ML20203B684

Monthly Operating Rept for Dec 1997 & Jan 1998 for Hope Creek Generation Station,Unit 1,summary of Changes,Tests & Experiments

ML20203B684
Person / Time
Site:	Hope Creek
Issue date:	12/31/1997
From:	Ritzman R Public Service Enterprise Group
To:
Shared Package
ML20203B670	List: LR-N980027, Forwards Monthly Operating Rept for Jan 1998 for Hope Creek Generation Station,Unit 1.Summary of Changes,Tests & Experiments Implemented During Dec 1997 & Jan 1998,encl,per Requirements of 10CFR50.59(b) ML20203B674 ML20203B684
References
NUDOCS 9802240387
Download: ML20203B684 (6)

Text

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I DOCKET NO.: 50-354 U!JI T : ljope Creek DATE: 12/11/97 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445 SXt@LARY OF CHMLQERuT_EATLAUp EXEERIMENTS EQB_IliluiME._SRREIL9EIM RATlH9_.1TATI ON MONTH DI MMDER 1997 and._Lang ry 1998 The following items completed during December 1997 and January 1998 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 different 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 effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

D_eJ!.Lgp Citangp_s S3gnmarv .qf Saf ety Evaluations 4EC-3449, Pkg. 6, Replace Selected Carbon Steel Piping and Fittings with Chromium Alloy Due to Flow Accelerated Corrosion.

This design change addressed various fittings and pipe that need to be replaced due to Flow Accelerated Corrosion. The following systems are covered by the safety evaluation associated with this design change: Feedwater, Condensate, Seal Steam, Moisture Separator Drains, Plant Heating, Main Steam, Extraction Steam, Heater Drains, Condensate Air Removal, and Reactor Feed Pump Turbine Steam. The design change includes replacing carbon steel piping and fittings with chrome moly alloy steel material of equal or heavier wall thickness.

9002240397 980215 PDR ADOCK 05000354 R PDR

, )4 This design change did not increase'the probability or  ;

consequences of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce ,

the margin of safety for any Technical Specifications, i Therefore, there are no unreviewed safety questions associated  !

with this design change.

Tomocrary Modifications Summary of Safety Ey_glug_t;1 gag There were no changes in this category implemented during >

December 1997 or January 1998.

Procedures Summary _of_ Safety EvaluatioD1 ,

NC.DE-AP.ZZ-0004(Q), Rev. 5, Design Drawings. This procedure revision included responsibility changes in the process for controlling engineering design drawings. This procedure revision allowed the task of transferring approved design change information-to be performed by a drafter or a designer.

Previously, this work was performed only by designers. This procedure revision also includes supervisory title changes.  ;

The changes included in this procedure are considered to be administrative in nature. Additionally, a designer will continue to peer review the changes to the engineering drawings.

Therefore, this procedure revision did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications. Therefore, there are no unreviewed safety questions associated with this procedure revision.

UfSAB_ chance Notices Summary of Safety EvaluatigJ13 CN M97-064, NBU Organization Changes, Consolidation of Manger -  !

Emergency Preparedness Position with the Managers - Corrective Action and Instructional Technology. This UFSAR change notice consolidates the Manager - Emergency Preparedness position with the Managers - Corrective Action and Instructional Technology.

The-new title is Manager - Corrective Action, Emergency Preparedness, and Instructional Technology. The manager reports to the Director - Quality,-Nuclear Training, and Emergency Preparedness. . This change also transfers quality services functions from the Manager - Corrective Actions to the Director -

Quality, Nuclear Training, and Emergency Preparedness, 2 a

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t l There is no reduction in the level of quality asuuran - u .<

technical support as a result of this change. Thes' te l urganizational changes only, and do not affect anv ' :u > <;9e  !

l systems, or components as d Jeribed in the SAR. 'F V e > s , '

. I j UFSAR change did not increase the probability or t. .astaf e1 ena .

a malfunction of equipment important to safety, cre)?0 cht i possibility of an accident or malfunction of a diffucgg 5ype ,

than previously evaluated in the SAR, or reduce thu e.argin of l

safety for any Technical Specifications. Therefore, there are no i i unreviewed safety questions associated with this UFSAR-change.

i CN H97-068, Safety Auxiliaries Cooling System T.asponse to a Turbine Auxiliaries Cooling System Pipe Break in a Design Basis 4

Earthquake. This UFSAR change notice was initiated to l

l incorporate the results of a calculation into the UFSAR. The calculation was performed to evaluate the Safety Auxiliaries  ;

Cool.ing System (SACS) response to a Turbine Auxiliaries cooling

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System (TACS) pipe break during a design basis earthquake. The '

calculation was required because the SACS to TACS isolation

, valves are not seismically qualified.

4 The-calculation determined that the SACS to TACS supply valves

would automatically isolate and would support the safe shutdown

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of the plant during design basis earthquake scenarios. This UFSAR change did not increase the probability or consequences of

, a malfunction of equipment important to safety, create the  !

possibility of an accident or malfunction of a different type 1 than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications. Therefore, there are no  ;

unreviewed safety questions associated with this UFSAR change.

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CN H97-083, Safety and Turbine Auxiliaries cooling System -

Required Flow Rates and Heat Loads. This UFSAR change notice was initiated to update the Safety and Turbine Auxiliaries Cooling i system flow rates and heat loada based on the results of a i calculation.

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. The calculation revision analyzed the minimum requiled flow ra'.es delivered to the Safety Auxiliaries Cooling System (SACS) '

cpmponenets to ensure that they remove their as-built design heat loads and does not make any changes to system equipment or  !

operation.

Therefore, this UFSAR change did not increase the probability or consequences of a malfunction of equipment j~ important to safety, create-the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical ,

Specifications. Therefore, there are no unreviewed safety questions associated with this UFSAR change. '

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.CN M97-004, Pcat-Scram Mechanical Vacuum Pump Operation. This UFSnR change notice revised the process for placing the '

mechanical vacuum pumps in operation after a reactor scram. Tne  ;

change notice clarified the limitations for using the mechanical  !

vacuum pumps anu achieved consistency between the licensing basis ,

and the operating procedures.

An engineering evaluation was also performed in conjunction with ,

this change notice. The engineering evaluation concluded that  :

there would be no increase in radiological consequences or in off-site dose releases. This UFSAR change did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident or ,

malfunction of a different type than previously evaluated in the  ;

SAR, or reduce the margin of safety for any Technical  ;

Specifications. Therefore, there are no unreviewed safety  ;

questions associated with this UFSAR change. t CN M90-001, Condensate and Reactor Coolant System Chemistry Silica Limit. This UFSAR change notice raised the condensate and  ;

reactor coolant system silica limit from 20 ppb to 500 ppb. This <

change is consistent with current EPRI guidance for BWR Water e Chemistry. This UFSAR change did not increase the probability or consequences-of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce l the margin of safety for any Technical Specifications.  !

Therefore, there are no unreviewed safety questions associated ,

with this UFSAR change.

CN M98-005, Nuclear Business Unit Organization Change. This change notice established a new position, the Executive Vice  ;

President - Nuclear Business Unit. The individual holding this s position assumes the duties and responsibilities of the Chief Nuclear Officer / President - Nuclear Business Unit in his absence.

This UFSAR change notice is organizational only and does not '

impact any system, structure, or component. This UFSAR change .

sdi d not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an i accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any .

Technical Specifications. Therefore, there are no unreviewed safety questions associated with this UFSAR change. l

-CN H98-006, Monthly Operating Report Contents. This change notice incorporated Generic Letter 97-02, was written to inform licensees that-the NRC was requesting the submittal of less .'

information in the monthly operating report. The Generic Letter allows the use of guidance provided in the Generic Letter instead of providing the information requested by Reg Guide 1.16. This 1 proposal-allowed Hope Creek to comply with Generic Letter 97-02

~instead-of Regulatory Guide 1.16.

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This proposal discusses reporting requirements only and does not impact any system, structure, or component. This UFSAR change did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident os malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications. Therefore, there are no unreviewed safety questions associated with this UFSAR change.

Reliciency Rpports Enamary of Safety Evaluations 971009231, Ultrasonic Test Scanner Bearing cap - Potential Lost Part. This deficiency report was written to document an ultrasonic test scanner bearing cap that was postulated to have fallen into the reactor, The following safety and operational concerns for the potential migration patterns in the core were addressed in the safety evaluation associated with this deficiency reports potential for control rod interference, potential for corrosion or chemical reaction with other reactor materials, potential for interference with Reactor Water cleanup (RWCU)/ Residual Heat Removal (RHR) isolation valvea, potential for fretting of fuel cladding, potential for impact to recirculation system performance, potential for blockage of vessel bottom head drain, and potential for damage to RWCU/RHR pumps.

The safety evaluation determined that the ultrasonic test scanner bearing cap would not affect safety related plant responses, including the ability to scram the control rods. Therefore, this deficiency report did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications.

Therefore, there are no unreviewed safety questions associated with this deficiency report.

971016131, Jet Pump Sensing Line Lower Bracket Clamp Repair 2 This deficiency report was written to document weld indications on three Jet Pump Sensing Line lower brackets. No cracks have been observed on the sensing lines. The safety evaluation associated with this deficiency report justified operation with a repair to the brackets. The repair consisted of clamping the sensing lines to the lower support-brackets in the original welded position, essentially restoring the lines to their original structural configuration.

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The addition of the clamps does not affect jet pump structural integrity and does not change the blowdown path during a loss of coolant accident. The sensing line is not safety related. The clamps are passive devices that restore the structural integrity of the sensing line attachments. Therefore, this deficiency report did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility ot an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications. Therefore, there are no unreviewed safety questions associated with this deficiency report.

971127121, Adjustment to Reactor Water Cleanup Leak Detection Betpoint. This deficiency report was written to document a new setpoint and allowable value for the Reactor Water Cleanup (RWCU) differential flow trip. A new design calculation was performed that required a lowering of the setpoint and the allowable value.

The calculation was performed to address the impact of a RWCU flow orifice being installed backwards.

No equipment was modified or introduced as a result of this deficiency report. This deficiency report did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical specifications. Therefore, there are no unreviewed safety questions associated with this deficiency report.

Qther Summary of sal 9tv Evaluation There were no changes in this category implemented during December 1997 or January 1998.

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