of New Schedules Followir.g approval of the Task Action Plan for each Category A* generic activity, the Task Manager, working with CMIPC, develops a detailed level "C" schedule for the generic review. After review and approval by the Lead Supervisor, the network is forwarded to the participating divisions in NRR for concurrence.
Following agreement by all partici-pating NRR organizations and discussions with outside organizations regarding their participation, the Task Manager prepares a memo to the Chairman of the Technical Activities Steering Committee from the Director of the Lead Division transmitting the schedule, indicating that the concurrence of the participating technical organizations has been achieved, and requesting approval. When the schedule is approved by the Technical Activities Steering Committee (TASC), the Task Manager apprises the other participants in the generic review (i.e., contractors, vendors, etc.) of the major milestones assumed for any submittals which are s
critical to the timely completion of the task.
Requests for Schedule Change After establishing a schedule, the Task Manager is responsible for maintaining or improving established target dates.
The Task Manauer must notify his manaaement immediatalv if it repears that a target date
- These procedures will be revised at a l ta er date to accommodate Category B and C generic activities.
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will slip by more than five workina days.
The vehicle for reporting slippages is the enclosed " Request for Schedule Change" form.
The Task Manager is to indicate the responsibility and reason (s) for the slip, the impact on the remainder of the schedule, and the potential for
. recovery of lost time. The Task Manager is to attach a copy of the
" Generic Issue Summary Report" computer printout for his or her project, on which the new estimated dates are to be entered next to the appropriate milestones. Any dates which are changed are considered to be estimates until approved by the Chairman, TASC.
Updating Generic Book fletworks As part of the monthly " turnaround" of the Generic Book, each Task Manager is resporjsible for updating both the Level "C" generic network and the " Generic Issue Summary Report" computer printout.
Each month OMIPC issues a specific, self-explanatory schedule for updating.
A target date (T) is the official schedule date for completion of a milestone approved by the Chairman, TASC. An estimated date (E) is the most recent estimate for completion of a milestone forecast by the Task Manager. An "E" date may be changed to a "T" date only after approval of a " Request for Schedule Change" by the Chairman, TASC.
Both the Level "C" generic networks and the " Generic Issue Summary Report" computer printout update sheets should be reviewed by the Lead Supervisor of the i
project before these update sheets are transmitted to OMIpC for incor-poration in the data base.
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Generic Issue Summary Reoort Level "C" milestone dates are entered into the computer by OMIPC following approval of each project schedule by the Technical Activities Steering Committee.
These detailed schedules are updated by 0MIPC upon receipt
. of approved " Requests for Schedule Change" and revised computer runs forwarded by Task Managers as part of the Generic Book update procedure.
On a monthly basis, each Task Manager is' provided with an updated version of his or her detailed project schedule in the form of the
" Generic Issue Summary Report" computer printout.
Each reviewer assigned to a generic review will receive a listing of the milestones they are responsible for completing via the weekly TACS reviewer level reporting system. Should a reviewer foresee that a milestone will not be completed on the approved target date, it is the reviewer't responsibility to inform the Task Manager of the anticipated deviation.
The Task Manager is the only person authorized to change a target date or an estimated date on a generic task schedule.
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TEST HATRIX HONTICELLO T-QUENCHER TEST Discharge Bay D SRV Mn RV.2-71-A (Quencher)=a Core Flow:.100%IO%
5 Discharge Bay:. C SRY No: RV 2-71-E fQucwcher Inittil Vessel Pressure:29,fB pst Discharge Bay:
E $RV Not Ry 2-71-G (iQuencher 1,
Reactor Water Level:
Time _ Closed Time _,
Initis1 Conditions Pipe Tim U OII"9 Test Pipe Temp, Pool Power Discharge Next Ih0"'S)
Test-Type Water Leg Tem level Time CVA Tm Number'(_1Q,_ Valve.
(2) _ M J X)(3)_
(sec)
(min:sec)
_Q'
__R.H.
Run Coments N
SVA A
CP,tNI.
70;80.80-85 5
>2
~
1.Shr(4) 501 SVA A
CP, Nill '
15
. 30:00 Jonin
., 502 CVA A
WP,fML 5
>2 lhr
~701' SVA A
CP,iWL 15 15:00 N/A Optional (6)
.702.
CVA,
A WP.NWL 5
>2 N/A 2hr(4)
~
001 5VA A
CP tML 15 (7)
N/A l
802 CVA
.A
- llP,in!L 5
>2 N/A 2hr(4)
~
901-SVA
~A CP,tnlL '
15 7)
N/A 902 CVA
.A HP,tull 10 S 7)
N/A l
903 CVA A
IIP,fML 10 5 7)
N/A 904 CVA A
IIP,frrll 10 5 7)
N/A 905 CVA A
ilP, tut 5
>2 N/A 2hr(4)
. b
'1001' SVA A
CP,lML 15 7)
Optional (e)
N/A i
1002.
CVA A
IIP,ilWL 10 7)
N/A 1
J003 CVA A
IIP,tHIL 10 7)
II/A i
._I 1004 CVA A
lip.HWL 10 (7)
N/A O.
1005 CVA A
IIP, R.R.
10 (7)
- i {d N/A
.1005; CVA-A flP, toll 5
(-)
>2 N/A 30 min p
.r t
,g,
'O Denotes optional test.
[1
))V
[
...e
Discharge Bay:
O SRV'Not RV 21716A (Quencher)
~
Core Flow:
1005 Initial Vessel Pressure: 985+jpsi Olscharge Bay:
C Sily No:
RV2-71-E(Quencher)
Reactor Water Level: 29'I l-*
Discharge Bay:,E SRV No: ~RV2-71-0(Quencher) initial Conditions Time. Closed Time Ti Test Pipe Temp, Pool Power' Discharge Pipe Next Test Type Water leg lemp Level Time CVA Cooling Test i
Number Q1 Valve (2)
_M
(%)(3).Jec)
(min sec) flyours)
Run Comments N/A 1101 SVA E
CP,fiUL 70-00 DD-85 15 47)
N/A 1102 CVA E
ilP,fML 10
(?),
N/A 1103 CVA E
IIP,tNL 10 (7)
FI/A 1104 CVA E
IIP,tillt 10 (7)
N/A 30 min 1105 CVA E
HP,HWL 5
Optional (9) 1201 SVA G
CP,fML 15 (7)
N/A N/A 1202 CVA G
llP,ilWL 10 (7) il/A l
1203 CVA G
llP,(IHL 10 (7) 1204 CVA G
llP,flWL 10 (7) fl/A N/A 30 min 1205 CVA G
llP,N'<ll 5
(7)
Optional (10
~1301" SVA A
CP,tML 15 (11)
>2 2hr(4) i
,1302 CVA ilP EWL 5
Optional (10',
l
~1401' SVA
'CP,lML 15 (11) 1402 CVA IIP,CWL 10-(11) 10 (11) l 1403 CVA IIP.Dil 1404 CVA IIP.EWL 10 (11) 4 I
,1405 CVA IIP EWL 5-
>2 2hr(4)
>2 2hr(4) Optional (14'.
5
~1501' SVA LY,i.'W1.
i
>2 2hr(4) l 1502 SVA LY,tNL 5
>2 2hr(4)
,1503_
SVA t.V,tml 5
.> 2 -
2hr(4) Optional (15:
~1601-SVA CP,tNL 5
>2 2hr(4)
)
1602 SVA CP,tillt 5
>2 2hr{4l 5
u 5
>2 2hrg4 i
_1604_
SVA e
I' 1701 IfVA E,A,G. CP,fML 70-80 65-70 15 (7) tt/A l
1702 ftVA E,A,G. IIP,tM.
70-80 65-70 10 (7)
N/A 1703 11VA E.4,G. I!P,t111L 70-80 65-70 10 (7)
N/A 1704 flVA E,A,G.
IIP,llWt.
70-80 65-70 10 (7) tt/A i-1705 I;yA E, A,'G. IIP,f ML.
70-80 65-70 2
(7)
>2 2hr(4) la Extended A CP.N1)L (12)
(9 (13) i D1midowl
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- ~ -
..1
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-. If0TES (1)' SVn = single valie. Actuation
. CVA a: Consec'u.tive..alv'a Actuatida
'.~[.
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(2). CP = Cool Pipe-
. WP.= Warm Pipe HP
- Hot Pipe..
. NWL = I!crmal Wate'r I.eg DTE= Elevated (tfansient)WaterLeg
'LV = Leaking SRV (3). In'itial power level to be chosen.by Test Cicrat. ions
~
-(4); lima required for pipe temperatu're sensor T}5 to return to within 5F.;cf t
initial temperature. '
~.
(5)
~
-a OPTIONAL EVA T'ST WITH WARM PIPE tdt?ERATURE
'(6)
E The objective of the 500'and 700 series test. runs is to permi.t predictfve
~
- evaluations of. peak S/RV discharge. line pressure before proceeding to the
?, SOOL series test run..in,which the,highe'st transtut-5/.RV discilargs.line.-
pressure is ' expected.to occur.
Perfomance of the 500 and.700 set.ies test runs will provide assur4nce that the Level 1 Criteria (as defined in the Test Procedure) will not be exceeded.
Tht' optional 700 series t'est run Will be performed if predictions from the 500 series test run indicate that the Level 2 Criteria will be exceeded in the 800 series test run.
~
(7)
Predetermi.ned velve closed time to be the minirmm time required to assure that the water leg has returned to nomal water level.
Evaluation of the predicted water leg transient is to be based on water leg transient data from prior test runs for valve "A".-
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'fl0TES TO. TABLE 5 (Continued).
(8)
OPTIOliAL CYA TEST.RUil5 FbR STATISTICAL SIGli!FICAtlCE The 1000 series test run will be performed pending the results of an evaluation of the 900 series test run for statistical significance.
The. criteria for performing the 1000 series. test.run is as follows:.
~
.A.
Calculates the mean (R) and standard deviation (c) 'of the peak wall pressure at one locatich.
Determine the t'ULTIPLIER on' the mean to reach.the 95-95 ccnfidence '
'B.
level deisgn load fro'm Figure 1.
C.
Apply this multiplier to the measured mean to determine the upper ~
bound of the tested pressure load.
D..If the upper-bound pressure load is les's than 15 psid','00 NOT perform the 1000 series test run.
~
E.
If the upper-bound nressure load is greater than 15 psid, tj perform the 1000 series test run; (9)
Optional Test' Runs with discharge into Bay E (SRV RV2-71G). The test data of discharge into Bay C shall be reviewed at test site by the monitoring teams of GE & NSP to determine the need of this test series.
(10)
OPTIONAL CVA TEST RUNS NITH WATER LEG OVERSHOOT A.
The 1300 test runswill be performed if, in pievious test runs, the transient water leg in the SRV discharge line was at least 5 feet above the nom 41 water leg height at any time greater than 2.5 seconds following closure of the SRV.
B.
The 1300 and 1400 series test runs will be performed if pre-test predictions, incorporating effects of observed maximum water leg height, indicate that Level 2 Criteria (as defined in the test procedure) will not be exceeded.
(11)
Predetermined valve closed time.to be th6 time at which the water leg reaches its. naximum height. Evaluation of the predicted water leg transient is to be based on data from prior test runs for valve "A".
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, NOTES.To IASLE.5.(Centinued)
' ',[, {,, '
..J-(12) Pool temperature, as ceasured by p} ant instrumentatiori, shalphe less. than (service. water te:rperature plus 10 F), but no cooler. than 50' F, o.r icwest pool temperature obtainable wfthin time acceptable by the plant management, and torus water level shall be between (-2) and (-4) inches (below fiWL).
J (13)
Extended SR'l bloudown to continue until any of the following criteria.
are eet:
(Do Not run FJiR.during.this test.or withio 30 minutes of valve closure).
A.
Average Temperature of T17,.T25 and T23 reaches 110*F.
B.
The predicted bulk 0001 temperature, based on initial temperature of T25, T43, T46,-T49, reaches,90*F, C.
Either one of tEo. plant pool ten;erature sen~ sors reaches 95'F.
D.
Torus water level. reachss +7,5 inches (above tii.'L).
(14).0PTICNAL LEAX,1!iG SRV TESTS
-A Three optional laating S/RV tests are to be perfor:r.ed if.5/RV 2-7L-A is determined to have started leaking after test 701 and if 3 leaking SRV tests have not been performed in conjunction with the preceeding test.
SRV 2-71-A will be determined to be leaking based on pipe temperature data B
evaluated by the on-site review teams.
(15)
OPTIONAL SVA TESTS The 1600 series test runs will be cerfor.med pending the results of an ev'aluation of SVA tests 2, 501, 801 and 901 for statistical significance-The criteria for performing the 1600 ser.ies. test runs is as follows:
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NOTESTOTASLE5(Continued)
~
(15)
(Continued)
A.
Calculate the reaan (i) and standard deviation (e) of the peak wall pressur.e at one location.
l B.
Determine the MULFIPLIER on the cean to reach the 95-95 confidence-level design load from Grach on 66uee /-
C.
Apply this' r::ultiplier to the ceasured c.ean to detemine the upper-bound of the tested pressure load.
D.
If the upper-bound pressure load is less than 9 psid, 00 tiOT perfom the 1600 se' ries test run.
E.
If the upper-bound pressure load is greater than 9 psid, 00-perform the 1600 series test run.
NOTE:
If perforr.ed as other Options, tests 701, 1001, 1301, and 1401 shall account for the 4 optional SVA tests and the 1600 test series shall not be run re-gardless of the results of the statistical evaluation.
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MONTICELLO T-QUENCHER TEST MATR TEST CONDITION N0. REQUIRED N0. OPTIONAL OPTION TRIGGER IF STATISTICALLY A9 JUSTED PEAK' WALL SINGLE VALVE ACTUATION, COLD PIPE, 4
4 PRESSURE EXCEEDS 9 psi NORMAL WATER LEVEL 0
4 AS PART OF CONSECUTIVE VALVE ACTUA-TION SERIES CONSECUTIVE VALVE ACTUATION, WARM PIPE, 1
1 IF EXTRAPOLATION OF WARM PIPE RESULTS NORMAL HATER LEVEL INDICATE H0T PIPE TEST WOULD EXCEED CRITERIA CONSECUTIVE VALVE ACTUATION, H0T PIPE, 5
5 IF STATISTICALLY ADJUSTED PEAK WALL NORMAL WATER LEVEL PRESSURE EXCEEDS 15 psi MULTIPLE VALVE ACTUATION, COLD PIPE, 1
0 NORMAL WATER LEVEL, BAYS C,D, & E CONSECUTIVE MULTIPLE VALVE ACTUATION, 4
0 HOT PIPE, NORMAL WATER LEVEL BAYS C.D, & E
.. -k:O '
CONSECUTIVE VALVE ACTUATION, H0T PIPE, 0
5 IF WATER LEVEL IS MORE THAN 5'6AB0VE ELEVATED WATER LEVEL NORMAL, 2 1/2 SEC AFTER CLOSURE SINGLE VALVE ACTUATION, LEAKING VALVE 0
3 IF VALVE LtAKS AND 3 PREVIOUS LEAKY VALVE TESTS HAVE NOT BEEN DONE SINGLE VALVE ACTUATION, COLD PIPE, NORMAL HATER LEVEL, ADJACENT BAY BAY C 1
0 BAY E 1
0 CONSECUTIVE VALVE ACTUATION, H0T PIPE, NORMAL WATER LEVEL, ADJACENT BAY BAY C 4
BAY E 4
SINGLE VALVE, EXTENDED BLOWDOWN 1
0 TOTALS 26 22
TABLE I SENSOR TYPES, NuttBER AND GENERAL LOCATION Number of Gauges / Number of Channels Total lorus Torus Torus Quencher SRV Vacuum Gauges /
Total Region Pool Support
& Support Piping Breaker Channels Penetrations (2)
Strain Gauges 117/37 64 96/16 2/2 8/8 Single 11/11 Rosette 47/141(1) 7/21 3/9 57/171 234 Accelerometers 7/7 Uni-Axial' 7/7 2/4 8
2/4 Bi-Axial 2/2 5/5 1/1 46/46 194 Pressure Sensors 34/34 4/4 2/2 6
2/2 Water Leg Probes 10/10 50 10/10 Temperature Sensors (Resistance Tempera-ture Detectors, RTD)
TOTAL 99/193 4/4 96/16 13/29 28/34 1/1 241/277 (3) 556 39/39 (4) 5/5 34/34 Other RTD (Not on PCit)
(1) 2 in Bay C/D, 3 in Bay C, 2 in Bay A, all others in Bay D (2) No. of Penetrations through manway cover and drain flange on torus (3) Total number of gauges / channels connected to PCM recording system (4) Total number of-gauges / channels connected to DS-83 Scan recorder
TANDARD DIST. OF INCOMING TOP
.L GENERIC LETTERS C TOPICAL RF TTS ON MARK I CONTAINMENT v.s. NuctsAn F.stutAroRY co=Miss12N dCWRTP'UWW80GA pccM,196 k
Epicat i
NRC DICTRIBUTION PoR PART 50 DOCKET MATERI AL 3:
FROM:
cart or occuusNT General Electric Company 11/4/77 Mr. Victor Stello, Jr.
San Jose, California o4Ts Racanvao L. J. Sobon 11/8/77 T,zyra n CNoTomtZso PROP lNPur PoRM NUMBER op COPIES REcEtVEo 21! RIGINAL ghNCLAgglPtEo CcoPy i st( 4%
ISCRIPTioN ENCLoSu ma i
Consists of response to NRC request concerning Mark I Contairunent Program in-plant safety /
relief valve discharge load test with a T-Quencher.....
RJL 11/8/77 (1-P)
(19-P) l 46WL /CScus.QeMoud l FOR ACTION /lNFORMATION
/
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! CENTRAL FILES f2)
I 8NRC PDR INSIC l
iTIC I
!I & C (7) i TACRS (16) l INTERNAL DISTRIBUTION l
IL. SRA0 (4) i I
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iG. LAINAS (4) i I i
i IJ. P. KNIGHT f2) l I
I i
! BUTLER (4)
I l l
ISTOLZ l
l 6 DAVIS' I
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tLEAR I
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l iREID 1
I iMOORE l
IVASSALLO I
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i IGOLLER l
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lSCHRODER I
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lTEDESCO i I
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iSTELLO l
t iEISEJHUT l
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l I SCHTr.NCER i
ISIHWEIL I
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i IJ. GUIBERT (2) l i
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Ii EXTERNAL DISTRIBUTICN CONTR OL NUMBER t
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i 77?l201.L2 l
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