ML20030B387
| ML20030B387 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 06/22/1981 |
| From: | Martin T NRC |
| To: | Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML20030B385 | List: |
| References | |
| FOIA-80-562 NUDOCS 8108140499 | |
| Download: ML20030B387 (34) | |
Text
l}// %. UkV hippt ms.-}e )y Atw.
-q. -Q ljy ;&/ n y a v
(/,.He//o
- v a
l_,Q;&hi-4/c i.ip ?;7 g
NRC SEQUENCE OF EVENTS MW [ $((p" INDIAN POINT 2 WATER LEAKAGE INTO CONTAINMEl.T WEDt!ESDAY OCTOBER 1,1980 l
0 PLANT STATUS: Reactor at 100% power Tavg at 546 F, Soron Ref. 1,2 Concentration at 185 PPM. Turbine Generator at 0
820 Kie, Vapor Containment at 108 F with 0.1 psig.
Vapor Containment (V.C.) entered while at 100%
Ref. 14,23, power to repair leaks on Fan Cooler Unit (F.C.U.)
37
- 25.
These repairs were pecepted by a desire to reduce the measured inleakage to the WastaHoldup Tank (W.H.U.T.)
FRIDAY OCTOBER 3, 1980 0
PLANT STATUS:
Reactor at 100% power, Tavg at 548 F, Boron Ref. 1,2 concentration at 180 PPM, Turbine Generator at 0
820 FNe, Vapor Containment at 111 F with 0.4 psig.
V.C. entered wh'le at power to repair leaks Ref. 23,35, on F.C.U.
- 21.
During entry, the floats,
37 associated with at least one V.C. sump pump controller and both V.C. sump level indication systems were lifted by hand to check their freedom of operations.
No apparent problems noted.
Subsequent measured inlaakage to the W.H.U.T.
Ref. 14,37 showed a noted reduction.
The v.C. sump level indication system now showad a water level be-tween the 45 inch and 91 inch level switches, on one instrument stalk, and between the 51 inch and 97 inch lovel switch on the other stalk.
All F.C.U.
weir levels indicated below 4 inches.
TUESDAY, OCTOBER 14, 1980 PLANT STATUS:
Reactor at 100% power, Tavg at 549 F. Boron Ref. 1,2 concentration at 145 PPM, Turbine Generator at 0
830 MWe, Vapor Containment at 111 F with 0 psig.
High weir level slann received on F.C.U. #22, read-Ref. 14,24 ing about 7 inches.
Licensee evaluated this alarm 37 and declared the alarm channel inoperable. This response action was based on no observed increase in V.C. radiation, particulate, dew point or sump level detector readings; no observed increase in calculated W.H.U.T. inleakage or reactor coolant system outleakage; and, no observed change in #22 weir level indication when ooerators closed the Ser-vice Water supply and return' lines to F.C.U.
- 22.
8108140499 810622 PDR FOIA CHRISTI80-562 PDR J
e
F1 56 THURSDAY, OCTOBER 16, 1980 PLANT STATUS:
Reactor at 100% power, Tavg at 549 F Baron Ref. 1,2 0
concentration at 160 PPM, Turbine Generator load at 830 MWe Vapor Containment Tempera-s 0
ture at 113 F. Containment Pressure at 0.2 psig, Primary system leak rate at 0.4.GPM, and W.H.U.T. inleakage during past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 2.3 GPM.
0940 Started #22 Containment Spray pump far PTM-19.
Ref. 1 1008 Secured #22 Containment Spray pump.
PTM-19 Ref. 1,2 acceptance criteria met.
1645 Notified by consultants, Woodward & Clyde, that Ref. 1,2, there was a possible earth:s ke at 1302 hourt 12 a
on 10-15-B0, in the vicinity of the Croton Reservoir.
The event was too small to determine the exact location or to register a number on their scale.
However, motion was detected by some of their instruments and no blasting was known to have occurred in that area at that time (the Croton Reservoir is about 12 miles from Indian Point at its nearest point.)
Notified required personnel and agencies.
1705 Completed check of Control Room and plant for Ref. 1.2 evidence of damage to equipnent and struc-tures; none found.
l 1707 Notified by Unit #3 that no motion'was detec-Ref. 1,35 ted by their seismic recorders.
1708 Notified NRC via hot line of potential earth-Ref. 1 quake report, response actions and results.
1733 Notified NRC Resident Inspector of potential Ref. 1 earthquake report, response actions and results.
l e
.9
Lt FRIDAY, OCTOBER 17, 1980 PLANT STATUS:
Reactor at 100% power, Tavg at 549 F, Turbine Ref. 1,2 0
Generator load at S20 MWe, Boron Concentration at 130 PPM.
Approx.
Received high alarm on NL lear Instrument Power Ref. 3 0030 Range Channel N42-Axial Flux Offset.
0030 Noted nightly heat balance readings appeared abnormal.
Ref. 2.11, Performed quadrant power tilt calculations. Tilt in-12,37.
dicated 1.02 upper and 1.03 lower.
Requested I&C to 41 check drawers.
Channel Nc2 indicated high positive axial flux tilt.
Suspected bad power range channel.
Quadrant tilt calculations performed on 1/2 hour basis; decreasing load to try to correct flux tilt before Tech Spec time limit reached.
Approx.
Reduced load from 100 percent due to Nuclear Instrument Ref, 1,34, 0100 System problems.
41 Anprox. 0145 Informed chief Operations Engineer.
Ref. 37 Approx.
Reactor Engineer requested to come to plant by the Ref. 50 0200 Senior Watch supervisor (5.W.S.). Was informed bottom detector on Nuclear Instrument Channel N42 was reading less than expected.
0200+
Performed monthly check on channel N42; all electronic Ref. 2,50 circuits 0.K.
0210+
load reduced to about 90 percent.
Ref. 1,34,E:
Approx.
Reactor Engineer arrived onsite.
Ref. 50 0300 App rox.
Performed incore flux map.
Ref. 2,19, 0325 50 0355 Determined flux distribution was normal and instrument Ref. 1,11, channel was failed.
Nuclear Instrument Power Range 12,34, Channel N42 declared inoperable.
50 S.W.S. requested the Chief Operations Engineer get Ref. 37 permission to operate above 70 percent power with one Power Range Nuclear Instrument Channel inoperable, as is required by licensee procedures.
l l
l e
P
/,,
i 7
FRIDAY, OCTOBER 17, 1980 (continued) 0400 Removed control power fuses from Channel N42.
Ref. 1,3,2, This caused a rapid indicated power decrease in the 11,12 N42 core quadrant, resulting in a rod drop alam and turbine runback actuation (due to rod drop pro, tection circuitry.)
Experienced Turbine Runback from 700 We to 500 We.
Plant Manager gave pemission to operate up to Ref. 34 100 percent power with one Power Range Nuclear Instr" ment Channel out of service.
0408 Axial flux offset alann.
Ref. 3 0415 High Tavg alann Ref. 3 0418 Tavg increased with lower steam demand and control Ref. 1,2,3, rods in manual.
Decided movement of control rods 11,12, undesi rable.
Dispatched operators to local turbine 37,41 generator controls.
Operator turned the load limitar in the. wrong dire-tion, driving the turbine generator load from 500 MWe to about 100 We.
Experienced a Reactor Trip from 70% powr.
First out annunciator indicated trip from Lolo Stm. Gen. Level #23.
Computer sequence of events log indicated Reactor trip due to High Pressurizer Pressure.
Plant Manager agreed with Chief Operations Engineer Ref. 34,37 to start up plant with only three power range nuclear instrument channels operable.
Decision to promptly return to power possibly tempered by the knowledge that xenon buildup would prevent return to criticality if actions delayed, due to minimal excess reactivity left in core.
0435 Licensee called NRC on " Hot Line."
IE:HQ log indicated Ref. 1.2.5 trip from 60% power caused by failure of power range channel #42; failure caused turbine runback and steam generator level oscillation causing reactor trip; all systems operated as expected; and plant nay go back to power with channel tripped.
Review of IE:HQ tapes indicated plant further reported no safety infection or radioactivity release occurred.
Approx.
0451 Completed critical rod estimate. Reactor Trip breakers Ref. 2,3 shut.
0540 Began pulling rods to go critical Ref. 1 0600 Reactor Critical Ref. 1.E
I 3
FRIbAY, OCTOBER 17, 1980 (continued)
Holding approximately 3% power, diluting to Ref. 2,37 compensate for xenon buildup.
Approx.
Director Technical Engineering called NRC Resident Ref. 36,65 0800 Inspector and discussed first Reactor trip.
Approx.
I&C department working on power range nuclear 0847 instrumentation.
Checks of Channel N42 show sluggish msponse.
Technician decided to do a comparison check.
Took all of Channel N42 trips out of the circuit with the exception of Overpower Delta "T" and Overtemperature Del ta "T".
Technician attempted msponse check on Channel N41 for comparison, re-ceiving second Overpower Delta "T" trip.
Reactor tripped on Overpower Delta "T" (2 out of 4 logic).
Prepared estimated critical position (Bank D at 145 Ref. 2 steps).
Plant Manager agreed with Chief Operations Engineer Ref. 34 to start up plant.
Approx.
I&C Engineer learned of grounded nuclear insttwent Ref. 40,59 0900 detector on Channel N42.
Detector signal cable center conductor to gret.nd and center conductor to shield conductor resistances both mad about 2000 Ohms.
0902 Reactor Trip breakers shut.
Ref. 3 Pulling rods to go critical Ref. 2 Approx.
Licensee called NRC on " Hot Line."
IE:HQ log Ref. 1,5 0920 indicated trip from 3% power at 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br />; technicians repairing power range Channel N42 were careless in cabinet; tripped on Overtemperature Delta "T" Channel 42; and, returning to power.
Review of IE:HQ tapes indicated plant further reported to be in hot shutdown; expecting to go critical within next hour; and, no safety injection or radioactivity release occurred.
Approx.
Technical Engineering Director discussed first Reactor Ref. 65 0930 trip with NRC Resident Inspector.
Plant Manager decided to take the plant to hot shutdown.
Ref. 34,36, to replace failed nuclear instrument detector.
De-37,44 cisica to shutdown was influenced by requirement to conduct daily flux maps, with one nuclear channel inoperable. and concern for wear on the incore instru-ment system, during the conduct of these procedures.
I a
4 FRIDAY, OCTOBER 17, 1980 (continued) 0950 Reactor critical Ref. 1,2 0950+
Operators directed,to shutdown Reactor Ref. 37 1010 Reactor Suberitical - Shutdown banks still out Raf. 1,2 1015 Shut Main Steam Isolation Valves (M.S.I.Vs) to Ref. 1,10, reduce cooldown rate.
Broke condenser vacuum.
36,5 0 One M.S.I.V. did not close fully. Operator able to close manually.
Approx.
Preparations begun to enter V.C. for Channel N42 Ref. 52 1030 detector replacement.
- Approx, Plans for V.C. entry were to pull detector in Ref. 39,57, 1145 line from elevation 46 feet and replace detector 110 from refueling cavity.
If elevation 95 feet lights were found off, plans were to exit and reg roup.
1200 V.C. entry.
Eight personnel (S I&C Tehncicians Ref 4.39,4:
and 3 Health Physicists) entered.
Five individuals 44,57,.
go to elevation 95 feet and find lights out.
Three individuals 90 to elevation 68 feet and then elevation 46 feet.
On elevation 68 feet, water was seen on floor around F.C.U. #22.
On elevation 46 feet, noted water coming from ceiling under F.C.U.
- 22 and from F.C.U. #22 weir.
Floor of elevation 46 feet was noted to have about 4 inches of water covering it.
1205 Crew out of V.C.
Report made to control room and Ref. 4,32,3c Manager, Nuclear Power Generation of observations.
37,38,:
44,57..
Operators verified isolation valves open on V.C.
Ref. 32,37 sump pump discharge line to the W.H.U.T.
Approx.
Isolated Service Water supply and return to #22 Re f. 1,2,4 1230 Fan Cooler Unit (F.C.U.) due to Service Water leak.
1320 Crew back in V.C. for second attempt to install Ref. 4.39,5?
Detector N42.
Planned to use flashlights on elevation 57,110 96 feet and rubber boots on elevation 46 feet.
e
I
,d
~
5 FRIDAY, OCTOBER 17, 1980 (continued) 1335 An S.W.S. Trainee, a Senior Reactor Operator, entered Ref. 32,35, the V.C. to investigate the water on the floor.
Both 110 V.C. sump pumps were found stopped and F.C.U. #22 was found to have a Service Water Leak.
Manual actua-tion of both V.C. Sump Pump floats caused one pump to start.
Replacement of fuses and possible resetting of the thermal overloads started the second V.C. Sump Pump.
Approx.
On elevation 95 feet, crew noted high temperature and Ref. 39,40,-
1345 humidity in refueling cavity and steam-like vapor exiting from 52,53,:
holes in the detector well covers.
A water film covered 59 the electrical conductors in the hole.
On elevation 46 feet, noted 4 F.C.U. weirs overflowing, including #22 F.C.U. weir at a reduced rate.
A lot of water was still dripping from the elevation 46 feet overhead, under F.C.U. #22.
1405 S.W.S. Trainee exited V.C. to obtain tools to inspect the Ref. 32,48, leak on F.C.U. #22 Service Wate r return line.
V.C, Sump 110 Pump #210 had been found with two blown fuses and V.C.
Sump Pump #29 had malfunctioned due to a cocked float assembly.
1430 S.W.S. Trainee returned to V.C. and removed the insula-Ref. 32,11C tien from F.C.U. #22 Service Water return line.
Hole found in 10 inch pipe at weld in position which could not be directly observed.
The Trainee exited the V.C.
20 ninutes later and informed the Control Room of his findings.
Approx.
Plant Superintendent notified by the I&C Engineer of Ref. 40 1430 inability to replace Channel N42 detector due to hot-humid vapor issuing from detector well.
Discussions with licensee management indicated no Ref. 33,34,:
manager believed there existed a requirement to 36,37,;
notify NRC of the Service Water leakage collected 48,50 on the V.C. floor; nor could anyone even recall a discussion of the potential need to make such a report.
1522 Licensee attempted to contact the Senior Resident Ref. 36 Inspector.
Left message on answering machine request-ing a return call.
No reason for the call was recorded.
Licensee reportedly intended to inform Resident of the M.S.I.V. closure failure and the discovery of a couple of inches of Service Water on the V.C. floor.
V.P.-Power Generation notified of water found on V.C.
Ref. 33 floor.
p 6
FRIDNY, OCTOBER 17, 1980 (continued)
The Technical Engineering Director questioned whether Ref. 50 water may have flowed into the Reactor Vessel pit, but was reminded that the pit had a 6 inch curb on the elevation 45 foot floor, that would prevent the 2 to 4 inches of water reported on the floor from entering the pit.
Approx.
Maintenance made V.C entry to repair F.C.U. #22 using Ref. 39,110
~
1600 a rubber backed stainless steel sleeve clamp for the 10 inch service water outlet line leak.
Licensee planned to return to power before 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> Ref. 26 with three operable power range nuclear instruments.
Operators directed to keep on top of V.C. sump pumping rate.
Approx.
S.W.S. Trainee entered V.C. to verify no water had Ref 37,48, 1800 gotten into Reactor Vessel Pit.
Found water in Pit 110 about 4 feet below locked grating on elevation 45 fee t.
(This is first reported evidence of water in the Reactor Vessel Pit).
The trainee checked the lights for the Reactor Vessel Pit Sump Pumps and believed one was lit and one was out.
He further observed an acceptable leak repair test of F.C.U.
- 22, noted water leak from near F.C.U. #23, and left after an hour.
Approx.
Plant Manager infonned by the Chief Operations Engineer Ref. 34 1900 that the Reactor Vessel Pit was flooded, that leaks on the F.C.U.'s were being repaired, and that the V.C. Sump Pumps were pumping the water out.
Approx.
Cleared pemit and started F.C.U. #22 Ref. 1,4 1945 Approx.
Tagged out F.C.U. #23 Re f._ 1,4 1947 l
Approx.
Licensee gathered equipment to install and operate Ref. 32.46 C:
1 2045 portable submersible pumps.
A Reactor Operator Trainee 110 l
entered the V.C. to detennine if the Reactor Vessel Pit Sump Pumps were running.
Found pump with the moisture detector alam lit (falsely believed to indicate pump I
running) to have power downstream of the line fuses.
l Trainee hung two strings with weights attached; one touched water surface and one extended several feet below the water level. Trainee reported the Reactor Ves'sel Pit water level had drcpped 4 inches during his
(
entry. This convinced the Trainee that the Reactor Vessel Pit Sump Pumps were pumping.
Approx.
V.C. sump isolated.
Waste Hold Up Tank (WHUT) being Ref. 4 2240 transferred to Unit 1.
l 1
o
I SATURDAY, OCTOBER 18 1980 PLANT STATUS:
Reactor suberitical in a hot shutdown mode Ref. 1,2 awaiting return to power.
Vapor Containment closed.
The water in the W.H.U.T. being transforred to Unit Approx.
Opened V.C. airlock for entry team (4 indivi-Ref. 4,47 0030 duals) to set up portable submersible pump.
58,1.
Team reported puddles on elevation 46 and water level from three inches to three feet below elevation 46 foot grate to tho Reactor Vessel Pip.
Team exited to get a key for the lock on thu grate.
F.C.U.
- 22 found to have another leak.
Approx.
Team entered V.C.,
unlocked the Reactor Vessel Ref.
2,J.
0100 Pit grate, 'nstalled portable air driven sub-46,F mersible pump on tho Rcactor Vessel Pit Inter-mediate Landing and ce=menced pumping the Reactor Vessel Pit to the V.C. Sump.
A V.C.
Sump Pump float was observed to be caught again and had to bo freed to start the pump.
Approx.
Ono team member reported seeing steam in Ref. 43, 0130 vicinity of Steam Generator (S/G) #21 on V.C.
elevation 68 feet.
Another team member tried to start a Reactor vessel Pit' Sump Pump by replacing blown fuses; but each time the fuses were replaced, they blew within 3 seconds of closing the electrical disconnect.
Approx.
Maintenance working on F.C.U. 423 motor Bef. 54 0130 cooler luak.
0135 Opened V.C.
sump isolation valves to the Ref. 4 W.H.U.T.
W.H.U.T.
level at 44% when valves were opened.
W.H.U.T. being transferred to Unit 1.
Approx.
Avera90 of Dew Point temperatures jumped Ref. 9 o
0200 from a normal average of 71 F to about 0
74 F and then Slowly decreased.
Approx.
Reactor Vessel Fit Sump Water Level WdS Ref. 37, 0200 reported to be dropping as the portable sumbersible pump discharged to the V.C.
Sump.
^
s&
F SATURDAY, OCTOBER 18, 1980 2
Air operated portable submersible pump may Ref. 37,i have failed.
Approx.
Reactor Vensel Pit Water Level reported to Ref. 46 0330 have dropped slightly from previous mark, but apparent rate of drop was significantly less than previous observation.
Approx.
Avorago of Dew Point temperatures had de<2ayed Ref. 9 0
0340 to about 72 F, but now turned and climbed to 0
about 86 F, over a period of about one hour.
Approx.
Average of Dew Point temperaturns had peaked Ref. 9 O
0445 atiabout 8G P and started rapid decrease to 0
about 76 F, over next 45 minutes.
Approx.
Average of Dew Point temperatures bottomed at Ref. 9 0530 about 76or and now started less rapid rise to abou't 840F, over a period of two hours.
Approx.
V.C.
entry party noted peactor vessel Pit Ref. 41 0530 water level decreasing.
Reactor Operator Trainee instructed to com-Ref. 46 pure estimated critical position for'0900 riours on 10/18/80.
Approx.
Average of Dew Point temperature peaked at Ref. 9 0730 about 84 F and then began slow decrease to 0
about 77 F, over a period of about one and one half hours.
0730+
Repaired V.C.
sump floats, which had become Ref. 4,34 cocked and stuck again, and inspected the 80,1.
Reactor Vessel pit.
(water level 13 ladder rungs down, elev. 34 feet).
Approx.
Average of Dew point temperDatures jumped Ref. 9 0900 from about 770F to about 82 F, where it re-mained for about three and one half hours.
e
I SATURDAY, OCTOBER 18, 1980 3
1227 S.W.S. toured containmen t and noted Water Ruf. 37, level in Reactor vessel Pit just above the 110 portable sump pump on the intermediate level.
The portable pump was pumping.
Found leak on #21 5/G blowdown line and #25 F.C.U.
S.W.S.
uAited the V.C.
at about 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />.
Approx.
Average of Dew Point temperatures jumped to Ref. 9 0
1240 about 86 F, where it remained for about one
'and one half hours.
Approx.
423 F.C.U.
in service.
Ref 4
1300 1350+
(LATE LOG ENTRY) (1). V.C. Entry, (2) #25 Ref. 2,4 F.C.U.
Service Water leak (secured), (3) 23 Poscible leak on #21 F.C.U.
(4) Estimate Reactor Vessel Pit level about 15th rung from elevation 46 feet.
1400+
(LATE LOG ENTRY)
W.H.U,T.
leve'l increased Bef. 4 from 23% to 33%; still transferring water to Unit 1.
Approx.
Average of Dew Point temperaturos bngan decay Ref. 9 1420 from about 860F to about 760F, where it re-mained till about 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on Sunday, 10/
19/80.
Approx.
Completed repairs to motor cooler of #23 Ref. 1,4, 1435 F. C. TT.
Started #23 F.C.U.
for test.
Approx.
V.P.
- POWor Generation notified of dis-Ref. 34 1500 covery of S/G blowdown line Icak and plans for repair.
Approx.
Two Nuclear Plant Operators (N.P.O. 's) entered Ref. 55,'
1715 v.C.
Reactor Vessel Pit portable sump pump discharging to containment sump two to three inches of water on elevation 46 feet floar,
(
inside ring wall.
Located S/G blowdown line lenk and noted staall amount of steam from leak.
Iso?.ated S/G blowdown line.
Located small leaks on (21 and #22 F.C.U.
e 4
--9
l.'
SATURDAY, OCTOBF,R 18, 1980 4
Approx.
Nuclear Side (N.P.O.) entered V.C.
Verified Ref. 4 1930 Pressure Relief Tank drain to V.C. sump shut and Reactor Coolant Drain Tank drain to V.C.
sump open per normal line up.
Approx.
Nuclear Side N.P.O. entered V.C.
to show main-Ref. 4,34, -
2100 tenance #21 S/C blowdown lino leak and to 82,11.
check on the portable sump pump on the inter-mediate level.
Putnp was in a few inches of water and probably not moving any water.
e O
e 34_.--
Q
m SUNDAY, OCTOBER 19, 1980 FT. ANT STATUS:
Reactor subcritical in hot shutdown mode Ref. 1,2 awaiting return to power.
The vapor Contain-ment was closed but unlocked with prossure relieving in progress.
Tho water in the W.II.U.T. Was being transferred to Unic 1.
Approx.
Air operated pump lowered to about 5 feet Ref. 2,41 0100 below intermediate landing of Reactor Vessel 43,80 Pit.
Water level just abova intermediate 110 landing.
Elevation 46 feet floor reportedly dry with some puddles.
0250 Commenced work on F.C.U.
921 cooler leak.
Ref.
2,/.
0400
$ carted F.C.U.
625 for test following leak Ref. 1,1C repairs.
s Acyrox.
Opened inlet valve to F.C.U.
- 21 Ref. 3,4 0535 Approx.
V.C.
entry made to repair portable sub-Ref. 41,:
0600 mersible pump in Vessel Pit, which had 100 stopped.
Water level at intermediato larding 9 rating.
Could not fix pump.
Lubricator had run out of oil and pump had siezed.
0625 Started F.C.U.
- 21.
Ref. 1 Repairs completed to V.C.
Sump Pu:r.p float Ref. 2 operated controllers.
0917 S.W.S.
toured V.C.:
W.H.U.T.
and V.C. Sump Ref. 2, '8.'.
full.
One to two inches of water en floor llo of elev.
46'.
Found float on V.C.
sump pump's controller loose.
Reactor Vessel Pit icvol awash at intermediate landing.
No evidence that installed Reactor Vessel Pit permanent sump pumps are working.
Left 7.C.
at 1003 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.816415e-4 months <br />.
Approx.
itepaired float ball for V.C.
sump pump con-Ref. 63 0930 troller.
a
'o' SUNDAY, OCTOBER 19, 1980 2
Approi.
S.W.S.
and Chief Operations Engineer decided Ref. 81,37 1030 to drill hole in neactor vessel Pit sump Pump's discharge line to preclude siphoning V.C.
Sump to Reactor vessel Pit.
Approx.
Nuclear side N.P.O. modo V.C.
ontry to put.
Ref. 2,4, 1230 new portable submersible pump in the Reactor 80 Vessel Pit, railed portable pump removed and one hunr3 about 5 feet below intermediate landing.
1300 F.C.U.
425 secured for maintenance.
Ref. 1,2 1430 Orilled hole in Reactor Vessel Pit sump Ref. 63,11 pump discharge line.
Noted no water came out, implying pamps not running.
T.icensee planned startup once the Reactor Ref. 37,41 Vossel Pit water level dropped below all incore instrument conduits.
Approx.
Meggered the 2 reactor cavity sump pumps:
Ref. 2,63 1700 No. 1 grounded, overload trippod and breaker tripped; No.
1, one phase grounded, over-load tripped, and closing coil shot.
v.c.
Sump Pumps in auto with floats operable.
Approx.
V.C.
entry to install second portable sub-Ref. 56,17 1915 mersible pump in Reactor Vessel Pit.
First pump was discharging water to the V.C.
sump.
Water level in the Reactor Vessel Pit was about 4 feet belCW the intermediate landing.
Approx.
Completed repairs on F.C.U.
425 leak.
Ref. 4 1925 2000 Nuclear side N.P.O. entered V.C.
to do Ref. 4,110 additional work on F.C.U.
422 normal outlet valve indication.
Approx.
Water in Reactor Vessel Pit nino rungs below Ref. 57 l
2030 intermediato landing.
(Elev. 24' 8").
Approx.
Shut v.c. sume isolation valves.
Ref. 4 2165 e
r
'o' e
SinDAY, OCTOBER 19, 1980 3
2200 Opened condenser Vacuum Dreakers.
Ref. 10 2230 Second Reactor vessel Pit Portable Pump still Ref, 39,I?
not working.
N.P.O.
cent in to correct im-110 proper hook up.
Water level about 4 feet below intermediate landing.
First pump still working.
r X.
Opened inlet valve on F.C.U. #25.
Ref. 4 e
O e
MONDAY, OCTOBER 20, 1980 i
I PLANT STATUS:
Reactor subcritical in a hot shutdown mode Ref. 1,2 awaiting return to power.
The Vapor Contain~
ment airlock door was closed with people working inside on F.C.U.'s.
Approx.
Completed repairs on F.C.U.
- 25 and valved Ref. 2,4 0025 it into service.
0125 Started F.C.U.
325 for tost.
Showed no ex-Ref. 1,2 cessive leakage.
Approx.
Second Reactor Vessel Fit portable pump of f Ref. 57 0115 again.
Water at 14th rung below intermediate landing (elev. 19' 8",
4" of water on bottom of pit).
V.C.
Sump pumps isolation valves closed.
Ref. 2 Approx.
Opened V.C.
Sump isolation valves.
W.E.U.T.
Ref. 4 0145 level at 86%.
- Approx, V.C.
Sump isolation valves closed with Ref. 2,4 0205 W.H.U.T.
level at 944..
0305 During V.C.
ontry found water on floor outside Ref. 3 9, C missile barrier, where it had previousli 110 (prior to midnight) been reported dry.
Opera-tors were wont into V.C.
to remove portable submersible pumps, if water level was found below incore instrument conduits in Reactor Vessel Pit.
Otherwise, were directed to add oil to the portable submersible pumps and continue pumping the Reactor VeScel Pit.
Water level was found below conduits in pit.
Approx.
Reautor Vessel Pit essentially dry.
Two Ref. 43,l' 0530 portable submersible pumps had boon ro-moved from the Reactor VesGel Pit and placed on floor outside missile barrier on elevation 4G feet floor.
Plant Manager made decision to Startup plant.
Ref 34 n
MONDAY, OCTOBER 20, 1980 2
Approx.
Performed V.C. Closcout.
V.C.
sump pumped Ref. 2,4,3' 0610 down all the way; final check on all F.C.U.'s 39,41,C found no leaks on cooling coils, motor coolers, 62,110 or external piping.
Removed air hoses from Reactor Vessel Pit and closed and locked the grating.
Recommended entry be madG in n0Xt 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to check for leaks.
L'. C. U. weir (22 was utill flo.fing sono water.
V.C.
sump isolation valves were closed with W.H.U.T.
level at 9$%.
Approx.
Commenced control rod withdrawal for normal Ref. 1,3 0630 startup.
0650 Reactor critical.
Ref. 1,2,4:
0700+
W.'H.U.T.
being transferrcl to Unit 1.
Ref. 4 Approx.
Manager, Nuclear Power Generation (N.P.G.),
nef. 34 0800 who had been on vacation since 10/14/80, arrived on site and was briefed on plant status.
0800 Annaphone in Resident Inspector office inter-Ref. 21,3C rogated.
Message frcm licensee indicatcs:
TLme 2 22 p.m.; 10/17: requests return call.
No reason given.
Resident inspector re-turned call at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />, found licensee representative out, and requested call back.
Approx.
Manager, N.P.G. made decision to shutdown, Ref. 33,34 0830 based on concern about chlorides on stain-leGG steel incore instrument conduits, v.P.
- Power Generation updated on plant s ta tus.
V.P.
- Engineering notified of water on V.C.
Ref. 33 floor and in the neactor vessel Pit.
Licensee initiated effort to compute volumo Ref. 34,25, of water pumped fron V.C.
Chemistry and 42 Fadiation Safety Director was instructed to swipo survey incore instrument conduits to determine level of flooding in Reactor Vessel Pit.
a
MONDAY, OCTOBER 20, 1980 3
0955 Reactor manually shutdown from less than Ref. 1,2 1% power.
Turbine never taken off turning gear.
Approx.
Opened V.C.
sump isolation valves with Ruf. 4 1010 W.H.U.T.
level at 80%.
Approx.
Closed V.C.
su*.y isolation valves with Ref. 4 1050 W.H.U.T.
level 95%.
1110 tcde preoarations for V.C.
entry.
Ref. 1,4 Approx.
Licensee returned call to Resident Inspector.
Ref. 21,3 1130 Stated that some water was found on contain-ment floor over weekend and plant was critical this morning, but now in hot standby.
Approx.
Licensee sampled water in Reacpor Vessol Ref. 1,12 1200 Pit; found 3400 ppm Nacl.
Licensee swiped 42,S1 incore instrument conduits; gound levels from 0.025 to 1.53 mg/100 cm' of chlorides, from point above elevation 46 feet to Reactor Vessel insulation, with res61ts increasing as neactor vessel was approached.
1300 Mon out of V.C.
Ref. 1 Manager, Nuclear Generation informed Sonior Rof. 35,2' Resident Inspector that preliminary water 37 inventory balances indicated about 43,000 gallons of water were pumped from the V.C.
Appro.v..
Resident Inspector called Region I; notified Ref. 20 1605 Acting Section Chief of V.C.
flooding, that preliminary inventory calculations indicated 43,000 gals. of liquid were removed from the containment.
Question of potential wetting of Reactor ;essel raised by Region I.
Approx.
Shut V.C.
sump isolation valves with W.II.U.T.
Ref. 4 1635 level 96%.
n
.,s
~
UONDAY, OC'OBER 20, 1980 4
T 1645 Region I called licensee.
Licensee indicated Ref. 20 Reactor Vossel was not wetted.
Chief Opera-tions Engineer and Assistant Chief Field Engineer were performing calculations to support these contentions.
Plant in hot shutdown.
Information requested from licensee on restart plans.
1707 Region I called senior Resident Inspector to Ref. 20 discuss open questions.
Approx.
Region I called IE HQ to discuss open ques-1710 tions.
1720 Region I called licensee.
Received licensee Ref. 20 commitment to not restart without first pro-tiding NRC four hours warning.
Discussed open questions wLth licenseu.
(1) Was Reactor Vessal wetted?
(2) If so, what effect on vessel?
(3) What corrective actions prevent re-occurrence.
(4) What plans exist for inspection of stain-less steel conduits?
Approx.
Opened V.C.
airlock for entry.
Ref. 4,11'.
L830 Approx.
Closed V.C.
Ref. 4,110 1900 Chief operations Engineer recomputed best Ref. 37 estimate of water pumped from V.
indicated about 106,000 gallons were removed.
Approx.
Nuclear side N.P.O.
entered v.C.
to string Ref. 4,11C 2100 hoses for clear.ing.
Unisolated city water to V.C.
Approx.
Opened v.C.
sump isolation valves.
Ref. 4 2135 Approx.
Shut V.C.
sump isolation valves.
Ref. 4 2205 2300+
11)
V.C.
sump isolation valve closod.
Ref. 4 (2)
W.R.U.T.
being transferred to Unit 1.
O m
s
~
TUE5 DAY, OCTOBER 21, 1980 PLANT STATUS: Reactor was subcritical in a hot shutdown mode Ref. 1,2 awaiting return to power.
The Vapor Containment was closed but unlocked.
People working in V.C.
City Water had been valved into the Vapor Con-tainment for cleaning.
0100+
Opened V.C. sump isolation valves.
Ref. 4 Approx.
Licenree took ten additional swipes of incore Ref. 13,35 0330 instruaent conduits, finding 0.065 to 0.605 37,110 ag/100 W, of chlorides.
Licensee sampled stain-less steel wool from the Reactor Vessel insulation; found 0.085 mg chlorides / gram of material.
0430 Nuclear side N.P.O. toured V.C., found elevation Ref. 4,110 46 feet floor dry, except for low area puddles.
V.C. sump full. Maintenance working in reactor vessel cavity.
0440+
Opened V.C. sump isolation valves.
Ref. 4 0605 NRC called for Plant Status Ref. 1 Approx.
Sampled V.C. Sump.
Ref. 25 0800 0845 Rtgien I called by Senior Resident Inspector:
Ref. 20,27 informed of plant status and plans.
Immediate Action Letter questions discussed.
Approx.
Started pumping V.C. sump.
Ref. 4 0900 App rox.
Spare N.P.O. tagged out the Reactor Vessel Pit sump Ref. 4 0930 pump controls and fuses.
Secured pumping V.C. sump.
W.H.U.T. level at 90%
0942 Licensee swiped insulation sleeve for a Reactor Ref. 13 Vessel Ingore Instrument stub tube; findings 2.9 mg/100 ce of chlorides.
1134 PNO-I-80-154, Centainment Fan Cooler Service Water Ref. 28 Leak, issued Approx.
Licensee took three swipes in and around insulation Ref. 13.110 1315 sleeve for Reactor Vessel Incore Instrument stub tubes; finding 0.44 to 1.66 mg/100 di of chlorides.
1
2 TUESDAY OCTOBER 21, 1980 Licensee cleaned incore instrument stainless Ref. 34 steel conduits in Reactor Vessel Pit Approx.
Opened V.C. sump isolation valves Ref. 4 1430 1430+
Completed certain precritical checks Ref. 4 Cleared Work Fennit on power range N42 detector.
Ref. 2,40 Conducted PT M29. Rev.1 (NIS Datector current 44
-comparator operational test), PC M1, Rev. 23 (Nuc1 car Power axial offset calibration), and PT M1, Rev. 26 (NUC. Power Analog).
Inspection of the Nuclear Instrument Channel N42 signal i
--f pew 2r lead connectors, located in the
- tor well, found drops of water within the
---d connectors.
The detector was replaced.
154?
' n I called licensee to solicit commitments Ref. 20
~AL 00-41.
Ecn:;er, Nuclear Power Generation decided to Ref. 26.34 proceed to cold shutdown.
35,37,4r Licensee recognized lacked proof that Reactor Vessel was no; wetted.
Licensee directed operators to cool Reactor Coolant System (R.C.S.) to cold shutdown to allow removal of the Reactor Vessel insulation, swiping and cleaning of Reactor Vessel surfaces, as necessary.
1659 Resident Inspector entered V.C. for inspection Ref. 110 of conditions in Reactor Vessel Pit.
Noted over-head lights out, white substance (like salt) on ventilation duct and arcund seams of Reactor Vessel mirror insulation.
2000 Comnenced borating Reactor Coolant System to Baron Ref. 1.2 concentration required for cold shutdown.
Approx.
Inserted shutdown Bank A by tripping Reactor.
Ref.'1,3 2020 W.ll.U.T. being transferred to Unit 1 Ref. 4 2300+
V.C. sump isolation valves open Purging V.C.
e
__._Q Q
EDNESDA'f, OCTOBER 22, 1980 PLANT STATUS:
Reactor subcritical and being cooled down to Ref. 1,2 cold shutdown mode.
Borating 60 cold shut-down condition.
All control rods inserted into the Reactor.
Purging the V.C.
W.H.U.T.
water being transferred to Unit 1.
Approx.
Maintenance entered V.C. to replace both Ref. 4 0045 Reactor Vassol Pit electrical sump pumps.
0530
.Biocked safety Injection.
Ref, 1 0615 NRC called to determine " Plant Statuu".
0700+
(1) still proceeding to cold shutdown.
Ref. 4 (2)
W.H.U.T. being transferred to Unit 1.
Approx.
521 Residual Heat Removal ( R.H. R) pump in Ref. 4 0845 service.
IAL 80-41 issued.
Ref. 27 1500 Investigation team dispatched from negion I Ref. as and other sites.
1G00 Licensee performed seven swipes of Reactor Ref. 13,.
Vessel shell, mirror insulation and'various Reactor Vessei Pit components; finding then0.005mg/100cm-to0.30mg/100cm}ess of chlorides.
This followed the first opening of the mirror insulation by the removal of a small square plate located at dead center bottom of the Beactor Vessel Ecad.
1700 Licensee determine boildown residue of 50 mls Ref. 13 of Hudson River Water (45000 ppm yielded a swipe result of 43.6 mg/100 cm, Nacl)
' o f chlorides.
1900 Investigation team assembled on site and wero Ref. 88 briefed by Resident Inspectors.
2000 Investigation team conducted first inteview.
Ref. 32,E O
THURSDAY, OCTOBER 23, 1980 PLANT STATUS:
Reactor now in cold shutdown with multiple Ref. 1,2 activities progressing within the vapor Con-tainment.
The Containment was open.
0000+
Licensee dipped stainless steel plate in Ref. 13 river water, dried the plata and swipeg f
it.
Sample results show 1.0 mg/100 cm o
0430 Licensee swiped five locations on Reactor Ref. 13,34, Vessel surfaces now exposed by removed mirror 35 insulation.
Sample results later showed chloride contagination levels of 19.0 to 41.0 mg/100 cm.
This followed removal of a circular piece of mirror insulation, about two foot in diameter, located dead center on the lower Reactor Vessel Head.
0730 Investigation Team met with licensee to dis-Ref. 88 cuss scope and duration of investigation, scope of assignment for each investigator, and current status of plant, licensee's in-vestigation, and plans for return to opera-tions.
0900 Licensee repeated earlier boildown and swipe Ref. 13 test of 50 mis of river water.
Swipe showed 2
49.0 mg/100 cm of chlorides.
1000 Licensee performed investigation team re-Ruf. 13,8E quested sample of recirculation sump water.
Sample showed 3400 ppm Nacl, 30 ppm Boron and 2.85E-3 uc/cc.
1350 Manager, Nuclear Generation informed investi-Ref. 35 gators that the current estimate of water pumped from the V.C. was 85,000 gallons and that the licensee still believed no water reached the Reactor Vessel.
Approx.
Licensee informed investigation team that Ref. 88 1600 they had received report from an S.W.S. that water level may have approached elevation 46 feet grating.
O a
, t -
'TIIURSDAY, OCTOBER 23, 1980 2
1700 Licensee swiped ten locations in reactor Ref. 13 vessel pit.
Samples would later show chloride levels from 0.08 to 25 mg/100 cm2, Approx.
Licensee informed investigation team of identi-Ref. 88 1800 ties of licensee employees who report to have soen water level within one to four feet of elevation 46 feet grating.
O e
l 4
e e
e y
,e
, ~.
. [).
y
,.4 FRIDAY, OCTOBER 24, 1980 PLANT STATUS:
Reactor now in cold shutdown with multiple Ref. 1,2 activities progressing within the Vapor Containment.
The Containment was open.
0500 Licensee swiped five reactor vessel locations Ref. 13,2 newly exposed on lower hemisphere as insula-tion was removed Sample results later show I
31-170 mg/100 cm.
This followed removal of the first four pie shaped pieces of mirror insulation on the Lower Reactor Vessel Head.
1020 Licensee called Resident Inspector office.
Ref. 42,1 Informed investigation team that licensee had determined that deposits on Reactor Vessel were definitely residue from evaporated river water.
Approx.
Licensee met with investigation team.
Ref. 88 1
1200 Investigation team informed that licensee believed about 9 feet of the Reactor Vessel were covered with river water, while in hot shutdown.
The status of the plant, licensee's investigation and schedule for corrective actions were discussed.
Approx.
Information Notice 80-07 on the Ind'ian Ref. 83 1800 Point 2 incident issued.
O
..i.
REFERENCE LIST 1.
SRO Log Book 10/8/80 - 10/22/80 2.
SWS Log Book 10/8/80 - 10/21/80 3.
Computer Alarm Printout 10/17/80 - 10/21/80 4.
Nuclear NPO Log 10/3/80 - 10/22/80 5.
Indian Point No. 2 - Information to Incident Response Center from Log 10/16/80 - 10/21/80, Memo from R. Woods, IE:HQ 6.
Detector Instrument Wells Sketch 7.
Containment Building Air Circulation System - Reactor Cavity Cooling -
Drawing 9321F4869-2 8.
Flow Diagram - Ventilation System for Containment, Primary Auxiliary and Fuel Storage Building - Drawing 9321-F-4022-14 9.
Dew Point Temperature Recorder Chart - 10/15/80 thru 10/21/80 10.
Conventional Side NPO Log 9/7/80 - 10/22/80 11.
Trouble Report including (: Quadrant Power Tilt Calculation Sheets, Procedure.
E-12 Rev. 3 Nuclear Instrumentation, Malfunction).
12.
Significant Occurrence Reports80-162 through 80-179; Note 80-177 was rewritten 10/24/80 13.
Unit 2 Reactor vessel chloride swipe Sample results:
10/20/80 -
10/23/B0 14.
Indian Point Station - Unit No. 2 Central Control Room Log Sheet 9/1/80 thru 10/21/80 1
15.
Flux Difference Log Sheets. October 8,1980 - October 21, 1980 16.
Dwg A207320-0, Diagram for connections for MCC-28 and Reactor Cavity Sump Pumps 17.
Crane Deming Pump Instruction Manual (Reactor Cavity Sump Pumps)
\\
l i
I I
..s;
Reference List (continued 2
18.
Specification No. MP 72-044, 6/16/72 (Reactor Cavity Sump Pumps) 19.
Quadrant Power Tilt Calculation Sheets October 18 - October 8, Operater N.I. plots of October 17, and Incore Flux Map of Octcber 17 20.
Telephone Log Book T. Martin 8-26-74 to date 21.
Telephone Log Book T. Rebelowski page covering 10-17. through 10-20 22 Indian Point Unit 2 Technical Specifications 23.
M W packages 2937, 2940, 2932, 2938, 2935, 2944 24.
Reactor Coolant Leakage Surveillance Records 10/3/80 - 10/16/80 25.
Chemical Division, Routine Test Log 10/6/80 - 10/22/80 26.
Night Orcer Book - Pages 78 thru 81 27.
nmnediate Action Lettor 80-41.
R.
PHO-I-CO-154 29_
Eight Photographa r.aken P.M. of 10/21/80 30.
Eleven Photographs taken A.t".
of 10/23/80 31.
Six Photographs taken P.M. of 10/23/B0 J2.
T. Schmei:ser. Senior htch Supervisor (G.W.S.) Trainee - 10/23/30 33.
1:. McGrath, V. I'. Power (ienera ticn ant! P.
- Zarakas, V.
P.
Entiineering Interview - 10/23/30 34.
M.
Shatkcuski, Plant Manager Interei.ew
.10/23/80 35.
W.
Monti, Manager - Nuclear Power Generation - 10/23/80 36.
J. Makopoaco, Tcchnical Enginocring Director - 10/23/80 37.
J.
Curry, Chief Operations Engineer - 10/23/8C 38.
R.
Spangenberect, NPO, Intervicw - 10/24/80 O
- 6 t
Reference List (continued) 3 39.
P. Rannells, Contract lip Interview - 10/24/80 40.
A. Brescia, T&C Supervisor Interview - 10/24/80 41.
R. Orzo, SWS Interview - 10/24/80 42.
S. Wisla,. Chemistry and Radiation Safety Director Interview -
10/24/80 43.
G. Hughes, NPO Interview - 10/24/80 44.
E. Baisel, I&C Supervisor Interview - 10/24/80 45.
W. Wedler, QA Engineer Interview - 10/24/80 46.
D. Bishop, RO Trainee Interview - 10/24/80 47.
G. Tobler, SRO Enterview - 10/25/80 48.
C.
Powell, GWS Interview - 10/25/80 49.
J.
Lewis, STA Interview - 10/25/80 50.
C. Limoges, Reactor Engineer Tnterview - 10/2S/80 51.
MWR 2936 & Procedurc 1C-CM-32.
" Removal and Replacement of Neutron Detector au:.semblies.
52 B. Olson, T&C Technician Interview - 10/27/80 53.
R. Flynn, IAC Technician Interview - 10/27/80 54.
W. nurr, Reactor Operator in Training - 10/27/80 55.
E. Ostman, Nuclear Plant Operator (NPO) -
56.
T.
Prunty, Nuclear Plant Operator -
57.
R.
Vogle, ITea)th Physic Supervisor -
58.
M.
Ruh, NPO in Training -
I
\\
l 1
.' s Reference List (continued) 4 59.
T. Walsh, I&C Engineer Interview -
60.
M.
Hayes, SRO Interview - 10/27/80 61.
11. Mann, NPO Trainee Interview -
l 62.
J. Jawor, NPO Interview -
63.
T. McKenna, Maintonance Foreman Interview -
64.
J. Halpin, Maintenan:e Superintendent Interview -
65.
T. Rebelowski, Schedule of Activities 10/17 thru 10/21/Ao 66.
Reactor Vessel Sump Water Level Plot 67 Conventional Area Log Sheet, Unit No. 210/3/8Q - 10/7/80 68.
Dia:nond Power Specialty Corporation, Mirror Insulation, Drawing MIC369-00lt,-003C -023C and-027C 69.
Employee Work Schedule 10/19/80 to 10/25/80 70.
Dwg. A200063, Containment Interior Concrete Plant at Eley. 46'0" and Dwg. A200525, Containment Building General Arrangement 71.
ESR No.12-9019 dated 3/15/79, FCU Epoxy Repairs 72.
Class A Modification Precedure. " Replacement of Leaking Section of #23 Fan Motor Cooler Return Line #496" dated 3/14/78 I
l 73.
Tony Nespoli, outage coordinator interview - 10/28/80 74.
Goulds Installation, Operation and Maintenance Instructions 75.
UE&C Specification No. 9321-01-238-15 dtd. 9/19/67 for Pumps
!24 and 25 (original nos., later changed to #29 & #210) 76.
PT-RZA, Rev. 2, " Containment Sump Level Analog Test" 77.
Containment Elevation Results frT,m Surveyor j
78.
R. Carter. NPO Interview - 10/29/80 O
^
i y.,
8 Reference List (continued) 5 79.
Dominec J. Sarc Partial Interview 10/26/80 80.
T. Hansell, NPO Interview 10/29/80 81.
W. Lettmoden, S.W.S. Interview 10/29/80 82.
I. Barlin, NPO Interview 10/29/80 83.
IE Infonnation Notice No. 80 Containment Cooler Leaks and Reactor Cavity Flooding at Indian Point Unit 2, dtd 10/24/80 84.
News Paper Clippings BS.
Press Release dated 10/23/80 86.
Memorandum from Con Ed's W. A. Monti, Manager-Nuclear Power Generation. SUBJ:
Vacation Replacement 87.
Picture Cataglog 88.
IP2 Investigation Spiral Dound Notes, 10/22/80 -
89.
Partial Fan Cooler Maintenance List (Tony Flora) 10/25/80 90.
List of Diamond Power /W dwgs number for mirror insulation for head.
TRausch, Diamond POWor) 91.
W/ Con Ed Flow diagram for Service Water System Con Ed Dwg. A200755 92, 9/30 - 10/19/80 Fan couler related maintenance list (Tony Flora) 93.
Chlorido and Fluoride Determination Procedurc IPC-A-027 (J. Higgins) 94.
List. of River Water Analysis Procedures (J. Tiiggins) 9S.
Dionek lY Operation and Analysis IPC-A-100 Rev. 0 (J. Hiqqins)
.D..
s
. ' = *. '
Reference List (continued) 6 96.
Instrumentation Penetration Assembly for RV CE dwg. E232-056-5 (E. Somers, W) 97.
Higgins hand calculation of convgrsion of 4600 ppm Nacl 50 m1 sample to determine Cl /dm concentration 98 Swipe Test List as of 10/24/80 (Partial List) (J. Higgins) 99.
Indian Point Chom Lab River Water Analysis for 10/22/80 (J. Higgins) 100.
Con Ed proposed procedure (Notification procedure) (CPG-80-2-10 for plugging tubes.
Project 9096 ESRI2-9019 101.
Containment Gldg. General Arrangemen t Con Ed Dwg. A200625 (Section "G-G") A200624 (Section "B-B")
102.
Portions of Indian Point 2 System Description 610.3
" Containment Cooling and Filtration System" 103.
10/26 PT Map of Nozzle PI locations (offical results invalidated due to ex cssive of non-relevant indications, however, no crack like linear indications)
(W. Perriera) 104.
Kressner to Monti Memo and deposit analyses of Jwipe Test chloride determination)
(J. Higgins) 105.
Updated Cl-determinations received 10/26/80 (J. Higgins) 10G.
PT report on no::les and conduit QCIR 80-2-44 dtd. 10/24/80 (W. Forriera) 107.
Steve Lerman info on inn chromatography methods (S. Lerman) 103.
Walter Wedler, QC Engineer, ne-Interview - 10/29/80 109.
Licensee's 10/28/80 Dra ft Operations History and Sequence of Events 110.
V.C.
Entry Logs 10/17/80 - 10/24/80 111.
Water Inventory Review 112.
QCIR & Associated MWR Master List and QCIR's 113.
Summary of Maintenance Engineer's Visual Inspection of Fan Cooler Units 1J 4.
Reactor Vessel Chloride Swipe Tests - 10/29/80 O
4 Reference List (continued) 7 115.
Maintenance Summary from MWR Records o f Fan Cooler Service Water Related Failures - 10/26/80 llG.
IDQ Procudure 93 117 J. Higgins, General Chemistry Supervisor Interview - 10/26/80 118.
R.
Burns, NPO Interview - 10/25/80 119.
J. Cullen, General Supervisor HP - 10/25/80 120.
Work Permit File B5000 series 121.
Press Release for Public Meeting scheduled 11/5/80 on Leakage of River water into containment at Indian Pt. 2 122.
Frank Phillips, Manager, Field Office QA&R - 10/27/80 123.
William Ferriera, NPG QA Engincur - 10/27/80 124 Con Edison Memo, Notification of Significant CVents, 3/6/80 125.
Indian Point Station Telephone Directory, 2 pa,qes 126.
Con Edison Report to AEC-Report 1/17/74 (Feedwater Line Break) Report & Letters 127 No. 23 Reactor Coolant Pump Seal Loss - 7/2/77 Plant Logs e Letter 128.
Composit of intorviews addressing sump leveis 129.
MNn's listed in reference 112 F
l l
l l
M
.E D
\\
'"?
go t
e
. '.p 1
4
(*
3 u
- J P
e.,/,
S
. s>
v i
4%.
4
. s, i'
-.. s.
-t a
l'
.s
,, y i a
,. )
y p
~
- k e
%s
," /~g\\
s s
(
l k rs s g>
i
,=
g
~
g j
'cQ f
i 80'b e D
l
- . On.
Q g
2' t"*
.~)
=
II w
v
'.y g-up
==
u i
r-o,,
\\
~,.
.. r:
9
- e.,*
m p
.o.
j
,g.
- = ' ' ~
-.'~
gr av
\\.a.).
~,
s"
=
'G~
y,
\\Q %r e
m di G
en *
^
Q
+
t.
J g.
__2.-
.s us y o'\\
O 4.
g o.
O o
's N
s a
N g
d 4*
9
~
s e
-e k.
g
.i,. s 9..
i -
m, s,
e O2
\\*
i e
v-f.
db
=
t
.o a,
,J a.
j
,1..
t J
g
.g O
\\
.r 2
w Md s-a W
7 d
N
.s
/
W.. :/,I, '.,.'-
s s
\\
e s
')#j 4
8 I
,7 h
g
- \\
g\\
g a.
p ja 98 o.**
O s'
- s s
/
o s%
.v s
. #.....,,s,
~~~~
.s u.
..a
?.
.,1 4.,e 4
- g' z'.
\\'
,, e A
p.
e N
a p
O G.
=
7
(
n-a 5a 1
e O
gfl [L
~
. - -..+-
- \\
q
. v.
s o*
l,..
i 1
i t..
'p'.
\\
.e lr s
i e*.,.
t s
jJ
._2 p
\\
")
I%
1 h
t s i
s 4
g JM
,I
.. - = =
e
~;
g
- .....i..
d f
e
=
't I
. t I
.l
\\
'g e
g g
. ',,h' y, U
- yp
.,1
,,gi
~
,-,r-
--, - - ~
.w..
.A e
r LT'iW
^
^
i.
'" ~
' 5 5..
157 1
( 157'*)
g
/
i,
%i
- 1. NGMBEQ.*a \\M PARESTH,Gsts 141" (16) 54oW o Ni JNDicA762. LtAn g
~
IN ce4 TEAL cowTaot ecoM.
(t39*)
- 2. ALL MEA %2EM:EMTS A2.E 2E AEEGNCED PROM THE MTTDM OF TAV. SOMP inni
-" W 3 Tanen56 Astt As f. EFT AckC/:
- ealoft.C/90. 8a do emsT.
s m eraa Mian.73 neo,gicar 3u3p pogp
<;o g p pggp p
...r q,.
93-i f
(FD mJ s
j
,@,.,.]
(,90 H
8
'. ~
$Q.
[m%o lJ a
~
4 N
i g
M.
8 O
,y g
gg g
..g r
i i
-' i k
k I
q' (50 I
%..)
4y
.........i 4
I 5
s uN
(
s s 4
'-0 CFF 14 p
g U ~o F F C
t:1 a
,'n 13-CO
-(c)
/ m.m ws j
x O
g
--w y--
. - - - - - - - - - _