IR 05000498/1989043
| ML19332E706 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 12/05/1989 |
| From: | Ray Azua, Bundy H, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19332E705 | List: |
| References | |
| 50-498-89-43, 50-499-89-43, NUDOCS 8912120002 | |
| Download: ML19332E706 (10) | |
Text
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APPENDIX
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. U.S.-NUCLEAR REGULATORY COMMISSION-REGION IV-
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NRC. Inspection: Report:- 50-498/89-43 Operating-License: ' NPF-76 ff' <
50-499/89-43, NPF-80
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Dockets:. 50-498-
'50-499 Licensee: Houston' Lighting & Power Company (HL&P)
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P.O. Box 1700
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Houston, Texas. 77001 Facility Name:1;SouthTexasProject.(STP), Units 1and2-Inspection At:
STP, Matagorda' County, Texas; (
_ Inspection Conducted:
November 13-17, 1989
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Ins'pectors-O MN/f*/
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H. F. Bundy? Reactor Insipector. Test Programs Date Section Division of Reactor Safety
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=R. V( Az p 'eovior tor, Test Programs Dat( ='
Sectioh7M s on.of Reactor Safety
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Approved:
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W. C. Seidle, Chief, Test Programs Section,
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Division of Reactor Safety..
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Inspection Summary
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' Inspection Conducted November 13-17, 1989 (Report 50-498/89-43; 50-499/89-43)=
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Areas Inspected: Routine, unannounced inspection of.the licensee's plant-
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surveillance _ procedures'(PSPs) and records.
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o Results:: The inspectors found that surveillance tests were being scheduled and
. performed as required by the Technical Specifications (TS) in accordance with approved PSPs.. The overall PSPs were high quality.- Acceptance criteria were
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clear and. test results were referenced to the criteria.
Independent verifica-tions and reviews were documented. Appropriate instructions for returning'
equipment-to service were given. The inspectors observed'that data package.
retrieval was. slow._ This was apparently caused by a large filing backlog. The
- inspectors advised the-licensee of the following apparent weaknesses and potential. improvement items:
(1) References to TS in the PSPs were generally vague.
Partial satisfaction of the TS requirement _was usually not stated when appropriate and, in
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these instances, it was usually not stated another PSP also responded to the TS.-
j-(2) The use of not applicable (N/A) was prevalent in the data packages, and in j
several instances, no explanation was given, or the explanation was.
inadequate.
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- (3) The licensee's creativity ~1n subdividing and assigning additional identifying numbers to individual TS created confusion.
In one example, a
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PSP referenced part of an action statement which should not have been subdivided, No violations or deviations were identified.
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r, DETAILS'
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Persons'-Con'. acted u
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- G. E. Vaughn, Vice President - Nuclear Group
- R. W. Chewning. Vice President - Nuclear Operations
- J. E. Geiger, General Manager - Nuclear Assurance
- W.; H. 'Kinsey, Plant Manager - STP s
- M.:R. Wisenburg, Chairman - Nuclear Safety Review Board i
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- T. J. Jordan, Plant Engineering Manager
- J. R.-Lovell. Technical Services Manager
- G. L. Parkey, Manager - Integrated Planning-and Scheduling--
- W. J. Jump, Maintenance Manager
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- J. W. Loesch, Plant Operations Manager
- W. L. Giles, Unit 2 Operations Manager
- W. H. Humble. Programs Supervisor - Plant Engineering Department
- C.-A. Ayala, Supervising Licensing Engineer
- A.lW. Harrison, Supervising Licensing Engineer
- A. K. Khosla, Senior Engineer - Licensing
'C. R. Grantom, Plant Surveillance Coordinator - Plant Engineering Department
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- S. Mick, Planner - Plant Engineering Department
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NRC-
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- J.- E. Bess, Senior Resident Inspector
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R., Evans, Resident Inspector The inspectors also interviewed other licensee employees during the. inspection.
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- Denotes'those attending exit _ interview on November 17, 1989.
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Plant Surveillance-Procedures (PSPs) and Records (61700)
^ The purpose of this inspection was to ascertain whether the surveillance of safety-related systems and components was being conducted as required by the TS and in accordance with approved procedures.
Pursuant to this objective, the inspectors reviewed the following licensee documents:
Station Procedure OPGP03-ZE-0004, Revision 9, " Plant Surveillance
Program"
. Station Procedure OPGP03-7A-0055, Revision 4, " Plant Surveillance Scheduling" Station Procedure OPGP03-ZE-0005, Revision 9. " Plant Surveillance
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Procedure Preparation"
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tThe inspectors then selected certain TS surveillance requirements and-reviewed the associated PSP and an appropriate number of data packages for
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each PSP.. Also, it was verified that selected test personnel had appro-
- priate training and educational' qualifications. The TS surveillance
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, inspectors, are tabulated in Attachment 1 for STP Unit 1 and Attachment 2-for STP Unit 2.'
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, m The inspectors determined that the required surveillances were being
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scheduled and performed as required. The PSPs were adequate. The
l acceptance criteria were clear and the test.results were appropriately
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referenced:to acceptance criteria. The data packages provided evidence of independent verifications and reviews. Appropriate instructions for returning equipment to service following testing were given.
l The inspectors observed that a large filing backlog made retrieval of data packages slow and cumbersome because those data packages in the holding area were not in the computerized file index.
Notwithstanding, the overall high, quality of the PSPs and da'ta packages, a i
number of potential improvement items were identified by the inspactors as follows.
References in PSPs to TS were generally vague.
It was seldom stated:that the PSP only ' partially satisfied a TS, if appropriate. Also, in instances of partial satisfaction,'it was seldom stated how the PSP
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responded to the referenced TS. The use of "N/A" (not applicable) was
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prevalent in data packages, and in several instances, no explanation was
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given, or the explanation did not state an adequate basis for the waiver.
a It was observed that the licensee was, on occasion., creative in assigning j
identifiers to TS requirements.
In one' instance, a PSP referenced part of i
an action statement which should not have been subdivided.
Specific details and comments associated with the data reviewed and
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potential improvement. items are as follows. The inspector observed in the TS that there were paragraphs that addressed two.or more items to be surveillance tested. The licensee, in some cases, had opted _to provide separate surveillance procedures to address each item. One such TS was-4.4.6.1.b. which addressed the calibration check of one flow.and two' level
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' instruments. Three procedures were generated to address,these items (2 PSP 05-ED-7839. -7823 and -7812).
In the text.of the' procedures, the TS
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that was being satisfied was listed. For the level instruments it was glisted as'4.4.6.1.b.1.
The last digit (1) was arbitrarily assigned to designate the fact that only one of the items of that TS was being addressed. This is not an uncommon practice, but it was noted that in another section of the procedure, the associated TS' action statement was
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The last digit (1) again was added, but it appears
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to havet been added in an effort to be consistent with the numbering used for the surveillance TS (4.4.6.1.b.1).
In that the action statement was all inclusive, this numbering was inappropriate.
It was also noted that this numbering method was not consistent in all of the procedures reviewed.
The inspector informed the licensee that the uncontrolled use of the arbitrarily-assigned numbers may lead to situations that could be
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misleading. The licensee agreed to follow up on this observation to
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determine if there~ are other inconsistencies in numbering.
In following
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formal on-the. job training-(0JT) program had not been instituted.
The licensee stated that this program would go into effect on December-12,
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1989, as agreed upon with the NRC regional office. The inspector discussed
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this matter with: regional personnel,-and no concerns are identified at
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. this time.
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No violations or deviations were identified 'in the review of this program
area.
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Exit Interview The inspectors met with the licensee representatives denoted in paragraph 1 on November 17, 1989 - and summarized the scope and findings of this inspection.
- The licensee did not identify, as proprietary, any of the materials provided to, or reviewed by, the inspectors during this inspection.
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ATTACHMENT 1
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STP UNIT 1-PROCEDURES AND RECORDS REVIEWED
,TS.
Description PSP Numbers l$
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4.1.1.3a ~
Verify MTC is less than 0 delta K/K/'F
.OPSP10-ZG-0001, R0-prior to initial operation above 5%
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RTP after each fuel loading.
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-4.1.1.3b Verify MTC is equal to or more positive OPSP10-ZG-0004, R2 i
than -3.1X10'4 delta K/K/*F within:
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7 EFPD after reaching an equilibrium j
boron concentration of 300 ppm.
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L 4.1.2.2d Verify at least 2 boron injection flow IPSP03-CV-0010, R4
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paths deliver 30..gpm each.
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4.1.3.4 Measure rod drop times of full length' rods. OPSP10-DM-0001 R1
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Measure target flux difference of each OPSP10-NI-0001, R5;
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operable excore channel at least once per
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92 EFPD.
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'4.2.2.2d Remeasure Fxy at'least once per 31 EFPD OPSP10-II-0003,;R4
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or as conditions dictate.
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rmine~RCS total flow rate by--
OPSP10-RC-0001, R0
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balance.
=4 Perform channel calibration for SG
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4.3.1.1,
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water level low-low trip.
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Table 4.3-1, Item 14-
- 1 PSP 05-FW-0537. R1; -0547 R1; -0519 R1; -0529, R1; -0539, R1;
-0549, R1; -0571, R1; -0572, R0; -0573, R1; -0538 R1; -0518. R1;
-0517, R0; -0528, R1; -0527. R1; -0574, RI 4.3.1.1, Calibrate power range neutron. flux-IPSP05-NI-0041, R0;
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' Table 4.3-1, Permissive P-8.
IPSP05-NI-0042, R1;
= Item 19.c IPSP05-NI-0043, R1 1 PSP 05-NI-0044, R1 j
4.3.2.1,.
Perform SI containment pressure high-1 1 PSP 05-HC-0934, R1; Table 4.3-2, channel calibration.
1 PSP 05-HC-0935. R1;
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Item 1.d IPSP05-HC-0936, R2 4.3.3.1, Calibrate containment atmosphere OPSP14-RA-1018, R3 Table 4.3-3, radioactivity - high alarm.
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Item 1.a 4.3.3.5.2 Demonstrate remote shutdown components 1 PSP 03-RC-0010, R3 l
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1 PSP 03-CV-0011, R4 l
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TS1 Description PSP Numbers
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4.3.3.6 Celibrate containment water level-(NR)
IPSP05-ED-7840 R0
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(L; Table 4.3-7, channels.
IPSP05-ED-7839. R0
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Item,13 h~
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Calibrate turbine overspeed' protection 1 PSP 05-TM-0001, R2
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4.3.4.2c
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4.4.4.-1 -
Demonstrate each PORV operable by
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performing a channel calibration.
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-0458. R1; -0457, R1;_-0655, R2
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'4.4.11b-Cycle-each reactor coolant vent valve IPSP03-R-0009. R3 from control room.
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4.5.1.1d.1)
Verify accumulator isolation valv'es-IPSP03-SP-00090, R0 open automatically on P-11 4.5.2d Visually inspect containment sumps.
OPSP04-XC-0001; R3
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-4.6.1.5 Verify containment air temperature does IPSP03il0-0002, R9
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not exceed 120*F.
4.6.2.lc.2)
Verify each CS pump starts in auto on a 1 PSP 03-SP-0013, R0*
i Containment Press. High-3 Test < Signal.
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4.6.2.3b Verify each RCFC group starts in auto IPSP03-SP-0013, R0;
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on a S1 signal.
L 4.6.3.2c-Verify that'each Phase B' isolation valve 1 PSP 03-SP-0018. R0 goes to the isolation position on a Phase:8-h, isolation test signal.
4.7.1.2(1b1)
Verify each auto valve in the AFW flow IPSP03-SP-0019, R0
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path actuates to correct position on f
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input of AFW actuation test signal.
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4.7.4b2)-
Verify each ECW pump starts in on IPSP03-SP-0013, R0
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a Si or a LOOP test signal.
IPSP03-0G-0013, R4 1 PSP 03-DG-0014, R4 i
IPSP03-DG-0015, R4 l
4.7.8d.2)
Verify FHB exhaust air system operable 1 PSP 03-HF-000), R6
by verifying system start on high IPSP03-HF-0002, R1 radiation and Si test signals.
IPSP03-SP-0013 R0
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TS Description.
PSP Numbers
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.4.8.1.1.lb Demonstrate onsite Class 1E distribution IP$P03-AE-0004. R2 f
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system operable by transferring unit p
power supply from the normal circuit to
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teach of the alternate circuits.
'4.8.2.1c.4)
Verify that battery charger will supply-1 PSP 06-DJ-0006, R3-at least 300 amperes at 125V for at
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least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />..
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ATTACHFENT 2
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STP UNIT 2 PROCEDURES AND RECORDS REVIEWED
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TS Description PSP Numbers
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4.1.2.2b Verify boron injection flow paths.
20SP03-CV-0009. R0 4.1.2.6a Verify boron concentration in each OPSP07-ZC-0001, R4
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borated water source.
4.2.1.3 Peasure target flux difference of each OPSP10-NI-0001, R5 operable excore channel at least once per 92 EFPD.
4.4.4.la Demonstrate each PORY operable by 2 PSP 05-RC-0455. R0 performing a channel. calibration.
2 PSP 05-RC-0458, R0 2 PSP 05-PC-0456, R0 2 PSP 05-RC-0457. R0 2 PSP 05-RC-0655, R1 4.4.4.lb Demonstrate each PORY operable by 2 PSP 03-RC-0010, R1 operating the valve thru one complete cycle of full travel.
4.4.4.2 Demonstrate each PORV block valve 2 PSP 03-RC-0009. R1 operable by operating the valve thru one complete cycle of full travel.
4.4.6.lb Demonstrate leak detection systems 2 PSP 05-ED-7839, RD operable by performance of channel 2 PSP 05-ED-7812-RO calibration for containment normal 2 PSP 05-ED-7823. R0 sump level and flow monitoring system.
4 4.6.2.2a Leak test each RCS pressure isolation 2 PSP 03-SI-0023 R0
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valve specified in Table 3.4-1, 2 PSP 03-RH-0010, R2
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4.4.11 Demonstrate each RV head vent path 2 PSP 03-RC-0011 RO operable, 2 PSP 03-RC-0009. R1 4.5.2b Demonstrate each ECCS subsystem operable 2 PSP 03-SI-0014. R1 at least once per 31 days by (1) venting pump casings and high points, (2) verifying
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TS, Description PSP Numbers t.
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Demonstrate primary containment integrity 2 PSP 03-SI-0016, R1
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at least once per 31 days by verifying
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correct positioning of valves and installation of blind flanges, f
e 4.6.2.la Demonstrate each containment spray 2 PSP 03-$1-0017. R0 '
system operable by verifying correct
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F positioning of valves.
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4.6.2.3a Demonstrate each group of reactor 2 PSP 03-HC-0001, R0 t
containment fan coolers operable by starting and operating each group from control room and verifying
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cooling water flow, i
i 4.6.4.2a-Demonstrate each hydrogen recombiner 2 PSP 05-CG-0001, R2 system operable by verifying attainment
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of minimum temperature and power.
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4.7.1.2.la.1) Demonstrate each AFW pump operable by 2 PSP 03-AF-0001, R1
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verifying that each motor-driven pump 2 PSP 03-AF-0002, R1
develops minimum discharge pressure
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and flow.
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