IR 05000328/1981020
| ML19350E775 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/03/1981 |
| From: | Burnett P, Fiedler R, Fielder R, Hunt M, Matt Thomas NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19350E763 | List: |
| References | |
| 50-328-81-20, NUDOCS 8106230511 | |
| Download: ML19350E775 (9) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION t
' s REGION 11 F
int MARIETTA ST., N.W.. SUITE 3100 V
ATLANTA. GEORGIA 30303
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Report No. 50-328/81-20 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name:
Sequoyah Nuclear Plant Docket No. 50-328 License No. CPPR-73 Inspection at Sequoyah site near Chattanooga, TN Inspectors:
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M. D. Hunt
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R. L. Fiedler
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Date Signed Approved by: [
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P.T Burnett, Acting' Section Chief Date Signed Engineering Inspection Branch Engineering and Technical Inspection Division SUMMARY Inspection on April 28 - May 1,1981 and May 5-8, 1981 Areas Inspected This routine, unannounced inspection involved 146 inspector-hours onsite in the areas of review of preoperational test procedures and test results evaluation, licensee action on previous inspection findings, licensee identified items and IE Bulletins.
Results Of the 4 areas inspected, no violations or deviations were identified.
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m REPORT DETAILS 1.
~ Persons Contacted'
Licensee Employees J. M. Ballentine, Plant Superintendent
~ G. G. Stack, Construction Project Manager
- J. M. McGriff, Assistant Plant Superintendent T. B. Northern, Construction Engineer
- E. A. _Condon, Preoperational Supervisor
' L. M._ McCloud, Nuclear Power QA Supervisor
J. M. Munns, Construction QA Supervisor-
- D. Kelly, QCRU Supervisor D. W. Mack, Assistant Constructior. Engineer
"M. R. Harding, Compliance Supervisor
- A. H. Gelston, Compliance Engineer
- D. P. Roberts, Compliance Engineer
- S. B. Miller, QCRU
- W. J. Glasser, QA Coordinator Other, licensee employees contacted included technicians and preoperational test' personnel.
NRC Resident Inspector E. J. Ford, Senior Resident Inspector S. D. Butler,' Resident Inspector
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- Attended exit interview 2.
Exit Interview
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The inspection scope and findings were summarized on May 1, 1981 and May 8, 1981, with those persons indicated in paragraph 1 above. Two new unresoi ted items and one new inspector followup item were discussed in detail.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Violation 328/80-23-01: Failure to correctly hydrostatic test Unit 2 RHR to acceptance. criteria. TVA has generated 12 NCR's as a result of a review of hydrostatic tests conducted prior to this find-ing.
Eleven of these NCR's have been reviewed by ENDES and have either _been accepted as is or required retests have been completed.
The remaining NCR involves piping which will be modified as a result of the hot functional testing. Work Plans will require flushing and hydrostatic testing after modification. This item is closed.
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(Closed) Violation 328/80-23-03:. Failure to control testing in that no site instruction prescribed cleanliness verification of instrument sensing lines. TVA submitted a final report to RII April 7,1981. SNP-Test 85.(accepted per NRC Regulatory Guide 1.84,. Rev.16, 5/80) for flushing and pressure testing sensing, sampling, control supply headers-and signal lines was completely revised and approved January 15, 1981.
The justification and test procedure modifications appear adequate.
This' item is closed.
c.
(Closed) Violation 328/80-23-04: Failure to follow QASP 7.1, require-ment for acceptable responses to QA audit findings. -The corrective-actions taken by the licensee as reported to RII April 7,1981 were reviewed. by the inspector and f9und adequate.
SOP 103 was revi. sed February 12, 1981, and TI No. 24 was revised January 2,1981.
Unresolved Items a.
(Closed) Unresolved Item 308/80-23-05: Licensee to determine if hydro-static tests ' demonstrated the design criteria were met. TVA cited ASME Code Case No. 240 which does not require testing of the suction line from the containment sump to the RHR suction shutoff valve.
5.
(Closed) Unresolved Item 328/80-21-04: No continuously recorded device was in use to monitor RCS temperature and pressure during hydrostatic tests. TVA construction had a locally mounted recorder connected to the following points: (1) center line of reactor vessel, (2) top of RV head flang, (3) RV below flange, (4) RV belt line region, (5) RV bottom head, and (6) pressurizer center girth area.
In addition to this chart record, temperature readings were recorded along with the pressure every 30 minutes. These records appear adequate in that the limits were listed and not exceeded per the records reviewed.
c.
(Closed) Unresolved Item 328/81-03-03: Records for penetrations con-taining bellows were missing. Pentrations containing bellows for which alignment documentation records were missing have been reinspected by the licensee. Penetrations found misaligned were documented on noncon-forcing condition report (NCR) 2655.
The inspector reviewed the penetration records and the licensee's resolution of NCR 2655. The NCR was evaluated by TVA's Division of Engineering Design and it was cetermined that the misalignment of these penetrations was not severe enough to require realignment and could be used as is. Penetrations with misalignments severe enough to require analysis by the vendor (Tube -Turns Inc.), have been analyzed (Tube Turns letter 74937Y-3 to TVA dated April-17,1981), and it was determined that these penetra-tions could be used as is. This item is closed.
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Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or. may involve violations or devia-tions. New unresolved' items identified during this inspection are discussed in paragraphs 6 and 8.
5.
'IE Bulletins (IEB)
a.
(Closed) IEB 80-05: TVA's response dated June 9,19EO indicated that the evaluations required had been completed. All tanks e'xcept the RWST are located inside the auxiliary or reactor buildings, b.
(Closed) IEB 80-09: TVA's response dated February 27, 1981 indicates that there were no Model AH-90 or NH-90 actuators supplied for Unit 2.
C Licensee Identified Items (LII) 10 CFR 50.55(e)
a.
(Closed) LII 328/80-09-11: Auxiliary P4 response time. Region II was notified of this deficiency April 15, 1980 and TVA submitted a. final report January 21, 1981. Work Plan S1410 completed 4/14/81 covered the necessary modifications to speed up the stroking time for valves 2LCV-3-148,156,164, and 171.
b.
(Closed) LII 328/81-02-01: Incorrect insulation weight. TVA submitted
~a final report April 8,1981. Thirty-five hangers were modified under work plans S1461 and S1328 which were completed April 14, 1981. The inspector reviewed these work plans, which appeared adequate.
c.
(Closed) LII 328/81-02-24:
Stress corrosion cracking on RCP oil cooler. TVA submitted a final report March 27, 1981.
The inspector reviewed records which were developed to cover the eddy current testing and plugging of tubes in question. These actions appear adequate.
d.
(Closed) LII 328/80-09-08:
Overstressed U-bolts on 3/4-inch drain lines. TVA submitted a final report dated May 1,1980. Work Plans 8611 and 8611R1 were reviewed for the work on Unit 2 and found ade-quate.
e.
(Closed) LII 328/80-09-10: Error in analysis of two-inch containment-spray test lines.
TVA's response dated May 15, 1980 described the corrective actions required to correct this condition. The Work Plans covering the hanger modifications and addition of hangers HCI-M-2 and i
HCI-M3 were completed February 26, 1981.
f.
(Closed) LII 328/81-02-22:
(NCR 2436) Under pressurized hydrostatic test.
This item was reported November 26, 1980 and a final report submitted February 3,1981. Twelve closed nonconforming reports
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identifying this condition were reviewed by the ' inspector. All 12 NCRs had been evaluated and the results either justified as is or acceptable retesting was conducted. This item is closed.
-g.
(Closed) LII 328/81-02-34 (CEB 8041): Analysis of steel containment penetration assemblies.
TVA reported this item to RII. December 19, 1980. The final report dated April 7,1981 advised that reanalysis of piping stresses and support designs determined that no modifications are required.
h.
(Closed) LII 328/80-09-07 (NEB 8007): Upper head ' injection hydraulic isolation valve accumulator weighing system. This item was reported to RII March 25, 1980. The revised final report was dated March 12, 1981.
In addition to the surveill...ce required by administrative procedure SI-2 there is an annunciator alarm for the accumulator low pressure.
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-(Closed) LII 328/79-21-08 (MEB 7926): Diesel generator turbocharger thrust bearing lubricatton.
The licensee reported this deficiency June 20, 1979.
The final report dated October 4, 1979 advised that revisions to SOI 82.18, 82.28, 82.38, and 82.48 limit unnecessary starting of the diesels between 15 minutes and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> following shutdown, except for an emergency start signal. Discussions with the licensee representatives indicate that to date no modifications have.
been made to overcome this problem. This will be identified as an open item 328/81-20-24.
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(Closed) LII 328/80-09-09 (EEB 8003): Environmental qualifications of pressure transmitters.
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(Closed) LII 328/81-01-01 (EEB 8006): Environmental qualification of steam generator level transmitters.
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(Closed) LII 328/81-01-02 (EEB 8008), (EES 8006):
Environmental qualification of selector switches.
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(Closed) LII 328/81-01-04 (EEB 8009, 8010, 8011, 8012, 8013, 8014, 8015, 8019), (EEB 8006):
Environmental qualification of Class IE equipment.
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(Closed) LII 328/81-02-15, (EEB 8023-8033, 8035-8038, 8008, 8040, 8041, 8044): Environmental qualification of equipment.
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(Closed) LII 328/81-02-27 (EEB 8044, RI): Environmental qualification of electrical equipment.
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(Closed) LII 328/81-20-23 (EEB 8102, 8104, 8105):
Environmental qualification of valve liinit switches.
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(Closed)'LII 328/81-20-17 (NEB 8110):
Environmental ' qualification of r.
control cables in the Emergency Gas Treatment System compartment. The eight licensee identified items above relate to equipment addressed in NUREG-0588, " Interim Staff Position on Environmental-Qualification of Safety Related Electrical Equipment". NUREG-588 set forth the require-ments for identification of all class IE equipment, categories of environmental conditions, types of equipment in each category, qualifi-cation test plans and identification of qualification documentation.
These positions are applicable only to plants that are or will be in the construction permit or operating license review process.
The inspector reviewed a sample computer program designed to maintain the status of equipment with limited life span that will identify when components require replacement.
RII will continue to review these commitments as open item 328/81-20-04, Licensee commitment to NUREG-0588.
The following licensee identified items have been reported to RII by TVA:
a.
(0 pen) LII 328/81-20-05 (NEB 8103), Limit switch actuator for mason-eilan air operated valve.
b.
(0 pen) LII 328/81-20-06 (NCR 2547) Reactor vessel field welds c.
(0 pen) ' LII 328/81-20-07 (MEB 8006 RI), Excessive pressure drop across ERCW strainers.
d.
(0 pen) LII 328/81-20-08 (MEB 8112), Geared limit switch cover melting in electrc,Jyne MOV's.
e.
(0 pen) LII 328/81-20-09 (NEB 8110), Blown fuse alarm in auxiliary control circuits.
f.
(0 pen) LII 328/81-20-10 (EEB 8109), Non-IE containment airlock elec-trical penetration.
g.
(0 pen) LII 328/81-20-11 (SWP 8107), ERCW system flow deficiencies.
h.
(0 pen) LII 328/81-20-12 (NES 8115), Possible error in SI system pre-operational test.
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(0 pen) LII 328/81-20-13 (M-80-11), Procurement control activities.
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(0 pen) LII 328/81-20-14 (NES 8117), Inconsistency in the establishment of the inspection program, k.
(0 pen) LII 328/81-20-15 (SWp 8112), Spacial separation for conduit and cable trays.
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(0 pen) LII 328/81-20-16 (EEB 8114), Degraded grid voltage time delay.
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(Open) LII 328/81-20-18 -(CEB 8108), Foam seals in mechanical pipe
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(0 pen) LII 328/81-20-19 (MEB 8122) Power operated relief valve opera-ting time.
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-(0 pen) LII 328/81-20-20 (NEB 8123), Containment H2 analy::er.
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(0 pen) LII 328/81-20-21 (EEB 8111), Nameplate rating for 460 volt IPoto rs.
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(0 pen) LII 328/81-20-22 (EEB 8115), Degraded voltage requirements for 460 volt motors.
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(0 pen) LII 328/81-02-11, SIS Train B Flow Deficiency (SQNNEB8025).
During preoperation test W-6.1E of SIS system performance the licensee found that.the train B cold leg injection rate for all four legs simultaneously was deficient. This was reported to IE:RII as a-licensee identified item (LII) under 10 CFR 50.55(e). The deficiency was resolved by changing the RHR heat exchanger outlet valve openings (originally designed to be 60 open) to 79* open. The licensee stated in the revised final report to the LII (IE report item no. 328/81-02-11) dated November 26, 1980, that
"...TVA's Division of Nuclear Power has been informed to incorporated procedures for verifying that the valve discs are set at 79..."
While reviewing this item the inspector found that the requirements for setting. the valve openings are indicated on the design. drawing (vendor drawing H-11051RO), and a field change notice (FCN) is necessary to revise the drawing. However, the drawing still indicates the valve opening be set at 60* and the inspector could find no information indicating a FCN had been initiated to revise the drawing to reflect the design change. There is no assurance that the valve openings will be set at 79* instead of 60* when maintenance is performed on the valves. This will be identified as unre-solved item 50-328/81-20-03, Setting of Valve Openings Following Mainten-ance.
7.
Loss of Offsite Power (LOP) Test The licenses had developed two preoperational test procedures to cover LOP testing. These were:
TVA-138(1)
TVA Onsite AC Distribution System TVA-138(2)
TVA Onsite AC Distribution System i-i i
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The tests were performed during the period August 1980 to October 1980 and were.not witnessed by NRC.
Review of the completed test results by ENDES had not been completed at the time of this inspection. Additional review by
'the inspector will be accomplished during a subsequent inspection.
Within the area examined, no violations or deviations were identified.
8.
Review of Engineered Safety Features Testing The following preoperational tests were reviewed to verify that the tests adequately address NRC requirements and licensee commitments relating to Engineered Safety Features.
a.
- TVA-13B(2)
TVA 0nsite AC Distribution System b.
W-06.01A1 SIS Integrated Flow Test c.
W-06.1C SIS Centrifugal Charging d.
W-06.10 SIS Safety Injection As a result of the review of the above tests, which had not received final results approval and had numerous unresolved deficiencies; and discussions with preoperational ' testing personnel it was determined that the commitment in Table 14.1-1 of the FSAR for an Integrated System Test has not been met and that there were no plans at present for such an Integrated System Test.
This discrepancy in the testing program was brought to the attention of the plant manager on May 7,1981.
The Plant Manager stated that it was his position that che present testing program was adequate.
This is an unre-solved item (UNR 328/81-20-01).
Valve testing performed during the conduct of the above test was performed without any associated pumps in operation which appears to be contrary to the guidance of Regulatory Guide 1.79 which requires valve operation under maximum expected differential pressure conditions.
This is an inspector followup item (IFI 328/81-20-02).
9.
Preoperational Test Procedure Review (Component Cooling System)
Test TVA-20A covers the manual operation of the component cooling system (CCS) motor operated and air operated valves; opening and closing stroke times of the CCS motor operated valves; automatic response of CCS pumos 2A-A, 2B-8, and C-B (B-train power feed) to a Unit 2 safety inject'-
signal and to a loss of voltage and blackout; automatic response of CCS p 3 C-S to a Unit 1 safety injection; automatic response of CCS pumps 2A-A ano 28-B to a low discharge header pressure signal; manual control of thermal barrier booster pumps 2A-A and 2B-B from all control stations; and automatic response of thermal barrier booster pumps 2A-A and 2B-B to a low discharge flow signal, flow differential signals, and under voltage and blackout.
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The inspector reviewed the test precadure to verify that NRC requirements, licensee commitments and important systein performance functions are ade-quately reflected in the test procedure.
10.
Preoperational Test Procedure Verification The inspector verified that a preoperational test procedure has been writ-ten, reviewed and approved for each of the following areas or systems:
Area / System Test Procedure Cold and Hot Flush of Systems TVA Construction Leak Detection TVA-01 In-Service Inspection TVA Constructi:,n Containment Building TVA-02A,02C,098 Auxiliary Building-TVA-09A,09C Instrument Air System TVA-27 Electrical Systems TVA-13B(1),138(2)
Refueling Equipment W 7.1, 7.2 Storage Equipment W 7.1
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Fuel Handling and Fuel Storage System W 7.1, 7.2 Fire Protection System TVA-25A,258,25C Reactor Vessel Head Cooling TVA-07 Hydrostatic Test TVA Construction Some of the above preoperation test procedures, along with those for other areas / systems, are addressed in other sections of this report, and will be addressed in future IE reports.
11.
(Closed) Inspector Followup Item 328/80-06-09, Audit of the Fire Protection QA Program at Unit 2.
The inspector reviewed the following QA audit reports relating to the fire protection program for Unit 2:
SN-E-80-06, Cable Tray Covers and Flamemastic Application, RB #2, SN-E-80-10, Examination of Installed Cables and Flamemastic Application, SN-G-80-10, Fire Protection System, SN-M-80-15, Sealing of Pipe Sleeves.
The inspector verified that resolution of the audit deficiencies and the
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corrective actions taken by the licensee were acceptable.
This item is closed.
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