IR 05000388/1985003
| ML17139D028 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/23/1985 |
| From: | Bettenhausen L, Florek D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17139D027 | List: |
| References | |
| 50-388-85-03, 50-388-85-3, NUDOCS 8504020301 | |
| Download: ML17139D028 (10) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-388/85-03 Docket No.
50-388 License No.
NPF-22 Priority Category B
Licensee:
Penns lvania Power and Li ht Com an 2 North Ninth Street Allentown Penns lvania 18101 Facility Name:
Sus uehanna Steam Electric Station Unit 2 Inspection At:
Salem Townshi Penns lvania Inspection Conducted:
Januar 24-30 1985 Inspectors:
D.
orek, Lead Reactor Engineer da e
Approved by:
L. H.
B ttenhausen, Chief Test Programs Section, ORS date Ins ection Summar
Ins ection on Januar 24-30 1985 Re ort No. 50-388/85-03
2
¹2 T
program during test condition TC-6, including test results evaluation and witnessing the Load Reject'rom High power, gA Interface and tours of the facility.
The inspection involved
hours by one region based inspector.
Results:
No violations were identified.
e oosomosos soosos PDR ADQCK 05000388
PDR DETAILS 1.
Persons Contacted Penns lvania Power and Li ht Com an H. Keiser, Plant Superintendent R. Kreider, QA Engineer T. Nork, Startup Coordinator
- R. Prego, Operations QA Supervisor
~R. Sheranko, Startup Test Group Supervisor D. Thompson, Assistant Plant Superintendent
"J. Todd, Compliance Engineer J. Zentz, Startup Test Engineer U.S. Nuclear Re viator Commission R. Jacobs, Senior Resident Inspector L. Plisco, Resident Inspector
~Denotes those present at exit meeting on January 30, 1985.
The inspector also contacted several other licensee personnel in the course of the inspection including shift supervisors, reactor operators and startup test engineers.
2.
Startu Test Pro ram References:
~
Susquehanna Steam Electric Station (SSES)
Final Safety Analysis Report
~
SSES Safety Evaluation Report and Supplements 1,2,3,4and5
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Regulatory Guide 1.68 "Initial Test Programs for Water Cooled Reactor Power Plants"
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SSES Startup Test Schedule
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AD-TY-460 Startup Test Administrative Procedure 2. 1 Test Results Evaluation
~Sco e
The 11 completed startup tests listed in on the findings section were reviewed to assess that:
Each was approved in accordance with administrative procedures; Test changes were annotated and completed if appropriate; Basic test objectives were met; Changes and test exceptions were noted; Test exceptions were resolved and accepted by management; Retests were completed if required; System or process changes necessitated by a test deficiency were properly documented and reviewed; Proper reporting of deficiencies; Data sheets were completed; Data was within tolerances; Test steps and data sheets were properly signed and dated; Engineering evaluation of test data; Test results were compared with established acceptance criteria; Documented review and acceptance of tests results; Offsite review committee and followup if audited; QA or independent review of tests results; and
~Findin s
Test results have been approved by appropriate management.
Except as noted below, the attributes identified above were found to be properly implemented in the completed startup test procedures.
A summary of each test follows.
"Shutdown Cooling Mode", Revision 3, Test Implemented January 6,
1985.
This test demonstrated the B loop and combined A and B loop performance.
One test exception was identified due to RHR flow being higher than specified in the test procedure.
RHR cooling was maintained and achieved 63'F cool down temperature differenc "~Co densate Storage Tank Injections", Revision 2, Test imple-mented January 18, 1985.
The Level
acceptance criteria were satisfied.
HPCI reached rated flow in approximately
seconds and did not trip.
One test exception was identified due to the inoperability of the HPCI suction pressure instrumentation.
QA and management review is in process.
"Rated Pressure Auto Quick Starts to Vessel", Revision 2, Test implemented January 24, 1985.
All acceptance criteria were satisfied.
HPCI reached rated flow in 21.5 seconds, did not isolate and had speed peaks of 3,468 and 4,060 rpm, with limits of less than 4,543 and 4,336 rpm respectively.
Management review was in process.
"Feedwater Pump Trip", Revision 1, Test Implemented January 27, 1985.
Feedwater pump B
was tripped.
The two remaining pumps maintained level following the recirculation pump runback.
The margin to scram from low level was 15.5 inches thus satisfying the acceptance criteria of at least three inch margin.
"Verification of Recirculation MG Set High Speed Stops",
Revision 1, Test Implemented January 22, 1985.
This test verified the electrical and mechanical recirculation pump high speed stops for the A recirculation pump after work performed in the Unit 2 scheduled outage.
The electrical stop was set at 100.4%
rated core flow and the mechanical stop was set at 103. 1%
rated core flow.
Management review was in process.
"Containment Temperatures at Steady State",
Revision 4, Test Implemented January 14, 1985.
All test criteria were satisfied except that the shield wall temperature was less than 100 F (93'F)
and the under vessel area temperature was less than 100'F (90'F).
Management and QA review is in'rocess.
"Recirculation System Flow Calibration", Revision 2, Test implemented January 13, 1985.
The test was satisfactorily conducted.
However, one test ex-ception was identified due to process computer indication being greater than the calculated value.
This test exception was similar to that identified ear lier and will be resolved as part of the test exception report.
Management review is in process.
QA review is in proces ST-35.1
"Recirculation System Flow Calibration", Revision 2, Test implemented September 27, 1984.
One test exception was identified (TER-134)
due to the computer indicated value exceeded the calculated value.
The test was repeated after the precommercial outage.
"Gaseous Radwaste System Performance",
Revision 0, Test imple-mented January 14, 1985.
Dilution steam flow was 9400 Lb/Hr with a
required value of greater than 8000 Lb/Hr.
One test exception was identified for high guard bed inlet flow and high guard bed inlet dewpoint.
Management and gA review is in process.
ST-39. 1
"Main Steam Piping Vibratory Response During Turbine Stop Valve (TSV) Closure",
Revision 3, Test implemented October 27, 1984.
All acceptance criteria were satisfied.
One TER was identified for an inoperable computer point.
An adequate sensor was utilized to assess the data.
"Recirculation Piping Vibratory Response During Pump Trips and Restarts",
Revision 2, Test implemented January 27, 1985.
Test was performed for the recirculation pump trip and restart.
All acceptance criteria were met.
Management and gA review is in process.
2.3 Test Witnessin Startup test ST-27.2,
"High Power Load Rejection",
was witnessed to assess:
Procedure of appropriate revision is available and in use by all crew members; minimum crew requirements were met; prerequisites and initial conditions were met; test equipment was calibrated and operable per procedure; procedures were technically correct; crew actions were correct and timely; coordination was adequate; and, there was a quick summary analysis of all data collected subsequent to test.
The inspector also reviewed the licensee prediction of the plant transient described in PLI-36162,
"ST-27.2 Pretest Prediction Using RETRAN-02", dated October 22, 1984.
~Findin s
ST-27.2 was performed on January 29, 1985, at 0054 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />.
Plant initial conditions included reactor power at 96%, total core flow of 97. 1 MLb/Hr, reactor dome pressure of 988 psig and reactor water level of 36 inche The inspector verified that prior to the test, briefings were conducted for the operations and testing personnel including a
discussion of potential problems that could occur.
An official test copy of the procedure was utilized.
Adequate crew was available, including operators who were being upgraded and in the licensee training program, the prerequisites and initial conditions were met, including the data logging computer GETARS, the procedures were ade-quate, and were properly implemented.
The licensee had technical personnel on site to assess the plant response in addition to the startup test requirements in order to permit a rapid plant restart.
The inspector observed startup test personnel assessing the data collected following the test.
The inspector review of the test data indicated that the stop valve and control valve response and recircu-lation pump trip logic response satisfied the test acceptance criteria.
The licensee review of the recirculation pump coast down data indicated that the recirculation pump coastdown did not satisfy the Level 1 criteria.
The licensee corrective action was to take the MCPR penalty for an inoperable recirculation pump trip as was done previously for Unit 1.
The licensee also reported a main steam line hanger fai lure that had occurred since the last time the hanger was reviewed during the performance of ST-25.3 MSIV Full Closure.
A test exception was identified.
The inspector will review the complete data package in a subsequent inspection.
2.4 Overall Startu Pro ram With the performance of ST-27.2 the licensee has three remaining startup tests to complete.
These are:
~
HPCI testing at 150 psig CST to CST
~
Turbine valve testing at rated power
~
Inerting the drywell These will be conducted following the restart of the plant.
The inspector also verified management approval of ST-23.6 and the justification for "use as is" included in TER-119, 120, and 127.
These items were identified in previous inspections.
4.
ualit Assurance Interfaces guality assurance inspectors were observed to witness performance of ST-27.2.
guality Assurance review of startup test results was in process for recent tests performed.
guality assurance review of all test results is required by the administrative procedures.
The Nuclear Safety Assessment Group was observed to also witness performance of ST-2 r
5.
Tour of the Faci lit The inspector made a
tour of the facility during the course of the inspection including the turbine building, control structure and control room.
No unacceptable conditions were noted.
6.
Exit Interview At the conclusion of the site inspection on January 30, 1985 an exit meeting was conducted with the licensee's senior site representatives (denoted in paragraph 1).
The findings were identified and discussed.
At no time during the inspection was written material provided to the licensee by the inspector.
The licensee indicated that no proprietary information was contained in the scope of this inspection.