ML20117C370
| ML20117C370 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/30/1996 |
| From: | Kepley L Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20117C309 | List: |
| References | |
| NUDOCS 9608270371 | |
| Download: ML20117C370 (6) | |
Text
4 DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 08/07/96 COMPLETED BY: L Kenley
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TELEPIlONE: (609) 339-1106 SIIMMARY OF CIIANGES TESTS, AND EXPERIMENTS FOR TIIE IIOPE CREEK GENERATING STATION MONTil JUIN 1996 The following items completed during June 1996 have been evaluated to determine:
1.
If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or 2.
If a possibility for an accident or malfunction of a difTerent type than any evaluated previously in the safety analysis report may be created; or 3.
If the margin of safety as defined in the basis for any technical specification is reduced.
The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant efIluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
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9608270371 960815 PDR ADOCK 05000354 R
Desien Channes Summary of Safety Evaluations 4llE-O'177: PACKAGE 2 IIEAT TRACE TUDE TO OFF GAS ROTAMETER AND RELOCATE ASSOCIATED TilERMOSTATS This design change relocated heat trace thermostats and extended heat trace circuit to the ofTgas rotameter to provide a more effective means of maintaining the required temperature and flow indication of the off gas radiation monitoring system to prevent condensation and enable the Radiation Monitoring System to function. UFSAR Figure 11.5.1, Sheet 2, will be modified to reflect the change.
The affected equipment is non-safety related. Relocating thermostats and adding a small i
section of heat trace will not increase the probability of a leak or failure of the gaseous radwaste system. This modification does not interface with any equipment that is important to safety.
Therefore, this design change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
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UFSAR Change Notices Summary of Safety Evaluations jlFSAR CIIANGE NOTICE, UFSAR SECTION 13.1, ORGANIZATIONAL e
STRUCTURE - RADIOI.OGICAL SAFETY ORGANIZATIONAL REPORTING STRUCTURE This change restructures the reporting requirements for Radiological Safety, encompassing the functional areas of emergency preparedness, radiation protection, chemistry, dosimetry and radiological instruments. The changes are administrative in nature, and do not change any parameters that could cause a malfunction. The changes do not relate to the operation of equipment important to safety. They do not relate to design, material, or construction standards, and do not affect system performance. They do not change the calculated radiation dose as a consequence of any accident, do not restrict access or impede actions on site, and do not relate to fission product barriers.
Therefore, this UFSAR change does not increase the probability or consequences of an accident previously described in the UFS AR and does not involve an Unreviewed Safety Question.
. UFSAR Cil ANGE NOTICE, UFSAR SECTION 10.2.3.6 INSERVICE INSPECTION This change extends the exercise test interval for the " critical" Bleeder Trip Valves (BTV) from weekly to once every 12 months (maximum). This change is in accordance with the General Electric (GE) methodology. The GE letter dated October 4,1995 states that performing " critical" BTV exercise test once every 12 months will satisfy the NRC's missile criteria. That criteria is based upon maintaining turbine missile probability below 10E-4 per turbine. year, as referenced in UFSAR section 3.5.1.3. The probability of turbine missiles will not be increased by the change. There are no radiological consequences associated with the change. There are no impacts to fission product barriers associated with the procedure change. The main turbine and BTV's are not defined as "important to safety" The BTV's function is to contain steam from the feedwater heaters from entering the turbine on generator load rejection or turbine trip. The change does not directly involve or interface with any equipment or system "important to safety" Therefore, this UFSAR change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
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UFSAR Channe Notices Summary of Safety Evaluations (Continued) l
'UFSAk CIIANGE NOTICE 94-38, INCORPORATION OF 10CFR20 CIIANGES The e
bulk of the changes are revised descriptions of administrative and programmatic features of t
the Radiation Protection Program, partially as a result of changes to 10CFR20, and including evaluation of area monitors on a quarterly rather than a monthly basis. The UFSAR is l
updated to describe the current radiation protection organization and consolidation of administrative procedures. There is no credible failure mode associated with these changes.
1 The changes do not relate to design, material, or construction standards, and do not affect system performance. They do not change monitoring setpoints or operational parameters, or i
affect human factors or access restrictions that would be in place during an accident situation.
The changes do not change the calculated radiation dose as a consequence of any accident, do not restrict access or impede actions on site, and do not relate to fission product barriers.
They do not affect requirements for the operation, maintenance, repair, or construction of equipment important to safety.
Therefore, this UFSAR changes does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
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- e Emergency Plan Changes Summary of Safety Evaluations EMERGENCY PI,AN SECTION 9 REVISION 5. EMERGENCY OPERATIONS FACIIJFY GENERATOR REPLACEMENT This change replaces the existing Emergency Operations Facility (EOF) natural gas fired generator with a new, larger capacity diesel generator. This change will significantly improve backup power and Heating, Ventilation, and Air Conditioning capabilities for the common EOF and related telecommunications equipment located within the Nuclear Training Center in Salem, New Jersey. No reduction in effectiveness of the Emergency Plan is expected as a result of this change. The new generator is expected to enhance the efTectiveness of the Emergency Plan due to its significantly larger load capacity and subsequent ability to handle more critical loads for a longer duration. An accident cannot be initiated by systems associated with the EOF; nor can the EOF increase the probability of an accident scenario. The EOF is not associated with any equipment important to safety previously evaluated in the Safety Analysis Report.
Therefore, this Emergency Plan change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
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Deficiency Reports Summary of Safety Evaluations DEFICIENCY REPORT USE-AS-IS DISPOSITION FOR TIIE "B" EDG STARTING l
AIR COMPRESSOR PRESSURE SWITCII 1KJPSIII,.6825C This Safety Evaluation i
supports the USE-AS-IS disposition for the 'B' EDG starting air compressor pressure switch, l
1KJPSliL-6825C. The normal switch setting is 380 psig to turn the compressor on and 425 l
psig to turn the compressor oft. However, during maintenance, the as found settings were 381 psig and 462 psig. The deadband of the switch is not adjustable. Therefore, the switch needs to be replaced, however, there is no switch available. The compressor is not safety related, however, the receivers that it supplies are safety related. This USE-AS-IS disposition will allow for continued operation of the 'B' EDG starting air compressor because the compressor has enough overpressure protection features to operate safely, and prevent damage to equipment or the compressor itself. There is a safety relief valve at the discharge of the compressor itself and a safety relief valve on each of the two air receivers The fit, form, function, and operation of the 'B' EDG and its starting air system will remain unaltered.
The failure of the switch only affects the ability of the compressor to start or stop. If the switch rendered the compressor not operational, station procedures are in place to crosstie another EDG compressor to the receivers. Loss of the compressor would not result in inoperability of the EDG as long as the receivers maintained sufricient air pressure. This l
USE-AS-IS disoosition will not affect the ability of the EDG to start.
Therefore, this USE-AS-IS disposition does not increase the probability or consequences of l
an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
b Temporary Modifications Summary of Safety Evaluations Procedures Summary of Safety Evaluations l
There were no changes in these categories implemented during June 1996.
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