|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20199J6981997-11-11011 November 1997 Rev 2 to 10CFR50.59 Review for Jet Pump Thermal Sleeve Cracking ML20202H1231997-09-30030 September 1997 Small Project Joint Permit Application & Attachments for PECO Energy Co,Peach Bottom Atomic Power Station,Rock Run Creek Low Flow Crossing, to Satisfy PA Dept of Environ Protection & Us Army Corps of Engineers ML20129E8711996-09-26026 September 1996 Rev 0 to 10CFR50.59 Review for NCR Pb 96-03414,Core Spray T-Box Cracks for Peach Bottom Atomic Power Station,Unit 2 ML20117E6351996-05-31031 May 1996 Seismic Evaluation Rept for Pbaps ML20117E6321996-05-31031 May 1996 USI A-46 Relay Evaluation Rept for PBAPS Units 2 & 3 ML20117E6251996-05-31031 May 1996 Seismic Safe Shutdown Equipment List for PBAPS Units 2 & 3 ML20129A4511996-01-11011 January 1996 Core Spray Sparger Downcomer Modification ML20129A4731995-12-11011 December 1995 Fabrication of Core Spray Line Downcomer Clamp ML20092M8921995-09-30030 September 1995 Shroud Vertical Team Weld Evaluation ML20098B1141995-09-30030 September 1995 Evaluation of Peach Bottom Unit 3 Core Spray Line ML20098B1211995-09-30030 September 1995 Residual Stress Analysis of Peach Bottom Unit 3 Core Spray Pipe to Sleeve Fillet Weld ML20092J8151995-09-15015 September 1995 Core Spray Line Tee-Box Analysis Rept for Peach Bottom Atomic Power Station Unit 3 ML20094H0521995-06-30030 June 1995 Pyrolysis Gas Chromatography Analysis of 21 Thermo-Lag Fire Barrier Samples ML20092K9871995-06-13013 June 1995 Rev 3 to Shroud Stabilizer Hardware ML20083K6611995-04-26026 April 1995 Rev a to Upgraded Eals ML20077M0861995-01-31031 January 1995 Nonproprietary TS Improvement Analysis for RPS for PBAPS, Units 2 & 3 ML20077M0951995-01-31031 January 1995 Nonproprietary TS Improvement Analysis for ECCS Actuation Instrumentation for Pbaps,Units 2 & 3 ML20073J7501994-09-30030 September 1994 Shroud Mechnical Repair Program,Peach Bottom Shroud & Shroud Repair Hardware Stress Analysis ML20079S0911994-09-29029 September 1994 Rev 0 to Application of Screening Criteria ML20073J7411994-09-24024 September 1994 Rev 0 to Stress Rept 25A5607, Shroud Stabilizers ML20072P5791994-08-26026 August 1994 Power System Harmonic Study for Peach Bottom Nuclear Power Plant, Final Rept ML20072L9631993-12-13013 December 1993 Evaluation & Screening Criteria for Peach Bottom Unit-2 Shroud ML20064K4291993-12-0303 December 1993 Evaluation & Screening Criteria for Peach Bottom Unit 3 Shroud Indications ML20059L1391993-11-30030 November 1993 Core Spray Crack Analysis for Peach Bottom Unit 3 ML20059G0901993-10-27027 October 1993 Evaluation & Screening Criteria for Peach Bottom Unit-3 Shroud Indications ML20149G0401993-05-30030 May 1993 Fatigue Evaluation of Peach Bottom II & III Reactor Vessels ML20118A3641992-08-26026 August 1992 Vols 1 & 2 of Individual Plant Exam,Peach Bottom Atomic Power Station Units 2 & 3 ML20073E5881991-04-30030 April 1991 Revised Station Blackout Analysis ML20073D0221991-04-30030 April 1991 Full Structural Weld Overlay Design for Peach Bottom Unit 2 RWCU Weld 12-I-1D ML20067E5071991-02-0808 February 1991 Simulator Performance Rept. W/Two Oversize Drawings ML20067E5051991-02-0808 February 1991 Simulator Performance Rept. W/Two Oversize Drawings ML20067E5091991-01-28028 January 1991 Malfunction Causes & Effects ML20055J3271990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20055J3231990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20055J3291990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML18095A3791990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20044H3281990-02-23023 February 1990 Rev a to 30-Month Stability Spec for Rosemount Models 1152, 1153 & 1154 Pressure Transmitters ML20247N3951989-05-16016 May 1989 Methods for Performing BWR Reload Safety Evaluations ML20236A8501989-01-31031 January 1989 Voltage Regulation Study ML20236A8351989-01-31031 January 1989 Rev 1 to Peach Bottom Atomic Power Station Units 2 & 3, Verification of Calculated Auxiliary Distribution Sys Voltages by Test ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20206K3021988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3 ML20151M5501988-07-15015 July 1988 Security Problem Root Cause Assessment ML20147A7971988-02-23023 February 1988 Root Cause Investigation of Shutdown Cooling Isolations Peach Bottom Atomic Power Station ML20148H1211988-01-15015 January 1988 Rev 0 to Peach Bottom Atomic Power Station,Units 2 & 3, Response to IE Bulletin 85-003 ML20149D6981988-01-13013 January 1988 Methods for Performing BWR Steady-State Reactor Physics Analyses ML20196K0311987-12-31031 December 1987 1987 Annual Plant Mod Rept,Per 10CFR50.59 ML20236V3311987-11-20020 November 1987 SAR for Peach Bottom Atomic Power Station Spds 1998-12-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000278/LER-1999-005-03, :on 990920,uplanned Esfas During Planned Mod Activitives in Main CR Were Noted.Caused by Inattention to Detail by Individuals Performing Work.All CR Mods Were Ceased to Allow Review of Mod Work Packages.With1999-10-20020 October 1999
- on 990920,uplanned Esfas During Planned Mod Activitives in Main CR Were Noted.Caused by Inattention to Detail by Individuals Performing Work.All CR Mods Were Ceased to Allow Review of Mod Work Packages.With
ML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 05000278/LER-1999-004-03, :on 990901,3A RPS Bus Was Inadvertently Deenergized,During Planned Mod Activities on Main CR Panel. Caused by Electrician Failing to Self Check Work.All CR Work Was Ceased Immediately & Shutdown Meeting Held1999-10-0101 October 1999
- on 990901,3A RPS Bus Was Inadvertently Deenergized,During Planned Mod Activities on Main CR Panel. Caused by Electrician Failing to Self Check Work.All CR Work Was Ceased Immediately & Shutdown Meeting Held
ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML15112A7681999-09-20020 September 1999 SER Accepting Revision 25 of Pump & Valve Inservice Testing Program,Third 10-year Interval for Plant,Units 1,2 & 3 ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 05000278/LER-1999-003-03, :on 990814,HPCIS Was Declared Inoperable Due to Erratic Behavior Resulting in Loss of Single High Train Safety Sys.Caused by Weakness in Procedural Guidance. Readjusted Hydraulic Governor Needle Valve.With1999-09-13013 September 1999
- on 990814,HPCIS Was Declared Inoperable Due to Erratic Behavior Resulting in Loss of Single High Train Safety Sys.Caused by Weakness in Procedural Guidance. Readjusted Hydraulic Governor Needle Valve.With
ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with 05000277/LER-1999-005-01, :on 990616,failure to Maintain Provisions of FP Program Occurred.Caused by Less than Adequate Engineering Rigor in Both Development & Review Analysis.Fire Watch Immediately Established.With1999-07-16016 July 1999
- on 990616,failure to Maintain Provisions of FP Program Occurred.Caused by Less than Adequate Engineering Rigor in Both Development & Review Analysis.Fire Watch Immediately Established.With
ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with 05000278/LER-1999-002-02, :on 990406,safeguard Sys to Unrelated Door Was Inadvertently Disabled by Security Alarm Station Operator. Caused by Noncompliance with Procedures & Less than Adequate Shift Turnover.Briefed Personnel on Event.With1999-05-0606 May 1999
- on 990406,safeguard Sys to Unrelated Door Was Inadvertently Disabled by Security Alarm Station Operator. Caused by Noncompliance with Procedures & Less than Adequate Shift Turnover.Briefed Personnel on Event.With
ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 05000278/LER-1999-001-03, :on 990312,ESF Actuation of Rcics Occurred Due to High Steam Flow Signal During Sys Restoration.Temporary Change to Restoration Procedure Was Initiated to Open RCIC Outboard Steam Isolation Valve in Smaller Increments1999-04-0808 April 1999
- on 990312,ESF Actuation of Rcics Occurred Due to High Steam Flow Signal During Sys Restoration.Temporary Change to Restoration Procedure Was Initiated to Open RCIC Outboard Steam Isolation Valve in Smaller Increments
ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With 05000278/LER-1998-009-01, :on 981227,unplanned Esfa Were Noted.Caused by Transformer Insulator Failure.Replaced Failed Insulator. with1999-01-20020 January 1999
- on 981227,unplanned Esfa Were Noted.Caused by Transformer Insulator Failure.Replaced Failed Insulator. with
ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with 05000277/LER-1998-008-01, :on 981130,circuit Breaker SU-25 Tripped.Caused by Less than Adequate Procedural Guidance.Operators Verified Sys Integrity & Successfully Returned Sys to Svc.With1998-12-30030 December 1998
- on 981130,circuit Breaker SU-25 Tripped.Caused by Less than Adequate Procedural Guidance.Operators Verified Sys Integrity & Successfully Returned Sys to Svc.With
05000277/LER-1998-007-02, :on 981107,failure to Meet TS & Associated LCO Requirments of Absolute Difference in APRM & Calculated Power of Less than 2% Was Noted.Caused by Substitute Valves Being Used.Removed Substitute Valves.With1998-12-0404 December 1998
- on 981107,failure to Meet TS & Associated LCO Requirments of Absolute Difference in APRM & Calculated Power of Less than 2% Was Noted.Caused by Substitute Valves Being Used.Removed Substitute Valves.With
ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with 05000278/LER-1998-005-03, :on 981025,inadvertent Unit 3 Electrical Bus E33 Trip (Esfa) During Performance of Unit 2 Electrical Bus E32 Surveillance Test Was Noted.Caused by Personnel Error. Sp S12M-54-E32-XXF4 Was Completed.With1998-11-20020 November 1998
- on 981025,inadvertent Unit 3 Electrical Bus E33 Trip (Esfa) During Performance of Unit 2 Electrical Bus E32 Surveillance Test Was Noted.Caused by Personnel Error. Sp S12M-54-E32-XXF4 Was Completed.With
ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 05000277/LER-1998-006-02, :on 980915,automatic RWCU Isolation Occurred While Placing RWCU Sys in Svc.Caused by Unexpected Surge of Water.Procedure Change Was Initiated to Open MO-2-12-74 & RWCU Sys Was Successfully Returned to Svc.With1998-10-0909 October 1998
- on 980915,automatic RWCU Isolation Occurred While Placing RWCU Sys in Svc.Caused by Unexpected Surge of Water.Procedure Change Was Initiated to Open MO-2-12-74 & RWCU Sys Was Successfully Returned to Svc.With
ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with 05000278/LER-1998-004-03, :on 980820,automatic RWCU Isolation Occurred While Placing B RWCU Sys Demineralizer in Svc.Caused by less-than-adequate Control of Equipment.Isolated B Demineralizer & Returned RWCU Sys to Svc1998-09-18018 September 1998
- on 980820,automatic RWCU Isolation Occurred While Placing B RWCU Sys Demineralizer in Svc.Caused by less-than-adequate Control of Equipment.Isolated B Demineralizer & Returned RWCU Sys to Svc
05000277/LER-1998-005-02, :on 980824,noted Failure to Meet TS Actions for Suppression chamber-to-drywell Vacuum Breaker Not Being Fully Seated.Caused by Personnel Failing to Take All TS Required Actions.Temporary Procedure Changes Were Made1998-09-18018 September 1998
- on 980824,noted Failure to Meet TS Actions for Suppression chamber-to-drywell Vacuum Breaker Not Being Fully Seated.Caused by Personnel Failing to Take All TS Required Actions.Temporary Procedure Changes Were Made
ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 1999-09-30
[Table view] |
Text
-
r,
(.
L,J HISTORICAL
SUMMARY
OF REACTOR KATER CHEMISTRY THROUGH 17/h PEACH E(7FTOM ATOMIC PC'.ER STATION UNITS //2 ed //3 PHILADELPHIA ELECTRIC COMPANY
.g" 4
8401260395 750324 DR ADOCK 05000 99 t
g'
~ ~ ~
~
~
9
. 9 PEACH BOPETOM UNITS 2 ( 3 REACTOR WATER CHEMISTRY,SUMPARY C
c
>q Unit E
/
'the first fill of >the hPV was on 6/5/7[with 700 ppm trisodium phosphate as PO.
4 Tho water chemistvor this fill and subsequent afulysis of water in the RPV indicate tha rcactor water to bo of a quality consistent ~with the requirements of Cleanliness Control of Piping and-Eqdpment, Spoc. 6280 - M-303, Technical Specifications, and Fus1 Warranty Documents. '
.s t"
1 w.
s...
Reactor Water analydes 'c'ammaridd below cover the initial fill and subsequent
\\
3
\\
flushes for 1972. Rosults for 1973 jnd 197h aro plotted with plant actitities noted on separato pages. From January tp June,1973, the dsta is presented as monthly ranges i
for pH and as monthly maximums for conductivity and chloridos, with the frequency of ths analysis roted on a separate page. Also included is a page noting the hours in 197h that the reactor water was between 1 and 10 prhos. Fuel Warranty allows lh days in this range.
1972 Chemistry - Reactor Uator (ungas othornise noted)
Notes and Related Cond.
Chloridos, Date Plant Activity
.r M pmhos ppb w
6/05/72 Ruactor Vessol Fill f
6.5 1.5
<10]
6/20/72 Flushing between reactor, ' torus, and C.S.T.
6/26/72 deactor vessol.1h0*F' 7/01/72 Attempted Hydro. of Reactor Teesel 7 /10/72 9.35 20.5 300 7/13/72 6.3 1.2
<100 7/18/72 Additional flushing completed of HPCI, Core Spray RHR, and ROIC 8/0h/72 Filling Torus from RPV + CST
]
79 2.9 CST Chemistry 7.5 2.h 8/06/72 CST Chemistry 0.8 1.0 Torus Chemistry 8/07//2 6.3 0.9
<10]
s 8/08/72 70 0.9
<10]
8 /09 /72 d
6.3 07 103 8/15//2 General flushing continues L..
s'
~~
8/29/72 Recirculating flushing completed
(
Reactor vessel drained for internal work 9 /26/72 Flushing reactor water C.U.
.\\
s 10/111/72
'y Flushing reactor water C.U.
s 10/2h/72 Flushing reactor water C.U. and tosting w
+
12/05//2./ CRD hydraulic system was operated for checkout "
, and filling of the RP7.
R.W.C.U. system was
\\
placed in service to maintain vnter quality.
12/11'/7'2
~
59 0.8
<100 12/19//2 (Pre-op testing - CRD and Core Spray,.
\\
5.7 1.2
<10D 12/27/72
$.6 1.0
<100
.12/28/72 12/29 //2 5.5 1.1
<100 e
N 4
Prepared by:
P. E.'Lutz, February 3, 975
. s.c - -.*. c r &
- . rt ev :
. '. - er e
- ,q e '
1 2
3 4:s 7
e 10 11 1?
13 IL 15 lo 17 e la 20 21 22 23 2L M
10u
- 1 u.
1 t
50 2..
l
,a.
4_
-_ - f O
f d
i 200
' 33 ' -
i i
,- 130 _.
__.,.._.4__..,
____i gg i
i
[
100
- 1 JO j
W
_i____.....
9 0
a i
i i.
t l
{
g t
I i
i P
See separate page for frequency of ar.aly11s, Jar..-June l
- [
v..+
- - - t t
a l
l
...-.a-.
i a
e.
,. ~
r
- -E __ $-~ s --., v%..-
6
~.. _.
.. -. -. - - - )I T-4 t
}
._{
p
._ __ g 3
4..
-o 5
j i
5 h
1 i
._.._p_..__.
. 2.0 ar.
f 1,5 1,3
,. -q..,, ;...
s
. ~.
., ~
c.
~.,a.,..
~
~,y o,a
.' armart February March Ap*11 May hre hly Aurust Septe w er Oetdar Moreece "e?eter PMCM SCrC a' %.. ?>
O.
PIANT EVENTS - 1973 PEACH BOTTOM f2 (Numbers correspond to those on plot.)
/
Date Plant Event T
1/2 RWCU operating to maintain RPV water quality 2
1/21 RPV hydro at 1020 psig h
' 2/13 1hcision to remove RPV head 3
2/2h Vessel head re-installed and bolts tensioned 5
2/27 RHR, Core Spray, RCIC, Reactor recirc., CRD Hydraulic System - initial dynamic flow testing essentially completed 6
3/1 RPV head removed 7
3/13 RPV and 7orus dowatered 8
3/27 RPV internal work completed 9-h/6 011 contamination discovered in hotwell 10 h/2h Oil contamination in hotweil cleaned up without affecting Condensate F/D 11
$/8 Fuel Inspection continues 12-6/5 Discovered putty like material floating on surface of Torus water
'13 6/19 Clean up flushing program - RPV to Torus lh 7/3 Torus clean up completed - Flushing included: RPV -> RHR -> Torus CST -> Core Spray ---> Torus Torus
- Cond. F/D - > Torus 15 7/9 Water returned to RPV and Torus 16 8/9 10% AEC license received - start fuel loading 17 8/26 Fuel loading completed 18 9/16 1st critical 19 9/2h RPV internals installed 20 10/h-10/6 RPV hydro completed 21 10/1h Reactor critical at 150 psig 22 10/22.
Reactor at 550 psig 23 10/30 Feedwater first delivered to the reactor vessel via the reactor feed pumps. Reactor water chemistry necessitated' shutdown. Letter frc:n CRH to WrU, ll/lh/73 'on file.
2h 11/6 Turbine rolled -' generator stator core winding problem discovered 25 12/h Decision to interchange the 2 generator stators W9 9
...-....m
l Im()
V) f PEACH BOTTOM f2 REACTCR WATER CHEMISTRI Frequency of ar.alysis: January - June,1973 Month Days Tested in Month January 20 February lh March h
April 10 May 15 June 6
OO o
7 rm
=
( )
a
.,a
.4
,o
.>,.a..o. g~o o3(sm I
\\j
~
=
t
.r -
y e,
8 uh g
< ~ ~
O s.
,s
=
w Y
r a
e 3
N, Oa i W
e F
8 R.
u h
I 3
8
~
(
i e<
l I
s.
I I
g, i
K 2
.i
.w.
~
n h
(4 0:
-4 t
n..
o a
.i 3
s o
')
l N
.n
/*
N 4
d
,b a2
?
1 l
- b i
s-r-
s' c
8 l ~".
C,L w
W e
- a. '
O 7
S 2'
J 4
w-2 a a s
u E
- 2. I s
m 3i
+
c a
3
. 4 I-I: 3(<
2 a.
~~
?
o
~
}
s.
+
- ehh, E
e y
v, e
5i 3
B l
o ).
y D
"e l
.C o
m.
u e
64 f.
i C
E i
b eo
,il
$98?S83P,RRo 1dri uastro peatossia
,o<
.s (m
c.
8o y ;_. -
e nvy
_-_.. ~. _ - o a >
i
,s
.i i,
, g a..i -
~
', i
.,i l'
g 7
1 1
i
- 9.._1.
p,. !
. I 1
4 4
1 a
i
~4-i el-a l
1
)
6 i
=>
.q 3
l
..l.
s a
g g
.i f
l 1
r
\\
.i 4
+--
s.
.i u__r_
r,
I 6
u, \\.
!. ?
4 s
i
.s 3
m 4
n 3
n I
i
- 1..
.t i
e d
g a
e s
4l
\\
a~.
n 3
L-
-..- {
- {-
._.p p,
x o
1 r.,
a t'
fi a.
y_..,
7 g
~_
__7
-1 I.
' '.s
~
i s
,e
. t,
.i E
.t +
0 4
i.
i o
s, d
~
i
[
%)
l!
g i.
i
_, a, -.. _ _...
,I.
i i.
e.
m
's 8
t
'(
.j I
i i.
r.
j t
- --- 1 :
Ii5 T
s
. t.
g
- 1 i
i
,2 i.i s
i
=
i t-
,i i.
t
- p. '.
a e.
.5 m,
3 t
,,.~ (,
7
'e 3
3 3
e s
t
,E 0
W
'19 i
s 2
i i
,1 s.
e s
- t. '
G
~.
,ic 5
c e
r e
,[ a
=
s a
=
J.
7
+
e.
j l.
~
i 4..
t g
.d: j a
?
I I'
- t 919"4 3 38o g8R0 e4 m r4 N
""4 e-e O O
,p anoa 3 qdd 'seppowo espin ud soqunt
p G
O PIANT EVENTS - 197h PEACH BOTTOM f2 (Nu;bers to correspond to those on plot.)
J Date Plant Events 1
1/1h Turbine generator rolled to synchronous speed 2
1/29 Generator overheating 3
2/13 Hydro to test recire, punp seal h
2/15 Turbine - generator rolled 5
3/5-3A0 Shutdown - Misc. Maintenance 6
3/18 Scram - Main Steam Lines isolated resulting in Reactor blowdown to tarus.
7
$/29 Shutdown to start pre-commercial mintenance outage 8
6/1h Condenser leak B-1 Water Box 9
7/1 Condenser leak B and A-2 Water boxes, small leak still in B-1.
10 7/$
!2 Commercial 11 7/26 Found substantial condenser leak in A water box.
12 8/2 Condenser leak repaired 13 8/5 Condenser leak repaired B Fater box lh 8/18 Small condenser leak indicated - appears too small to find 15 9/8 Condenser leak - C water box 16 9/13 Shutdown to repair condenser leak 17 9/16 Found condenser leak - Condensate pump shaft sheared 18 10/1 Condenser leak - A Water box (200 gpm flow of torus water to Reacter) 19 10/$
Condenser leaks repaired - A B-2 Water boxes,18 tubes in each box plugged 20 10/21 Condenser leak repaired, A-2 Water box 21 ll/h Scram - relief valve 22 11/5 Condenser tubes staked over weekend 23 11/16 900 stakes placed in condenser between tube support bundles; 2-3 leaks A-1, C-2 Fater boxes repaired additional leak C-2 Water box indicatcl.
2h ll/2h Condanser leak C-1 Water box indicated water box 0.0.S. remainder of week 25 12/2 Condenser leak A-2 water box indicated 26 12/3 Condenser leak indicated and repaired 27 12/16 Condenser leak indicated and repaired 28 12/19 and 12/22 Power reductions required for several condenser leaks - 229 tubes plugged A-1 12/21 and 12/22 Upper two rous of tubes - all water-boxes (1000 tubes plugged)
- 99 4
O O
PEACH BOTTOM f2 - 197h REACTOR WATER CONDUCTIVITY 11 a 110 Date Hours July 2
6 3
2h Sept. 9 13 10 21.8 29 6.6 Oct.
1 2h 2
3.5 19 6.5 20 h.6 Nov. 15 13 Dec. 15 13 5 16 6
139.2$ hours total =or 5.8 days O
ee
?-- -
l Unit 3
~
The first fill of the RPV was on 10/21/73 with 900 ppm trisodium phosphate as PO.
4 Nhils there were no reactor water analysis found per se during the initial fills and flurhes,analyscs for the water sources were available and are summarized below for 1973.
All the analyses are acceptable and conform to the Cleanliness Spec. requirements.
R: cults for 197h are plotted with plant activities noted on a separate page. Chemistry was within Tech. Spec. and Fuel Warranty during the operating period including January, 1975.
1973 Chemistry Notes and Related Cond.
Chlorides, Date Plant _ Activity pH mhos p;,b
[
9/26/73 Water in SLC Tank for RHft hydro 6.1 2.2
<10 10/19/73 Fill water - Demin. Storage Tank 7.5 1.0
<10 Fill water - Cond. Storage Tank 72 1.h 320 10/21/73 TSP Fill of Reactor 10/22/73 Fill Water - Demin. Storage Tank 72 0.5
<10
- 10/30/73 Refill of RPV after various systems were backflushed from reactor Cor.d. Storage Tank 73 0.8h
<1000 10/31/73' RPV after refill 0.3 - 0.7 11/02/73 Backflushing completed 11/17/73 RPV Hydro 11/20/73 ~
Reactor Vessel recirculation flush started 12/0h/73 Recire. flushing - Condenser - Reactor -
Min. Steam leads - Condenser, Cond. Demin. being used to clean up inventories on a routine basis 12/18/73 Flushing program essentially complete except
.HPCI and RCIC 4
'9@
-sh-
7 n
ob v
8R2PSRSARSo 4'.
A i
V<
As u
E
(*
U WJ 4% e AN' t
~.
7 V
N t
a rw l
C 4
- s e
b
S et J
e8 e
i vt of t
9
t Y
a F4*
p e
9 C'.*
to.
.e
./
3 4
d.
s3.'
r.
C r
CW.*
C.
%W l,
i
.e.
S 4
e C
e4 6
A 3
L
'o E
bi tr' L'
8 t.
Q f
W g
c 4.
^
E f:
W, i
ap en h
.N 9 #l [' 'E 8'N9 COO
.~
ad i'wB ern papenm
pm
' 4.z o
- 4. [m
. ;.i,
4 a e
e.
~
J.
l 3
t s.
l s
y g
.1
J s.
t O
..h,i i
i y
{
1
's, s.
I.
1 i
i i
s'+
1 8
, 8.-
o 1
- h i
i.
i j
tf I
t u
l n
1 J.
I e'
1 "p
3 Jt
t i
- u. -
j
=
a p-f
~
n-i p
i
- 1---
p n
7 A
,3 t=3e l
ot W
s 5
,i 9
t i
o L
rh G
w 5
,s 9
. ~.., -
i
?
=
e t
=
a E'
..{
m, i
n
[
v: v4
~ __.
.5
'i; o
o a
=
g 5
x o
h I
3
[a 3
=~
b 4.J p.
- a. -
5 3
13 l3
=
1 1
e 1
Cn 5
E S
55
'G u
u n-e
!.a
- e i
I
~ ll
,l
{-
b k!
- i. j l
1
?
n t
s-
$4 ) 3 88QO en4 m o
u.
a ts 3 4 44d3 J+siod 5 qdd 8veppoic agiun Hd i,2 quit ' Aggaggsqwo a
f
s
_f PIA!!T EVENTS,197h PEACH BU' TOM f3 (Numbers to correspo"id to those on plot.)
J Date Plant Events
-1 1/2 Reactor vessel internals.being installed 2;
1/J $
Condenser manually cleaned 3
1/29 Torus drained, manually cleaned and refilled. Two hydrostatic tests completed on reactor h
3/12
~ Pre-operation testing continues 5
3/28 Recirculation flush of HPCI and RCIC completed. Plant flushing program completed.
6 h/5-h/8 Operational hydrostatic test to 1000 psig 7
5/7 Completed testing of RHR, core spray and recirculating systems 8
5/21 0.E. work completed on feedwater spargers on inside of vessel 9
'6/18 Fuel inspection completed 10' 7/5 Start fuel loading' 11 7/31 Fuel loading completed 12
-8/7 Critical at h:30 a.m.
Shutdown 5:50 a.m.
Operational tests completed 13 8/13 Vessel head on. ~ Bolt tensiohing completed
-1h 8/15 Reactor vessel hydrostatic test completed
.15 8/26-2% power l 16 8/27 21 WP testing 9/3 Turbine synchronized at 9%. Tested to 18%.
18
_9/6 Reactor at pressure 19 9/23 Tripped due to MSIV malfunction.
20 10/16 Unit at rated pressure 21 11/15 100% power testing 22
-11/21 B-1 condenser leak. Reactor chemistry necessitates shutdown.
23 11/22 One tube plugged in B-1 water box 2h 12/9 -
Outage 25
~12 /12 C-1 condenser' leak 26 12/16 Staking of condenser 27
'12/19 82 tubes plugged in B-2 condenser 28_
12/23 Unit placed in con:norcial service
-~ ^
YEACH' BOTTOM WITS 2 + 3
.actorWatsrChemistrySummaryO Nota: There are many pages of deminerali::ed water analysis used for various ' systems on file at Peach Bottom. It can be stated that any fill water used for a' Class A
- rystem as defined by the Cleanliness Spec. -conformed to the requirements of that epsc ie. pH 5 6 - 8.0, conductivity 3 0, chlorides <l.o ppm.
I i
S' G
OO E-----
n-
,