IR 05000351/1986043
| ML20210T203 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek, 05000351  |
| Issue date: | 09/22/1986 |
| From: | Briggs L, Wink L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20210T190 | List: |
| References | |
| 50-354-86-43, NUDOCS 8610080337 | |
| Download: ML20210T203 (9) | |
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l U.S. NUCLEAR REGULATORY COMMISSION
REGION I
l Report No.
50-354/86-43 Docket No.
50-354 License No.
NPF-57 Licensee: Public Service Electric and Gas Company 80 Park Plaza Newark, New Jersey 07101 Facility Name: Hope Creek Generating Station, Unit 1 Inspection At: Hancocks Bridge, New Jersey Inspection Conducted:
September 2-5, 1986 Inspectors:
b L. Wink, Reactor Engineer
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Approved by:
f!#E/8h
. Briggs /g hief, Test Program Section, date
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OB, DRS Inspection Summary:
Inspection of September 2-5, 1986 (Inspection Report No. 50-354/86-43)
Areas Inspected:
Routine, unannounced inspection of the overall power ascen-sion test program including procedure reviews and test results evaluation, independent measurements and verifications and QA/QC interface.
Results: No violations were identified.
NOTE:
For acronyms not defined, refer to NUREG-0544, " Handbook of Acronyms and Initialisms."
8610090337 860930 PDR ADOCK 05000354 G
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DETAILS 1.0 Persons Contacted Public Service Electric and Gas Company (PSE&G)
- R. Beckwith, Station Licensing Engineer
- G. Connor, Operations Manager P. Dempsey, Shift Test Coordinator
- M. Farschon, Power Ascension Manager B. Forward, Power Ascension Administrative Coordinator
- A. Giardino, Manager-Station Quality Assurance (QA)
- R.
Griffith, Principal Engineer-QA T. Hersum, Power Ascension Engineer D. Hosmer, Lead Shift Test Coordinator
- P. Krishna, Assistant to General Manager-HC0
- D. LaMastra, Lead Engineer-Hope Creek Systems R. Salvesen, General Manager, Hope Creek Operations W. Schell, Power Ascension Technical Director W. Thomas, Shift Test Coordinator L. Zull, Lead Startup Test, Design and Analysis Engineer U. S. Nuclear Regulatory Commission D. Allsopp, Resident Inspector
- R. Borchardt, Senior Resident Inspector
- Denotes those present at the exit meeting on September 5, 1986.
The inspector also contacted other members of the licensee's staff in-cluding Senior Nuclear Shift Supervisors, Reactor Operators, Test Engineers and members of the Technical staff.
2.0 Power Ascension Test Program (PATP)
2.1 References Regulatory Guide 1.68, Revision 2, August 1978, " Initial Test
Programs for Water-Cooled Nuclear Power Plants" ANSI N18.7-1976, " Administrative Controls and Quality Assurance
for the Operational Phase of Nuclear Power Plants" Hope Creek Generating Station (HCGS) Technical Specifications,
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Revision 0, April 11, 1986 HCGS Final Safety Analysis Report (FSAR), Chapter 14, " Initial
Test Program"
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I HCGS Safety Evaluation Report (SER), Chapter 14, " Initial Test Program"
Station Administrative Procedure, SA-AP.ZZ-036, Revision 3,
" Phase III Startup Test Program"
Specification NEB 0 23A4137, Revision 0, " Hope Creek Startup Test Specification"
HCGS Power Ascension Test Matrix, Revision 7 2.2 Overall Power Ascension Test Program Discussion The inspector held discussions with the Power Ascension Manager, Power Ascension Technical Director and other members of the PATP staff to assess the overall status of the test program and test re-sults review. The licensee completed Test Condition 1 (10% - 20%
rated power) on August 23, 1986 with the performance of TE-SU.SV-281, Shutdown from Outside the Control Room, and entered a 6 day outage.
The licensee completed the Plateau Review of Test Condition One on August 27 (see paragraph 2.4 for discussion). Test Condition 2 (25%
- 45% rated power) officially began on August 29 but testing was de-layed due to troubleshooting of a field ground in the Main Generator.
- The Main Generator was brought back on-line on September 5 and test-ing recommenced.
2.3 Power Ascension Test Procedure Review Scope The Power Ascension Test procedures listed in Attachment A were re-viewed for their conformance to the requirements and guidelines of the references in paragraph 2.1 and for the attributes previously defined in Inspection Report 50-354/86-03.
Discussion TE-SU.ZZ-005. The Test Plateau Matrix for Test Condition Two was reviewed to verify that, in addition to the testing previously ident-ified for this test condition, tests deferred from Test Condition One were included.
TE-SU.AB-252. During the review of the analysis section of the MSIV Full Isolation Test the inspector had a question concerning the im-pact of the SRV Lo-Lo Set Function on the prediction of the antici-pated pressure rise following the trip.
The inspector held discus-sions with the Power Ascension Manager, Power Ascension Technical
Director, Lead Startup Test, Design and Analysis Engineer and other
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members of the PATP staff to determine if the SRV Lo-Lo Set function had been correctly modeled in the Transient Safety Analysis Design Report (TSADR). The inspector found that the documentation contained in the TSADR was not sufficiently detailed to resolve this concern.
The licensee's representative contacted the General Electric Engineers in San Jose responsible for the TSADR and received pre-liminary indication that the SRV Lo-Lo Set Function had been included in the computer models used to generate the pressure rise predict-ions.
Pending receipt on site of supporting documentation and review by the NRC this item will be considered unresolved (354/86-43-01).
This concern also applies to power scension test TE-SU.CH-273, Full Power Turbine Trip Test.
Findings Within the scope of the review, no violations were identified. One unresolved item was identified.
2.4 Power Ascension Test Results Evaluation Scope The power Ascension test results listed in Attachment B were eval-uated for the attributes identified in Inspection Report 50-354/.
86-24. All test results evaluated had received a detailed review by an independent reviewer and the licensee's Technical Review Board although not all had been formally accepted by management.
The in-spector will verify formal management acceptance of the tests results during a subsequent inspection.
A summary of significant test results and identified test results deficiencies is provided in the discussion below.
Discussion TE-SU.ZZ-004 The inspector reviewed the Test Matrix results package for Test Condition One presented to the Station Operations Review Committee on August 26, 1986.
In addition, the inspector reviewed in detail the seventeen (17) results deficiencies that remained open at the end of Test Condition One and the scope of testing deferred to Test Condition Two. The inspector concluded that sufficient testing had been satisfactorily performed to justify the plant's entry into Test Condition 2.
TE-SU.BF-054. This test was performed in conjunction with the plan-ned scram during the Shutdown from Outside the Control Room, TE-SU.
SV-281. The scram times of four selected rods (coordinates 26-23, 42-15, 50-47 and 54-19) were measured and verified to be well within the acceptance criterion and technical specification limit of 7.0 second f l
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TE-SU.SE-112. The first calibration of the LPRMs was performed at 17.5% of rated thermal power. The Level 2 acceptance criterion re-quires that each LPRM read within 10% of its calculated value.
Twenty-four (24) LPRMs (of a total of 168) failed and a results de-ficiency (RDF #82) was generated to bypass these detectors until a more accurate calibration could be performed at a higher power level.
Of the 24 detectors that failed, 7 were identified as having elec-trical problems requiring correction.
TE-SU.ZZ-122. The APRMs were calibrated conservatively by means of a manual heat balance. The technical specification setpoints for scrams and rod blocks were verified. All acceptance criteria were satisfied.
TE-SU.BD-142. At a reactor pressure of 157 psig, RCIC was tested for operability during an actual vessel injection. All acceptance cri-teria were satisfied including a time to rated flow of 17.6 seconds (Limit 30 seconds) during a hot quick start.
TE-SU.BJ-151. This test was performed twice (at 200 psig and at 925 psig reactor pressure) to span the design operating range for HPCI.
Time to rated flow at both conditions was well within the acceptance criterion and technical specification limit of 27 seconds (14.3 se-conds at low pressure and 17.7 seconds at high pressure). All other acceptance criteria were also satisfied.
TE-SU.BB-191.
This initial verification of the core thermal-hydraulic limits was performed at 16.2% of rated thermal power and 43.5% of rated core flow. All acceptance criteria were satisfied and the results are summarized below:
Parameter Ma,ximum Measured Limit LHGR (kW/FT)
3.34 513.4 CPR 5.551 21.393 APLHGR (KW/FT)
2.84 s12.10 TE-SU.BB-221. This test was performed at (16.5%) of rated thermal power to demonstrate adequate transient response of the pressure regulator with the Main Turbine on-line. A results deficiency (RDF #88) was identified when several controlled variables (among them reactor pressure and control valve position) failed the Level 2 acceptance criterion for quarter wave damping (decay ratio) during positive step changes in pressure setpoint ( 10 psi). The inspector will follow the resolution of this deficiency during subsequent testing. All other. acceptance criteria were satisfied, i
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TE-SU.AE-236. This test was performed at 18.4% of rated thermal power to demonstrate adequate transient response of the feedwater startup level controller. All acceptance criteria were satisfied.
However, limit cycles in reactor water level of 3 to 4 inches (peak-to peak) were noted and a Deficiency Report (HIC-86-1805) was issued to investigate and resolve this problem.
The inspector will follow the resolution of this problem during subsequent inspections.
TE-SU.AB-251. This test was performed at 16.5% of rated thermal power to verify the stroke and closure times of the MSIVs. All acceptance criteria were satisfied and the results are summarized below:
Valve Stroke Time (Sec)
Closure Time (Sec)
Minimum Maximum Time Time Measured Limit Measured Limit F022A 3.09 3.0 3.27 5.0 F0228 3.57 3.0 3.90 5.0 F022C 3.57 3.0 3.97 5.0
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F022D 3.55 3.0 3.92 5.0 F028A 3.51 3.0 3.75 5.0 F0288 3.34 3.0 3.88 5.0 F028C 3.01 3.0 3.52 5.0 F028D 3.33 3.0 3.57 5.0 Since valves F022A and F028C were close to the acceptance limit the licensee elected to adjust the stroke times of these valves during the outage following Test Condition One. The stroke time of F022A was increased by 1.09 secondr (cold) and the stroke time of F028C was increased by.43 seconds (co'...).
l TE-SU.BB-261. The functional test of the SRVs was performed at 19.9%
of rated thermal power and a reactor pressure of 927 psig. Two level i
2 results deficiencies were identified. The first, RDF #83, identi-fied five SRVs whose tailpipe temperatures failed to return to pre-test levels. The second, RDF #89, involved three acoustic monitors which did not respond properly when their associated SRVs were cyc-led. The inspector will follow the resolution of these deficiencies during future routine inspections. All other acceptance criteria were satisfied.
TE-SU.GT-724. All acceptance criteria were satisfied.
TE-SU.AB-793. This test did not contain acceptance criteria but i
collected baseline data on acoustic monitor noise levels during SRV lifts in order to determine appropriate alarm setpoints for technical
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specifications. As discussed above (TE-SU.88-261), three acoustic monitors failed to properly respond to SRV lifts and baseline data for these remain to be obtained following the resolution of RDF #89 and the subsequent retest.
Findings No unacceptable conditions were identified.
3.0 Independent Measurements and Verifications The inspector performed multiple independent measurements and verifica-tions during the evaluation of power ascension test results (paragraph 2.4).
In all cases the inspector's measurements and verifications agreed with those of the licensee.
No unacceptable conditions were noted.
4.0 QA/QC Interface with the Power Ascension Test Program During the course of evaluating power ascension test results, the inspec-tor verified that the test results packages had been reviewed by QA eng-ineers and that their comments had been appropriately resolved.
No unacceptable conditions were noted.
5.0 Unresolved Items Unresolved items are matters about which more information is required in order to determine whether they are acceptable, an item of noncompliance or a deviation. Unresolved items disclosed during the inspection are discussed in paragraph 2.3.
6.0 Exit Interview At the conclusion of the site inspection on September 5, 1986, an exit meeting was conducted with the licensee's senior site representative (denoted in paragraph 1.0).
At no time during the inspection was written material provided to the licensee by the inspector. Based on the NRC Region I review of this re-port and discussions held with licensee representatives during the in-spection, it was determined that this report does not contain information subject to 10 CFR 2.790 restrictions.
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Attachment A Power Ascension Test Procedures Reviewed TE-SU.ZZ-005 Test Plateau Matrix Test Procedure for Test Condition Two, Revision 1, Approved August 29, 1986 TE-SU. BJ-152 High Pressure Coolant Injection System Reactor Pressure Vessel Injection, Revision 2, Approved June 16, 1986 TE-SU.BJ-153 High Pressure Coolant Injection System Reactor Pressure Vessel Injection-Cold Quick Start, Revision 2, Approved June 10, 1986 TE-SU.ZZ-161 Bottom Drain Temperature Test, Revision 2, Approved May 22, 1986 TE-SU.ZZ-164 Post Recirculation Pump Trip Temperature Stratification Test, Revision 2, Approved June 10, 1986 TE-SU.BB-222 Pressure Regulator Test-Bypass Valves Incipient, Revision 2, Approved August 8, 1986 TE-SU.AB-252 Main Steam Isolation Valve Full Isolation Test, Revision 1, Approved February 10, 1986 TE-SU.CH-274 Bypass Valve Capacity Test, Revision 0, Approved August 27, 1986 TE-SU.EG-751 Safety and Auxiliary Cooling System Operational Performance Test, Revision 0, Approved October 22, 1985 TE-SU.ZZ-781 Reactor Building Ventilation System Normal Operation Performance Test, Revision 0, Approved May 22, 1986
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Attachment B Power Ascension Test Re$ults Evaluated TE-SU.ZZ-004 Test Plateau Matrix Test Procedure for Test Condition One, Revision 2, Completed August 26, 1986, Results Accepted August 27, 1986 TE-SU.BF-054 Control Rod Drive System Scram Testing During Planned Scrams, Revision 4, Completed August 23, 1986, Results not yet accepted TE-SU.SE-112 Local Power Range Monitor Calibration, Revision 2, Completed August 21, 1986, Results not yet accepted TE-SU.ZZ-122 Average Power Range Monitor Calibration at Power, Revision 3, Completed August 21, 1986, Results not yet accepted TE-SU.BD-142 Reactor Core Isolation Cooling System Reactor Pressure Vessel Injection, Revision 7, Completed August 12, 1986, Results Accepted August 28, 1986 TE-SU. BJ-151 High Pressure Coolant Injection System Condensate Storage Tank Injection, Revision 5, Completed August 12, 1986, Results Accepted August 28, 1986 TE-SU. BJ-151 High Pressure Coolant Injection System Condensate Storage Tank Injection, Revision 6, Completed August 22, 1986, Results Accepted August 29, 1986 TE-SU.BB-191 Core Performance, Revision 1, Completed August 21, 1986, Results not yet accepted TE-SU.BB-221 Pressure Regulator Test-Control Valve Controlling, Revision 5, Completed August 21, 1986, Results not yet accepted TE-SU.AE-236 Feedwater Startup Controller Test, Revision 4, Completed August 14, 1986, Results not yet accepted TE-SU.AB-251 Main Steam Isolation Valve Functional Test, Revision 3, Completed August 20, 1986, Results not yet accepted TE-SU.BB-261 Relief Valve Test, Revision 4, Completed August 22, 1986, Results not yet accepted TE-SU.GT-724 Containment Penetration Cooling Normal Operation Performance Test, Revision 2, Completed August 14, 1986, Results not yet accepted TE-SU.AB-793 Safety Relief Valve Acoustic Monitor Baseline Data, Revision 0, Completed August 21, 1986, Results not yet accepted L
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