IR 05000369/1980024
| ML20002B889 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 11/20/1980 |
| From: | Donat T, Martin R, Myers D, William Orders, Shymlock M, Skinner P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20002B884 | List: |
| References | |
| 50-369-80-24, NUDOCS 8101070159 | |
| Download: ML20002B889 (8) | |
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Report No. 50-369/80-24 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: McGuire Nuclear Station Docket No. 50-369 License No. CPPR-83 Inspection at McGuire Nuclear Station near Charlotte, NC Inspectors: 0 $M
_ be / 9, /980 T. J. Donat Date Sigried
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@. B. Shyml ck (August 12-5)
Date Signed
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]/W. /fi/TSC P. Skinner (August 12-15)
Date Signed
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W. O. Meyers (September 16-19)
Datd Signed
u h.o/eo
. T. Orders (September 22-24)
Date Si{;ned Accompanying Perso el:
R. H. Woods, (September 24)
Approved by:
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R. b. Martin, Section Chief, RONS Branch Dale $igned SUMMARY Inspection on August 4, 1980 - September 30, 1980 Areas Inspected This routine, inspection involved 217 (108-August, 119-September)
inspector-hours onsite in the areas of Preoperational Test Witnessing, Preopera-tional Procedure Review, Followup on Previous Inspection Findings, Comparison of cs Built Safety Systems to FSAR figures, and Monitoring of the Status of Plant Preparation for Licensing.
Results Of the areas inspected, the findings were clear in all areas.
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DETAILS 1.
Persons Contacted Licensee Employees
- M. D. McIntosh, Station Manager T. L. McConnell, Superintendent-Technical Services
- L. E. Weaver, Performance Engineer
- W. M. Sample, Licenseing and Project Engineer
- C. P. Rogers, Instrumentation and Electrical Maintenance Engineer
- D. J. Rains, Superintendent of Maintenance G. W. Cage, Superintendent of Operations B. Hamilton, Reactor Engineer G. Singletary, Associate IAE Engineer D. Simmons, Associate IAE Engineer G. Golbreath, Assistant Test Engineer Other licensee employees contacted included construction craftsmen, technicians, operators, mechanics, security force members, and office personnel.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on August 15, August 22, and September 12, 1980 with those persons indicated in Paragraph I above.
The inspector (s) reviewed the efforts and areas covered since the last exit meeting.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Followup on Previous Inspection Findings Closed - Inspector Followup Item 78-BU-LA, concerning atypical weld material in reactor pressure vessel cladding welds. The inspector reviewed the generic letter from W. S. Reimuth to C. E. Murphy dated 7/1/80 in which the weld material was found to be acceptable. Based on this letter the item is considered closed.
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Closed - Inspector Followup Item 78-33-01, concerning the need for an approved reactor vessel inspection procedure per paragraph C.I.2.3 of Regulatory Guide 1.20, Rev 1.
The inspector discussed the licensee's commitments to Regulatory Guide 2.20 as stated in the FSAR, section 3.9.3.1. This commitment was to perform a pre-Hot Functional and a post Hot-Functional examination per the regulatory guide including as a minimum, the thirty-five points shown in FSAR figure 3.9.1-1.
Af ter se; eral discussions the licensee arranged a meeting with the NSSS vendor, station personnel, and the inspector to discuss the need for a licensee approved procedure since the NSSS vendor was to perform the inspection.
It was pointed out that Regulatory Guide 1.20 paragraphs C.I.2.3, C.3.1, C.3.2, C.3.3, and C.3.4 all require that the inspection shall be performed in accordance with a procedure listing the method of exam. nation, method of documentation, specialized equipment, and a tabula-tion of specific inspection areas.
On August 22, 1980 the licensee reviewed and approved TP/1/A/1150/18,
" Post Hot Functional Internals Inspection". The procedure does meet the requirements and commitments of FSAR section 3.9.3, and Regulatory Guides 1.20 and 1.68.
This item is closed.
Closed - Inspection Followup Item 78-28-02, concerning the lack of a state-ment in the Duke Power Company Administrative Policy Manual concerning meeting the quorum and frequency requirement. The inspector reviewed the requirements of Technical Specification 6.5.2.6 and policy numbers 2.6.2.2(e) and (f) dated 9/4/79 and found that meeting quorum requirements and frequency requirements are consistent. Therefore, this item is considered closed.
Closed - Inspector Followup Item 78-38-09 concerning completion of con-struction of the containment sump and recirculation suction lines. 1La inspector har, verified completion of the installation of the containment sump inlet housing in the containment pipe chase and the recirculation piping to the ND pump / spray pump pipe chase in the auxiliary building. The inspector has also seen the licensee's submittal documenting model test data and requesting the deletion of a full scale test. Based on these findings, the item is considered closed.
Closed - Open Item 78-30-01, concerning a discrepancy in the blowdown time recorded for cold leg accumulator D.
The inspector reviewed the initial accumulator test, TP/1/A/1200/03D, and the retest TP/1/A/1200/0s:
as well as the NSSS vendor letter MCN-79M-103 dated 12/11/79 in which the performance of all four cold leg injection accumulators was determined to be acceptable. Based on the evaluations performed and the documentation provided, the item is closed.
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-3-Closed - Open Item 79-17-01 concerning resolution of Hot Function Test (HFT) discrepancies on excess letdown system, pressurizer PORV valve binding, spray valve leakage, and actuator modifications on the pressurizer PORV valves and the atmospheric Steam Dump Valves. The HFT Sequence was re-peated between June 6, 1980 and August 1, 1980. During this second HFT sequence new preoperational tests or repeat performance of the original tests were performed. For the specific tests identified in the open item, these were:
TP/1/A/1150/04C Pressurizer Preliminary Spray Flow Fuctional-2 TP/1/A/1150/07A NC System Thermal Expansion and Restraint-2 TP/1/A/1150/16 Pressurizer Power Operated Relief Isolation Valve Functional Test-NEW TP/1/A/1150/17 Over Pressure Protection for Solid Meter Low Pressure Operation Verification-Test TP/1/A/1200/05B NV Functional Test (HOT)-Repeat TP/1/A/1200/09 Boron Thermal Regeneration System (BTRS) Hot Functional Test-Completed TP/1/A/1250/04 Auxiliary Feedwater System Functional Test - Rewritten TP/1/A/1250/05 Main Steam Safety Valve Setpoint - Repeat TP/1/A/1250/06 Main Steam Isolation Valve Timing - Repeat Based on the successful completion of these tests the item is closed.
Closed-Open Item 80-03-03 concerning replacement of defective locking ut-ts on limitorque salve operators in Unit 1.
The review of the completed work package is documented in report 30-369/80-20 and the item is closed.
Closed - Open Item 80-20-01 concerning manual / auto controllers set point adjustment potentiometers on main control board. The inspector reviewed the results of the licensee review of setpoint adjustment potentiometers mounted on the main control board. Twenty of the thirty-six potentiemeters are to be removed and of the remaining sixteen, eight will be administra-tively controlled and eight will be connected to entirely manual operation (auxiliary feedwater pumps to steam generators). Based on the licensee's actions this item is closed.
Closed - Open Item 80-22-01 concerning licensee's resolution of heat effects on pressurizer hydraulic snubbers. The inspector reviewed the licensee's Significant Deficiency Report SD 369/80-15. This report docu-ments the fact that the high temperature experienced in the pressurizer cubic 12 during the hot functional test program had effected the integrity of the snubbers hydraulic fluid reservoirs. The report stated that as a corrective action all except eleven snubbers would be replaced with mechanical snubbers and that those remaining would have metallic reservoirs.
The inspector has verified that the snubber modifications have been completed'and the item is closed.
6.
Preoperational Test Procedure Review
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The inspector reviewed the licensee's proposed test program for the con-tainment air return fans, TP/1/A/1200/11, against the description provided in FSAR sections 6.2 and 14.1 and the requirements specified in Regulatory Guide 1.68 Rev. O.
Based on this review, the inspector had the following comments on the proposed test:
The concept of utilizing a pipe support stanchion and a gunner's sight a.
level to verify that the pressure measuring pitot tube is vertical is acceptable provided that the data sheet requires signoff that the bubble has been checked in two orientations at right angles to each other and that the bubble was within an acceptable band in each orien-tation.
b.
The concept of taking a grid set of pitot tube pressure readings (6x8=48) and using the average of these readings as the final dis-charge pressure can be considered acceptable provided the licensee demonstrates that the inherent randomness in the fan's discharge pressure (turbulance effects) has been accounted for. Some items suggested for consideration were (a) repeatability of the average pressure value between different sets of readings, (b) how consistent are the values of the standard deviation uZ the discharge pressure, and (c) how repeatable is the fan's discharge pressure profile.
If the licensee demonstrates that the data and hence the pressure has a repeatable profile and is statistically consistant, the inspector has no further comments.
This item will be followed as Open Item 80-24-01.
7.
Preoperational Test Witnessing
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The inspectors witnessed the performance of two preoperational tests as well as monitoring the performance of the overall test program.
(a) The inspectors witnessed selected portions of preoperational test TP/1/A/1600/03, RPS System Functional Test. Also verified was that the copy of the test procedure being used was up-to-date, that the applicable plant conditions were in effect and that the test prereq-uisites were satisfied. Special Test Equipment needed for the test was examined for evidence of calibrations being current and the equip-ment being operable. The administrative controls regarding test interruption and resumption were observed and appeared adequate.
The test chronological log, an appendix of the procedure, was being maintained and it appeared to adequately document significant events, unusual conditions, test deficiencies and interruptions.
Test trew actions appeared timely and correct for the test situation.
Temporary modifications, such as jumpers or lifted leads were apparently adequately controlled by documenting them in the procedure or by the station's current administrative procedures.
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In all areas inspected, no items of noncompliance or deviations were identified.
(b) Also witnessed was preoperational test TP/1/A/1350/03, Unit Protection Relaying Functional Preoperational Test, The inspectors verified that an approved and current procedure was being used, that acceptance criteria were consistent with FSAR and technical specification require-ments, that plant conditions and test prerequisites were met, and that test equipment was within calibration dates and appeared to be func-tioning properly. During the performance of step 12.2.4.4.2 of the
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test, the response was not as specified in the test procedure.
According to the procedure, three alarm points should have been listed on the plant's event recorder; instead, only one was typed. When the test engineer investigated the problem, it was discovered that oaly the first alarm arriving will be printed. The test engineer stated that a test procedure change to delete the second and third items would be generated. The inspector will review the procedure change to verify that a second independent review concurs in the proposed change (deletion). Until that review is complete this will be considered Inspector Followup Item 80-24-02.
8.
Comparison of As Built Plant Safety Systems to FSAR Drawings The inspectors examined both trains of the following safety-related systems to determine if the as installed condition of the system corresponded to the configuration depicted in the FSAR:
(a) Decay Heat Removal MC-1561-1.0 (R7C018)
(b) Containment Spray MC-1563-1.0 (R9C016)
(c) High Pressure Safety Injection (Boron Injection Tank and cold leg injection lines)
MC-1562-1.0 (R7C016)
(d) Safety Injection Pump MC-1562-3.0 (R7CO20)
(e) Low Pressure Cold Leg and Hot Leg MC-1562-3.1 (R3C011)
Inj ection (f) Auxiliary Feedwater MC-1592-1.0 (R9)
-1.1 (R2)
(g) Upper Head Injection MC-1562-4.0 (R8)
These systems were initially traced and compared to licensee provided "as built" drawings. These controlled drawings were then compared to the FSAR figures.
Based on the number of systems traced to date, the inspectors concluded that many of the label plates are missing and that in most of these instances the valves involved are check valves, vent valves, or drain valves. A larger percentage of the instrument root valves are also not labeled. To date the following significant items have been identified to
the licensee for resolution:
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Auxiliary Feedwater check valve ICA-53 seal plate leaked
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Upper Head Injection MOV INI288A had motor operator missing
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Decay Heat Removal train A recirculation line does not originate immediately downstream of the heat exchanger but instead taps off of the ND to charging pump and safety injection pump suction line down-stream of check valve IND70.
Cold leg safety injection pump line throttle valves INI-488 and 1NI-386
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were installed upstream of the designated vent and drain valves.
Cold leg safety injection piping at the loop 2 junction has two series
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vent valves, 1NI-176 and INI-169 not shown in drawings.
The licensee has committed to correct the discrepancies above, to have the"as-built" drawings revised to reflect the actual conditions,,and will submit an FSAR amendment to correct the drawings in Chapter 6.
9.
Completed Preoperational Test Package Reviews Ten completed procedures were reviewed. The reviews included:
(a) verifying that all test procedure changes had been reviewed and approved by at least the test engineer's supervisor and, if the change altered the scope of the method of the test, that the change received a cross disciplinary review as well as a review by the SRC; b.
verifying that all test prerequisites were satisfied and signed prior to performance of the applicable portion of the test; verifying that all special equipment is listed by its identifiying c.
serial or tag number and calibration due information shows that it was in calibration during the conduct of the test; d.
verifying that all procedural steps had been initialed indicating performance or deleted by a procedure change, or documented as outstanding per a test deficiency; verifying that the test meets the acceptance criteria; and, e.
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verifying that all deficiencies identified during the test were either resolved and the necessary portions of the test repeated or are being resolved through an approved work request and that the retest require-ments listed on the work request are adequate.
The tests reviewed were TP/1/A/110,0/01 Controlling Procedure for Hot Functional Tests TP/1/A/1200/03B Upper Head Injection System Functional Test TP/1/A/1200/03C Safety Injection Pump and Flow Adjustment j
Functional Test
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-7-TP/1/A/1200/03D TP/1/A/1200/03E N1 Accumulator Functional Test Safety Injection System Check Valve Functional Test TP/1/A/1200/03F TP/1/A/1200/03G Upper Head Injection System Functional Test II Safety Injection Pump and Flow Adjustment
Functional Test II TP/1/A/1200/03H TP/1/A/1200/28 NI Accumulator Functional Test II INDIB/IND2A Auxiliary Power Supply Operability Test TP/1/A/1200/20 TP/1/A/1200/05A Equipment Hatch Leak Rate Functional Test NV system Functional Test-Cold Within the areas inspected, no items of ncncompliance or d identified.
eviations were 10.
New Fuel Storage blies stored in the spent fuel pool.The inspector monitored the lice uel assem-accordance with licensee approved periodic test PT/1/A/4550/03BThe ins accompanied a licensee engineer into the spent fuel pool and verifi d
. The inspector information he radioed to a second engineer who recorded it int e the Later the inspector compared the serial numbers recorded versus th o the PT.
fuel loading master index.
No discrepancies were noted.
e original The inspector was notified by the licensee that due to the prima being stored in the new fuel storage area, that they intended to d f ry sources installing additional fire detection instruments until aft e er were installed in the core.
er the sources always in the area and had been trained in how to alert the statiThey in the event of a fire.
who stated that, as long as there were personnel continuously iT on personnel and if the additional fire detectors are installed as soon as pr n the area following removal of the primary sources he had no objection t actical plans.
o the licensee's 11.
Containment Air Locks From the initial plant status meeting attended by the in or on August 4, air locks (PAL's) has been in question.
e personnel seals, seal failures and changes in seal design have been notedContinual replac changes have been continouusly made to the volumetric seal tightness t Also,
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equipment and questions of availability of vendor support have been rai est Due to the extended period which has elapsed with no resolution of a sed.
acceptable door'
of the entire personnel air lock should be performed once the n
is achieved.
This will be followed as Inspector Followup Item esign 80-24-03.
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