IR 05000498/1987047
| ML20238C546 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 08/27/1987 |
| From: | Bundy H, Carpenter D, Constable G, Reis T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20238C499 | List: |
| References | |
| 50-498-87-47, 50-499-87-47, IEB-80-06, IEB-80-6, NUDOCS 8709100191 | |
| Download: ML20238C546 (11) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspector Report:
50-498/87-47 Construction Permits:
CPPR-128 50-499/87-47 CPPR-129 Dockets:
50-498 Expiration Date:
December 1987 and 50-499 December 1989 l
Licensee:
Houston Lighting & Power Company (HL&P)
P. O. Cox 1700 Houston, Texas 77001 Facility Name:
South Texas Project, Units 1 and 2 (STP)
Inspection At:
STP, Matagorda County, Texas Inspection Conducted:
June 27 through July 31, 1987 Inspectors;
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9 /f7
. R.Tirpenter, Senior Resident Inspector Date Project Section C, Reacter Projects Branch (
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U gT"Reis, Resident Inspector, Project Date Section C, Reactor Projects Branch
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1T/2 '?h JiT. F.'~Bunay,7Foject Inspector, Project Date Section C, Reactor Projects Branch g/7-7/97-Approved:
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C. t.r erutible, Chief, Project Section C Date Reactor Projects Branch 8709100191 s7o9o4
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gDR ADOCK 05000498 (.
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Inspection Summary
_ Inspection Conducted June 27 through July 31, 1987 (Report 50-498/87-471 50-499/87-47)
Areas Inspected:
Routine, unannounced inspection including licensee action on previous inspection findings, incomplete preoperational tests, IE Bulletins, security, preoperational test procedure review, preeperational test witnessing, and site tours,
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Results: Within the areas inspected, no violations or deviations were identified.
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DETAILS i
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Persons Contacted
- W. P. Evans, Project Compliance Engineer j
- W. H. Kinsey, Plant Manager
- G. L. Parkey, Plant Engineering Manager
- J. Constantin, Supervisor, Simulator Training
- J. D. Green, Operations Quality Assurance Manager
- S. M. Dew, Mr. nager, Operations Support
- D. N. Brown, Manager, Construction Support
- G. L. Jarvela, Health Physics Division Manager
- S. M. Head, Supervisory Licensing Engineer
- G. Ondriska, Startup Engineer Supervisor
- M. E. Smith, Unit 1 Outage Manager
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In addition to the above, the NRC inspectors also held discussions with various licensee, architect engineer ( AE), constructor, and other
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contractor personnel during this inspection.
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- Denotes those individuals attending the exit interview conducted on August 3, 1987, 2.
Licensee Action on Previous Inspection Findings (Closed) Open Item 498/8708-06 This item tracked the licensee's evaluation of the component cooling water hammer incident which occurred on March 11, 1987. The licensee evaluated this event in Incident Review Committee Report 0372, which was reviewed and closed by an NRC inspector in NRC Inspection Report (IR) 50-498/87-27.
That review constitutes closure of this item.
(Closed) Open Item 498/8708-27 This open item concerns the review and quarterly update of Procedure PRO-1, " Standing Orders." There is a requirement in PRO-1 to review and update quarterly the site Standing Orders but there was no mechanism to document completion of this requirement.
The licensee has revised this procedure to Revision 3, which incorporates a review and update checklist. When updates are added or quarterly reviews are accomplished the reviewer dates, initials, and annotates the activity on the checklist.
The NRC inspector has reviewed this system'and considers it acceptable.
This open item is considered closed.
_(Closed)OpenItem 498/8708-30 This open item concerns the adequacy of Plant Procedure OPGP03-ZO-0003, Revision 3, " Temporary Modifications and Alterations." There were six
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concerns raised by the NRC inspector ir. Revision 3 of this procedure. The i
licensee has reviewed this procedure several times since this item was i
opened. The current revision (6) of'OPGP03-ZO-0003 has been reviewed by
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the NRC inspector and the six items identified in the open item have been l
acceptably resolved.
This open item is considered closed.
i (Closed) Open Item 498/8708-34 This open item identified potential concerns during the. trial use of operating procedures prior to OL.
The licensee reviewed all license compliance reviews (LCRs) to ensure they were properly performed under the current revision (Revision 6) of Plant Procedure OPGP03-ZO-0003,
" Temporary Modifications." The following are the specific points and
licensee's action on each item.
Temporary Modification TI-DG-87123 was written and installed without
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performing an LCR.
The individual who requested the temporary modification and his supervisor who approved the request are not nuclear plant operations i
department (NPOD) personnel.
They have been counseled to comply with
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procedures.
Only NPOD system engineers are authorized to request temporary modifications. NPOD system engineers have received additional training on the temporary modification program.
This appears to be an isolated case.
Records were incomplete. A plant operations review committee (PORC)
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review was not signed in the required 14 days and the LCR was not
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included in the closed temporary modification package.
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The PORC review requirement was included in Revision 5 of Station Procedure OPGP03-ZO-0003 (effective May 8, 1987.
Temporary i
modifications initiated prior to that date are not required to have a PORC review.
Temporary modifications written per Revision 5 or 6 (6 is the current revision) of.0PGP03-ZO-0003 have had the required
14-day PORC review.
An HL&P review of temporary modifications was performed on April 1, 198. Temporary modifications that were not closed prior to that date have been reviewed for completion of LCRs.
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Those temporary modifications that were closed prior to April 1, j
1987, have been restored.
Since the systems are now in the original j
configuration, there is no reason to review the closed documents.
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l Incomplete review and documentation of performances of LCRs for i
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procedures and design changes i
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Pro:edures were written specifically for use following receipt of an operating license (0L) and were evaluated for license compliance on that basis.
The biennial review program and each procedure revision includes a reevaluation of license compliance (reviewing procedure against the current final safety analysis report (FCAR) and Technical Specifications.
In addition, surveillance procedures have been reviewed against the Final Draft TS.
The following documents are in place to ensure LCRs are performed as-required during the design change process: OEP 3.14Q, " Review of Design Changes During Document Turnover"; IP 3.1Q, " Modifications";
IP 3.200, "10CFR50.59 Evaluation."
The NRC inspector has reviewed the licensee's actions on this open item.
and considers them acceptable.
The open item is closed.
(Closed) Violation 498/8703-01, " Failure to Follow Procedures" This violation concerns tailure to follow plant Procedure OPGP-03-ZL-0002, Revision 4, "New Fuel Receipt,~ Inspection and Storage," Step 8.4 which requires taking alph. contamination surveys and recording the data for new fuel receipt.
The licensee has revised the procedure to clarify the survey and data recording requirement.
The original Revision 4, had a limit of less than 50 dpm alpha for the shipping container and less than 20 dpm alpha for the new fuel. The technican recorded all the data as less than 50 dpm..The current revision specifies that both survey areas are to have less than 20 dpm alpha contamination. Additionly the health
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physics (HP) technicans were provided additional training in the requirements of procedures.
The two assemblies that were noted as having the suspect data reading were resurveyed and verified to be less than the 20 dpm alpha contamination. A l
review of the documentation for the 32 previously received new fuel survey data sheets did not identify any additional suspect readings.
The NRC
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inspector has reviewed the licensee's actions on this violation and considers them acceptable.
This violation is considered closed.
(Closed) Open Item 498/9708-59 This open item concerns NRC inspector' ; observations concerning plant
maintenance procedures dealing with the calibration of test equipment.
The seven procedure have been reviewed and revised to clarify the points of concern.
The changes have been reviewed by the NRC inspector and are acceptable, j
(Closed) Open Item 498/8708-64 This open item concerns an action statement that was identified as a
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" Note" in Plant Procedure IPOP04-RC-0002, Revision 1, " Loss of Reactor
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Coolant Pump." The procedure has been revised to change the " Note" to a
" Caution" statement and also incorporate the associated actions in the action statement sections of the procedure.
The NRC inspector has reviewed the Revision 2 of the procedures and considers it acceptable.
This open items is considered closed.
(Closed) Open Item 498/8723-05 This open item concerns Procedure NGP-820, " Nuclear Safety Review Board (NSRB) Policy." The procedure needed clarification in two sections and did not reflect the requirement of Draft Technical Specification, Section 6.5.2.2, in one other section.
The licensee has revised the procedure to clarify the points of concern and also reflect the requirements of the Draft Technical Specification. The NRC inspector has reviewed the revised procedure and considers it acceptable.
This open item in considered closed.
(Closed) Open Item 498/8723-06 This open item concerned the NSRB Procedure NSRB-01, " Rules of Conduct."
The NRC inspector observed that the procedures did not fullfill the requirement as described in the Section 6.5.2.9.a, with regard to unscheduled NSRB meetings.
The licensee has revised Procedure NSRB-01 and this revision has been discussed with the NRC inspector.
The revision now addresses the concerns of the NRC inspector and agrees with the Draft Technical Specification requirements.
This open item is considered closed.
(Closed) Open Item 498/8723-07 This open item concerns NRC comments on plant Procedure OPGP03-ZA-0004, which deals with how the PORC conducts it's activities.
Some attributes of the Sections 6.5.1.5 and 6.5.1.6.p of the Draft Technical Specification were not adequately addressed in the PORC procedures.
The licensee has i
revised this procedures to ensure it complies with the Draft Technical Specification.
This open item is considered closed.
3.
Incomplete Preoperational Tests I
i The following preoperational tests are not complete and are not intended l
to be complete prior to fuel loading.
The licensee submitted
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justification that the tests are not functionally required prior to loading fuel based on the following criteria:
The system tested is not required to place the plant in a safe shutdown condition prior to the listed mode.
The system tested is not required to mitigate the circumstances of
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any accident prior to the listed mod g
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The, system tested is not required to prevent release of n bioactivity
to ".he environment prior to the listed, mode.
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Specific criteria are listed for the' indik idual tests.
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e Test / Percent Complete Title and Licensee Remdrid
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1-BR-P-01 - 0%
Boron Recycle System and Evaporatdr I
Perforv.ance - To be completed prior to
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Mode 2.
There is no requirement for recycling boric acid prior to Mode 2
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1-CN-P-01 - 974 Communication Paging _,and Site Warning Test
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j will be completed uppt receipt of emer,fency notification system'(045) phones fyom hRC.
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Emergency communication is available.from e
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center (TSC), and the control room,(CR).
l 1-EW-P-05 - 100%
Essential Cooling Water (ECW) ChilleE Retest Required Condenser Valves - Portion of test riquirbd
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to verify operation with low ultimate heat
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i sink temperature (less than 53 degrees
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Fahrenheit) WilI be completed by September 30, 1987 The valves are presently W
locked open to provide proper flow to the p.nential chillers'.
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1-FW-P-01 - 10%
Feedsater (FW): System Isolnion and Flow
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Control Logic Test - Testing not requiied to be complete prior to Mode 4.
Main feedwater isolation valve (MFWIV) operability'not, required until Hade 4.
1-HB-P-01 - 99%
Control Room Heatina, Ventilation and Air Conditioning (dVAC) System Preoperationaj Test - System is operable per Technical
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Specification.
The low and high flow alerms on the cleanup units are the only items not f
tested, due to design problems. The alarms will be operable and tested. prior to Mode 2.
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1-hk-P-01 - 0%'
Heat Trace - The systems for which the heat f
tracing.ild tested in this test are not j
required until Mode 3 (auxil bry feedwater)
or Mode 2 (Post-Accident. Sampling System (PASS), Containment Monitoring,'iieat tradng d
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and Boron Recycling). The safey-related
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will ba tested for each systen prior to 4he required mode for the.'systto
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1-PS-P-01 - 99%
Primary Sampling - Selected PASS valves must-(
be timed under dynamic conditions. The PASS
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valves will be tested prior to Mode 2.
Reactor Coolant System (RCS) must be at
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operating temperature and pressure prior to completing.this test.
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Liquid Monitors - IRA-RT-8041 testing was
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field complete 7-30-87 Test results are in Joint Test Group (JTG) review and will.be
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transmitted to the vault by 8-7-87. The turbine generator building (TGB). sump monitor is not required to be operable
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prior to Mode 2.
H 1-RA-P-18 - 98%
System Communications - System only needed
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for personnel reentry into containment
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following initial criticality.
Test i
scheduled to be complete prior to Mode 2, but
/~ is scheduled to be field complete by 8-3-87.
1-HC-A-02 98%
Containment High-Efficiency Particulate Air
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Filters (HEPA)/ Charcoal Preoperationaf~ Test
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Not required till Mode 2 since no airborne
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radioactivity generated until Mode 2.
1-RC-P-06 - 99%
Steady State Vibration Monitoring Test 1-RC-P-07 - 99%
Thermal Expansion Monitoring Test 1-RC-P-08 - 99%
Transient Vibration Monitoring Test To be completed at full power because
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measurements and observations can only be made during full power conditions (examples:
i main steam lines, main feed lines).
1-RC-P-11 - 98%
Pressurizer Level and Pressure Control preoperational Test To be completed prior to Mode 2.
The only section which is
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outstanding is to verify accumulator isolation valves open automatically on RCS c
pressure, which can only be done during
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Mode 3.
(The valves are administratively
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opened during normal operation; this test
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verifies. automatic operation, which-is a
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backup to the operator's procedure.)
1-SP-P-03 - 95%
Solid State Protection System (SSPS) Response p < Time Test - There are four areas not yet
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tested:
1) Overtemperature Delta T,
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, Overpower Delta T, and RCS resistance temperature detector (RTD) response times I
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k will be gathered
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The RTD
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times cannot we collected untilltne:RCS is filled.
SSPS trip functions froin thnse loop are not required to be functional'unt,il the '
unit is critical.
2); Urgent alarm testireg is '
not required until Mode 4 The alarms do not need to be functional until engineered: safety.
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features actuation signal (ESFAS) and trip functions are needed in Mode 4.
3) stean/
generator (SG) level transmitter LT527 d
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response time must ~be collected prior to,.
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The testing is.. field comp 12te and
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will be approved pN et ic Mode 3 ~
4) Feedwater isolation '/alves (FWIV) and ;
turbine trio response tihes are not needed until Modes 4 and 3, respectively. The ESFAS functions do not need to be operable prior to
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these modes. The times will attually be gathered from 1-FW-P-01-
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1-WL-P-02 - 0%
Liquid Waste Evaporator _Py formance Test
- See below 1-WL-P-03 - SC';
Liquid Waste Process Preaperatioral Test '
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- See below 1-WS-P-01 - 0%
Solid Radwaste Concentration Storage /Transfpr Chemical Feed - See belov 1-WS-P-02 - 25%
Spent Resin Co3p_ actor Transfer _Syg.em _
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procedures 1-WL-P-02,1-WL-03,1-SS-Pn)1 and
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1-WS-P-02 will be completed prior to Mie 2.
There will be r.0 liquid or solid cafwaste
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generated prior to Mode 2.
1-CU-A-01 - Field Work Plant Computer System - System is ndt' ' ~
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Complete required until Mode 2 because system
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monitoring and computational functions are not required until the plant is critical.
1-CV-A-01 - 50%
Boron Concentration Measuring System - This
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testing will be completed prior to full power operation. Boron concentration will bv-determined by sampling, which is a more precise method of determining.
1-FW-A-01 - 90%
Feeriwater System - To be completed at ful: power because testing requires main FW
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pump; to be run at full load This can be
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accomplish only at full power corditions with riequate steam supply.
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1-LA-A-02 - 755 smergpncy Lighting - Normal lighting 1-LA-A-0', - 80%
.availaaie and operational emergency lighting 1-LA-A-05 - 70%
"not pot entially impacting prior to Mode 4.
1-LA-A-06 - 90%
All systems scheculed to be compteted prior 1-LA-A-09 - 0%
to Mode 4.
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"The NRC inspector has reviewe.d these tests and this status and concurs with the licensee's conclusions The NRC inspector concludes that present test status. is not a deviation frcm FSAR commitments. Additionally, the NRC inspector ha reviewed the piant schedule to en; ore these tests are on the critical path schedule. Th.3 mode change check.tbeets also require the completier. of these tests prior to the mode where the system is required to be operable.
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IEBulletins[JEB)
(0 pen) IEB 80-06, Engineered Safety Features /.ctuatigp Signal (ESFAS)
Reset This bulletin concerns components improperly changing their positions upon receipt of ESFAS reset sional.
This Dulletin was originally closed following analysis of engineering drawings.
During ESF preoperational testing results revier, it was found that several valves returned to their ure-ESF actuatien signal condition subsequent to reset.
This is contrary to design commitment 3 The licensee has committed to revise the circuitry I
prior to entering Mo:ia 4.
This item has been reported by the licensee in l
accordance with 10 CFR 21.
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Securi (y During this inspection aeriod. the resident inspectors have been actively involved in the ongoing security inspection.
Their findings will be documented in NRC IR 50-498/87-43, 50-499/87-43.
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Preoperational Test Procedure Review Duri;ig the January 1987, insoection period (IR 50-498/8703) the NRC iracector performed a review'of preoperational test Procedure 1-CV-P-01,
" Chemical and Volume Contral System (CVCS) charging, Letdown and Seal
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Inspection," but that rrview was not adequately docummented in NRC IR 50-498/8703.
The test was foynd adequate and in compliances with the FSAR and Regulatory Guide 1.68.
No comments were fo'rwarded to the licensee for resolution.
No violations or deviations wera identified.
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Preoperational Test W'tnessing During hot functional testing the performance or' Procedure 1-RH-P-01, 02, and 03, the " Resident Heat Removal (RHR) System Performance, Trains A, B, and C," was witressed by the NRC inspector.
This information was not
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explicitly documented in conjunction with the hot functional testing, which included 22 separate preoperational tests.
The RHR testing demonstrated the system had the proper design characteristics prior to applying a thermal load to the system. The tests were conducted appropriately with the use of approved procedures and qualified test personnel.
The witnessing of the thermal performance of the RHR Systems Procedure 1-RH-P-04, was documented in NRC irs 498/87-03 and 87-08.
A violation of this test procedure was demonstrated in NRC IR 498/87-08 and has subsequently been closed. This entry documents the witnessing of comprehensive testing of the RHR system.
No additional violations or deviations were identified.
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Site Tours The NRC inspector conducted site tours both independently and accompanied by licensee personnel.
These tours were made primarily to assess security conditions, plant status, and personnel activities as fuel loading, Unit 1, approaches.
The areas toured includea:
Unit 1 - mechanical and electrical auxiliary building (MEAB), reactor
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containment building (RCB), fuel handling building (FHB), emergency diesel generator building (EDGB), isolation valve cubicle (IVC),
essential cooling water (ECW) intake structure and the lighting diesel buildings.
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Unit 2 - MEAB.
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Exit Interview The NRC inspector met with licensee representatives (denoted in paragraph 1) on August 3, 1987, and summarized the scope and findings of the inspection.
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