Similar Documents at Hatch |
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Category:ANNUAL OPERATING REPORT
MONTHYEARHL-5581, Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 21997-12-31031 December 1997
Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 2
ML20141E3261996-12-31031 December 1996
Suppl Rept, Ei Hatch Nuclear Plant Annual Operating Rept for 1996,Plant Procedures
HL-5320, 1996 Annual Operating Rept for Edwin I Hatch Npp,Units 1 & 21996-12-31031 December 1996
1996 Annual Operating Rept for Edwin I Hatch Npp,Units 1 & 2
HL-5115, Ei Hatch Nuclear Plant - Units 1 & 2 Annual Operating Rept 19951995-12-31031 December 1995
Ei Hatch Nuclear Plant - Units 1 & 2 Annual Operating Rept 1995
HL-4787, 1994 Annual Operating Period1994-12-31031 December 1994
1994 Annual Operating Period
HL-4513, Ei Hatch Nuclear Plant Units 1 & 2 Annual Operating Rept 19931993-12-31031 December 1993
Ei Hatch Nuclear Plant Units 1 & 2 Annual Operating Rept 1993
HL-2074, Ei Hatch Nuclear Plant - Units 1 & 2 Annual Operating Rept, 19911991-12-31031 December 1991
Ei Hatch Nuclear Plant - Units 1 & 2 Annual Operating Rept, 1991
ML20029B3751990-12-31031 December 1990
Annual Operating Rept for 1990 for Hatch Units 1 & 2. W/910301 Ltr
ML20012A1331989-12-31031 December 1989
1989 Annual Operating Rept on Safety Relief Valve Challenges & Design Changes & Tests for 1989. W/900227 Ltr
ML20235M4441988-12-31031 December 1988
Annual Operating Rept for 1988 for Hatch Units 1 & 2. W/
ML20147E9211987-12-31031 December 1987
Annual Operating Rept for 1987
ML20207R8871986-12-31031 December 1986
Annual Operating Rept for 1986
ML20008E7171981-02-28028 February 1981
Annual Operating Repts for 1980.
ML19344D2691980-02-28028 February 1980
Interim Annual Operating Rept for 1979.
ML19289D3331979-02-23023 February 1979
Annual Operating Rept for 1978.
ML20112F8571977-12-31031 December 1977
Interim Annual Operating Rept for 1977
1997-12-31
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217D3061999-10-13013 October 1999
SER Accepting Licensee Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation
HL-5845, Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With1999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With
ML20217A1691999-09-22022 September 1999
Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers
ML20212A6641999-09-13013 September 1999
Safety Evaluation Authorizing Relief Request RR-V-16 for Third 10 Yr Interval Inservice Testing Program
HL-5836, Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With1999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With
ML20210J9631999-08-0202 August 1999
SER Finding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2
ML20210J9271999-08-0202 August 1999
SER Finds That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant,Susceptible to Pressure Locking or Thermal Binding
HL-5818, Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With
HL-5805, Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With
ML20207E7631999-06-0303 June 1999
Safety Evaluation Concluding That Licensee Proposed Alternative to Use Code Case N-509 Contained in RR-4 Provides Acceptable Level of Quality & Safety.Considers Rev 2 to RR-4 & RR-6 Acceptable
HL-5795, Monthly Operating Repts for May 1999 for Ehnp Units 1 & 2. with1999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Ehnp Units 1 & 2. with
ML20206G1691999-05-0404 May 1999
SER Approving Requirements of Istb 4.6.2(b) Pursuant to 10CFR50.55a(a)(3)(ii)
HL-5784, Monthly Operating Repts for Apr 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With
HL-5766, Monthly Operating Repts for Mar 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With
ML20207M1891999-03-11011 March 1999
SER Accepting Relief Request for Authorization of Alternative Reactor Pressure Vessel Exam for Circumferential Weld
HL-5755, Monthly Operating Repts for Feb 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With
ML20206P6981999-01-0707 January 1999
Ehnp Intake Structure Licensing Rept
HL-5726, Monthly Operating Repts for Dec 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With
ML20196J4931998-12-0707 December 1998
Safety Evaluation Accepting Proposed Alternatives in Relief Requests RR-V-12,RR-V-15,RR-P-15,RR-V-7,RR-V-12,RR-V-14 & RR-V-15
HL-5714, Monthly Operating Repts for Nov 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With
HL-5706, Monthly Operating Repts for Oct 1998 for Hatch Nuclear Plant Units 1 & 2.With1998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Hatch Nuclear Plant Units 1 & 2.With
ML20155B6121998-10-28028 October 1998
Safety Evaluation of TR SNCH-9501, BWR Steady State & Transient Analysis Methods Benchmarking Topical Rept. Rept Acceptable
HL-5691, Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With
ML20153G2481998-09-24024 September 1998
SE Concluding That Licensee Implementation Program to Resolve USI A-46 at Plant Adequately Addressed Purpose of 10CFR50.54(f) Request
ML20239A2531998-09-0303 September 1998
SER Accepting Licensee Request for Relief Numbers RR-17 & RR-18 for Edwin I Hatch Nuclear Plant,Units 1 & 2.Technical Ltr Rept on Third 10-year Interval ISI Request for Reliefs for Plant,Units 1 & 2 Encl
HL-5675, Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 2
ML20238F7131998-08-31031 August 1998
9,change 2 to QAP 1.0, Organization
HL-5667, Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 2
HL-5657, Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures1998-07-30030 July 1998
Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures
ML20236W3441998-07-30030 July 1998
Safety Evaluation Accepting Relief Requests for Second 10-yr ISI for Plant,Units 1 & 2
ML20236V5191998-07-28028 July 1998
Safety Evaluation Accepting Proposed License Amend Power Uprate Review
ML20236N6751998-07-0909 July 1998
Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps
ML20236L1821998-07-0707 July 1998
Safety Evaluation Accepting 980428 Proposed Alternative to ASME Boiler & Pressure Vessel Code,Section Xi,Repair & Replacement Requirements Under 10CFR50.55a(a)(3)
HL-5653, Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 2
HL-5640, Monthly Operating Repts for May 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Ei Hatch Nuclear Plant,Units 1 & 2
ML20248B8651998-05-15015 May 1998
Quadrennial Simulator Certification Rept
HL-5628, Monthly Operating Repts for Apr 1998 for Ei Hatch Nuclear Plant1998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Ei Hatch Nuclear Plant
HL-5604, Monthly Operating Repts for Mar 1998 for Edwin I Hatch Nuclear Plant,Units 1 & 21998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for Edwin I Hatch Nuclear Plant,Units 1 & 2
ML20216B2711998-02-28028 February 1998
Extended Power Uprate Safety Analysis Rept for Ei Hatch Plant,Units 1 & 2
HL-5585, Monthly Operating Repts for Feb 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-02-28028 February 1998
Monthly Operating Repts for Feb 1998 for Ei Hatch Nuclear Plant,Units 1 & 2
HL-5571, Monthly Operating Repts for Jan 1998 for Edwin I Hatch Nuclear Plant,Unit 11998-01-31031 January 1998
Monthly Operating Repts for Jan 1998 for Edwin I Hatch Nuclear Plant,Unit 1
HL-5551, Monthly Operating Repts for Dec 1997 for Ei Hatch Nuclear Plant,Units 1 & 21997-12-31031 December 1997
Monthly Operating Repts for Dec 1997 for Ei Hatch Nuclear Plant,Units 1 & 2
ML20199B0561997-12-31031 December 1997
Rev 0 GE-NE-B13-01869-122, Jet Pump Riser Weld Flaw Evaluation Handbook for Hatch Unit 1
HL-5581, Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 21997-12-31031 December 1997
Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 2
HL-5533, Monthly Operating Repts for Nov 1997 for Ei Hatch Nuclear Plant,Units 1 & 21997-11-30030 November 1997
Monthly Operating Repts for Nov 1997 for Ei Hatch Nuclear Plant,Units 1 & 2
HL-5514, Monthly Operating Repts for Oct 1997 for Edwin I Hatch Nuclear Plant,Units 1 & 21997-10-31031 October 1997
Monthly Operating Repts for Oct 1997 for Edwin I Hatch Nuclear Plant,Units 1 & 2
ML20212A1981997-10-16016 October 1997
Safety Evaluation Denying Licensee Request for Relief from Implementation of 10CFR50.55a Requirements Re Use of 1992 Edition of ASME Code Section XI for ISI of Containments
ML20211M6491997-10-0808 October 1997
Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted
ML20211H5311997-10-0101 October 1997
Rev 2 to Unit 1,Cycle 17 Colr
ML20211H5251997-10-0101 October 1997
Rev 3 to Unit 1,Cycle 17 Colr
1999-09-30
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t Enclosure Edwin L Hatch Nuclear Plant Annual Operating Report for 1996 Supplemental Report Plant Procedures 42SV-C71-001-lS ,
r Revision 0 of this LSFT was written to implement Technical Specification Improvement - i Program (TSIP) surveillance requirement, SR 3.3.1.1.15. This LSFT demonstrates the operability of various RPS trip logic channels. This procedure will be performed while '
the Unit is in the Shutdown or Refuel modes, with no CRD work or fuel movement activities in progress, and all clearances that affect the performance of the procedure will be released.
The performance of the procedure has been evaluated to not increase the probability or consequences of occurrence of an accident or malfunction previously evaluated in the FSAR, or create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR, and no margin of safety as defined in the basis for any l Technical Specification is reduced by this activity.
52PM-M>E L-006-1S Revision 0 provides instructions for removing the breaker from Frame 1B of Bus IR22-S016 while maintaining power to its respective load by installing a temporary feed from Frame 3T of the same Bus to the load side of Frame 1B. The plant will be restored to design configuration before procedure completion.
The performance of the procedure has been evaluated to not increase the probability or ,
consequences of occurrence of an accident or malfunction previously evaluated in the FSAR, or create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR, and no margin of safety as defined in the basis for any Technical Specification is reduced by this activity.
34SO-T47-001-2S Revision 2 of this procedure allows operation of the drywell cooling fans,2T47-B010A&B, simultaneously to maintain drywell cooling average temperature < 135'F. ,
HL-5383 - E-1 9705200403 970505 I .
i PDR ADOCK 050003216 R PDR L
l Enclosure 1996 Annual Operating Report flant Procedures The performance of the procedure has been evaluated to not increase the probability or consequences of occurrence of an accident or malfunction previously evaluated in the FSAR, or create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR, and no margin of safety as defined in the basis for any Technical Specification is reduced by this activity.
34SP-110495-DC-1-2S
- - This procedure checks the interlocks between valves in the Residual Heat Removal (RilR) system which have the potential to establish a drain path from the reactor to the torus. The prerequisites for this procedure are designed to prevent an actual draindown event and to maintain compliance with Technical Specifications. This procedure does not involve a change to plant design and does not involve the installation ofjumpers or the opening oflinks. The purpose of the procedure is to ensure that valve interlocks function as designed.
The performance of the procedure has been evaluated to not increase the probability or consequences of occurrence of an accident or malfunction previously evaluated in the FSAR, or create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR, and no margin of safety as defined in the basis for any Technical Specification is reduced by this activity.
4 42SV-P41-001-lS Revision 1 deletes the automatic isolation function on high flow of valves 1P41-F310A-D in accordance with Design Change Request (DCR) 1H93-049. Please see the summary of the evaluation for this DCR in the Unit 2 Design Change Requests section of the Annual Operating Report submitted on February 28,1997.
52PM-MEL-001-2S Revision 0 of this procedure provides instructions for removing the breaker from Frame 3B of Bus 2R22-S016 while maintaining power to its respective downstream load. This is a temporary change to the plant and the plant will be restored to design configuration before procedure completion.
The performance of the procedure has been evaluated to not increase the probability or
- consequences of occurrence of an accident or malfunction previously evaluated in the FSAR, or create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR, and no margin of safety as defined in the basis for any
. . Technical Specification is reduced by this activity.
IIL-5383 E-2
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Enclosure 1996 Annual Operating Report
] Plant P'rocedures -
- 42SP-112095-PI-1-2S ;
. Revision 0 of this procedure allows continued enforcement of preloaded control rod patterns beyond the low power setpoint by blocking the signal from 2C32-K608 and . !
2C32-K618, which normally send a signal to the NUMAC Rod Worth Minimizer (RWM) 4 indicating that the plant power level is greater than the setpoint (based on feed flow and ;
steam flow). This action in no way impacts the function of the RWM to enforce the control rod pattern to maintain BPWS requirements; in fact, the use of this procedure to continue the enforcement beyond the low power setpoint (below which the enforcement is required due to the analyzed Rod Drop Accident) is conservative and will serve as an 7
- operator aid for the prevention of control rod movement errors.
?
The performance of the procedure has been evaluated to not increase the probability or i l consequences'of occurrence of an accident or malfunction previously evaluated in the FSAR, or create the possibility.of an accide'nt or malfunction of a different type than any ;
previously evaluated in the FSAR, and no margin of safety as dermed in the basis for any :
y Technical Specification is reduced by this activity.
[ 03SP-022296-SA-1-lS Revision 0 of this procedure was for the performance of Test or Experiment Request j F (TER)96-001. The purpose of the TER was to determine the capability, or capacity, of !
one Reactor Feed Pump (RFP). The test was to show if one RFP, in conjunction with a l Reactor Recirculation System run back to the Number 2 Speed Limiter could maintain ;
reactor vessel water level above the low water level scram setpoint in the event of a trip t
of one of the two operating Reactor Feed Pump Turbines (RFPT) at power uprate conditions. l l The performance of the procedure has been evaluated to not increase the probability or ,
consequences of occurrence of an accident or malfunction previously evaluated in the FSAR, or create the possibility of an accident or malfunction of a different type than any l previously evaluated in the FSAR, and no margin of safety as defined in the basis for any Technical Specification is reduced by this activity.
F !
!I 34SO-R22-003-IS 1 Revision 0 of this procedure provides instructions for de-energizing and electrically ,
' isolating 4160 VAC Bus 1C from the system grid so that preventative maintenance can be performed on the Bus. Performance of this procedure is only allowed when the plant is c
in cold shutdown or during refueling outages.
7 i - IIL-5383 E-3 l
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?'- -* Enclosure j
{'* 1996 Annual Operating Report Plant Irrocedures ;
l ,
1 The performance of the procedure has been evaluated to not increase the probability or
. consequences of occurrence of an accident or malfunction previous ly eva luated in the FSAR, or create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR, and no margin of safety as defined in the basis for any Technical Specification is reduced by this activity. ;
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i 31GO-INS-001-0S i
Revision 8' of this procedure incorporates the Third Ten Year Interval IST program i
, requirements. The changes include new requirenants as directed in the ASME OM
. Code. The revision changes the method of determining the allowable stroke time of ;
o motor operated valves tested per the IST program. j The performance of the procedure has been evaluated to not increase the probability or ;
- consequences of occurrence of an accident or malfunction previously evaluated in the 1 4 FSAR, or create the possibility of an accident or malfunction of a different type than any j i previously evaluated in the FSAR, and no margin of safety as defined in the basis for any l
- Technical Specification is reduced by this activity. l 4 i 42SV-IU2-009-0S :
- I i Revision 1 of this procedure resulted from Technical Specifications Amendment 195 and ,
l added the remaining Unit I safety-related batteries, IR42-S001 A/B & 1R42-S002A/C, to :
0 the procedure and combined the service and performance tests into one procedure. !
1 The performance of the procedure has been evaluated to not increase the probability or
- consequences of occurrence of an accident or malfunction previously evaluated in the !
FSAR, or create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR, and no margin of safety as defined in the basis for any l Technical Specification is reduced by this activity.
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