IR 05000346/1977025
| ML19329B617 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/09/1977 |
| From: | Knop R, Shafter W, Tambling T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19329B419 | List: |
| References | |
| 50-346-77-25, NUDOCS 8002050734 | |
| Download: ML19329B617 (11) | |
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j U.S. NUCLEAR !:ECtfLATORY COMMISCION 0FFICE OF INSPECTION AND ENFORCEMENT
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REGION III
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Report No. 50-346/77-25 I
Docket No. 50-346 License No. NPF-3 Licensec:
Toledo Edison Company Edison Plaza 300 Madison Avence Toledo, OH 43652 Facility Name: Davis-Besse Nuclear Pcwer Station, Unit 1 Inspection At:
Oak Harbor, OH Inspection Conducted:
July 19-21, 27-29; August 5, 6, 8-12, 18, and 19, 1977 8 0 $w, f., --
7!72 Inspectors:
T. N. Tambling
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W. D. S fe i
L. R. Greger Approved By: R. C. Kn Ch M
Reactor Projects Section 1
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Inspection Summary Inspection on July 19-21, 27-29; August 5, 6, 8-12, 18, and 19, 1977
,TReport No. 50-346/77-25)
i Areas Inspected:
License prerequisites required prior to entering Mode 2 and Mode 3 of operation, status of deferred preoperational testing, witnessing of initial criticality and zero power physic testing, review of licensee event reports, review of status of radiation protection, and radwaste program for startup testing. The inspection involved 137 inspector-hours onsite by three NRC inspectors.
Results:
No items of noncompliance *or deviations were found.
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DETAILS SECTION I
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Prepared By:
T. N. Tambling 1.
Personn Contacted
- J. Evans, Station Superintendent
- T. Murray, Assistanc Station Superintendent
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- D. Zemenski, Operations Engineer
- L. Stalter, Technical Engineer L. Grime, Reliability Engineer D. Briden, Chemistry and Health Physicist
- W. Creer, Assistant to Station Superintendent
- J. Buck, Operations Quality Assurance Engineer G. Humphreys, Instrument and Control Engineer
- R. Brown, Assistant Engineer l
- G. Novak, Power Engineering General Superintendent D. Lee, Test Program Manager (B&W)
T. Reddaway, Project Start-up Engineer (Bechtcl)
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The inspector also talked with and interviewed other licensee employees, including members of the technical and engineering staff, reactor shift crews, radiation protection, training, startup test leaders, and QC personnel.
- Denotes cho'se attending exit interviews.
2.
Licensee Action on Previous Inspection Findings d
(Closed) (346/75-23):
Licenece to develop a list of safety-related componete.s systems and activities to which the QA program is applic-able.
The inspector verified by review of revisions to the Quality Assurance Manual, that the licensee had developed reference lists of safety-related and ASME components systems and activities to which to QA progran is applicable.
(Closed) (346/77-05):
Licensee to provide an emergency plan imple-menting procedure to cope with weather conditions which require personnel to remain at the station for undetermined periods.
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Condition F.1.s of Attachment 2 to License NFP-3).
The inspectu, verfied that an appropriate revicion to the Emergency Plan impicmer...g precedures had been made and issued.
(Cloced )(346/77-05):
Licencee.t.o incorporated into the Ecurgency N
Plan inplementing procedures (!) evacuation of personnel to
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minimize exposure to hazard, (2) a personnel accountability system, and (3) conditions for re-entry into previously evacutated areas
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for search and rescue (also Condition F.1.b of Attachment 2 to
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License NFP-3).
The inspector verified thot appropiate revisions j
to the Emergency Plan impicmenting procedures had been made and
issued.
3.
Completed and Appecved Test Procedure Results The inspectors reviewed the following deferred preoperational test procedures for cocpleteness with regard to:
Meeting acceptance criteria.
a.
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b.
Appropriate management review and approval.
Confornances to the requirements of administrative procedures.
c.
The review of the deferred sections of the test packages included review of temporary and major procedures changes, QC verification sheets, chronological logs, resolution of deficiency reports and other related material.
Contaimsent H Dilution and Hydrogen Purge System TP 161.02 gx
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Boric Acid Evaporator Acceptance Test TP 230.03
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Main Steam Isolation Valve Test TP 271.09
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Station Response to Loss of Instrument Air TP 256.01
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i Steam and Feedwater Rupture Control System TP 315.01
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TP 330.04 - Control Rod Drive Integrated Test TP 340.01
- Seismographic Monitoring System Makeup and Purification System TP 600.04
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Auxiliary Feedwater System and Steau Cenerator Level TP 600.11
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TP 600.14 - Reactor Coolant System Expansion and Restraint Test Power Conversion System Expansion and Restraint Tests TP 600.19
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Reactor Non-Nuclear Instrumentation Calibration Test TP 600-15
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~s TP 600-17 CRD System Operational Test
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Outstanding Preoperational Tests Three defered pre-operational tests are not complete:
Freeze Protection System TP 261.02
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i TP 401.11 Instrument Ground Grid System i
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Communication Test TP 100.01
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Gn TP 261.02, heat tracing on the pressurized relief valves liquid i
seal loops rnd the nitrogen fill liner to the pressurizer and core e
floed tank are being upgraded.
Temperature obtained on the press-urizer relief loop seals were in the range to restrict the number of valve actuations to 30 dische ge cyc1cs (See LER NP-32-77-12 dated August 19, 1977 for details).
The licensee will track the number of cycles and also plans to upgrade the heat tracing.
On the nitrogen fill liner to the pressurizer and core flood tank the licensee will administratedly control the use of this line until the heat tracing is upgreded to provide the desired temperature Os control. The licensee commited to provide instructions to the Ti' eld to monitor and control the line temperature during use.
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On TP 401.11, the licensee could not meet the acceptance criteria of a electrically separate instrument ground system when the tie lick to the station ground syst'em was removed.
(See letter L. S. Roe to J. C. Keppler, dated August 3, 1977, Serial No. 339).
This was due in part to the instrument system supplied by Babcock and Wilcox Company and Bailey Meter Company which was not installed to have separate instrument and station ground.
The licensee has proposed to delete the test as a requirement.
The licensee's request is currently under review. The licensee was informed that resolution on this test is a restraint to Mode 1 operation.
On TP 100.01, the licensee has completed all but the phase of the test dealing with the Turbine Building.
Final balancing of the system is planned when the e.urbine is put into operation.
The licensee stated in an exit interview that this phase of the test would be completed prior to exceeding 25% power.
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Bcron Dilution Mode Tesc As a previous commitment in the FSAR the licensee has installed by-pass lines around valves DH 1517 and DH 1518 to provide a mininum decay heat flow of 40 gpni during a post LOCA condition to provide a means to reduce boron buildup in the reactor core.
To verify that these lines had been properly sized to provide a minimum of 40 gpm (Condition F.4 of Actachment 2 to License NPF-3), the inspec-tor reviewed TP 203.03, Decay Heat Removal System Preoperational Test, Section 7.11.
Based upon simulated post LOCA flow con-ditions, the test results indicated that minimum measured flow was greater that 40 gpm in each decy heat loop (40 to 50 gpm).
This measured ficw rate satisfies the design requirements.
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6.
Review of Nonroutine Events Reported by the Licencee The inspector reviewed licensee actions with respect to the fellow-ing listed nonroutine events reports to verify that the events were reviewed cnd evaluated by the licensee as required by Techni-cal Specifications, that corrective action was taken by the licensee, and that safety limits, limiting safety system settings, and limit-ing conditions for operation were not exceeded.
The inspector c::amined selected Station P.eview Board minutes, licensee investigation
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reports, logs, and recorde, and inspected equip.nent and inter--
viuwed selected personnel, Failure to establish required communications, monitoring, a.
and supervision during installation of incore detectors (NP-32-77-01).
b.
One Containment Radiation SFAS outside LCO due to operator error (NP-32-77-04).
c.
Loss of Decay Heat Systen flow due to unauthorised work on pressure transmitter (NP-32-77-9).
d.
Failure of butter fly valve seats in the Component Cooling Water System (NP-32-77-10).
e.
Failure to reset RPS high flux setpoint to < 5% while in shutdown bypass (NP-33-77-8).
f.
Seismic Trigger firing puriously (HP-33-77-13).
The inspector noted that the licensee had identified and corrected four items with the Technical Specifications related to these events.
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No other items of noncompliance or deviations were identified.
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During the exit interview the inspector discussed the number of '
events associated with personnel errors and the need for the licensee to reduce these.
Also the licensee was requested to submit a supplement report to LER NP-33-77-13, on the investigation of the failure cause in accordance with Regulatory Cuide 1.16.
This supplemental report was submitted August 16, 1977.
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The following licensee event reports were reviewed and closed out on the bases of an in-office review and evaluation:
a.
Momentary loss of audible indication on source range detector (NP-33-77-3).
b.
Containment radiation channel inoperable (NP-33-77-4)
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Loss of Panel 41 and SF.\\S Channel 1 during naintenance (NP-33-77-10).
d.
Failure of wind speed indicator (NP-33-77-12),
c.
Failure of Containment Personnel airlock door to latch (NP-33-77-18).
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Two hydraulic snubbers in Decay Heat Recoval Syctcc inoperable (NP-33-77-19).
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Containment Sump level and flow monitoring inoperable (NP-33-77-20).
h.
Contaiment Spray Pump 1-1 surveillance instrumentation out of calibration (NP-33-77-21).
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Removal of makeup pump 1-1 from service to perform maintenance on suctiun valve (NP-33-77-23).
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Removal of makeup pump from service for corrective maintenance (NP-33-77-24).
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De-emergized "J" bus to complete modification (NP-33-77-27).
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7.
Design Deficiency in Shield Building Blowout Panels, LER NP-32-77-7
l The inspector reviewed the licensce's report dated July 25, 1977, and the corrective action (FCR 77-152).
During this review it was noted that the blow out panel setpoint (i.e., the pressure at which the panel would relieve) was not an Q-listed item. This was due f' x
.in part that the pancis were installed for a feedwater line rupture i
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protection and not censidered a boundry of the Emergency Ventilation
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System.
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V The licensee commited to the following:
a.
To Q-list the blowout panci de -ign and setpoint.
b.
Demonstrate that the. current repair meets QA/QC requirements, c.
All future work,n the blowout panels will have QA/QC involvement.
Based on the action taken and the commitments made by the licensee, the inspector concluded that the corrective action taken by the licensee appears to be adequate.
8.
Seismic Qualified Flow Indication for Low Pressure and High Pressure Injection System Per Condition C.(3)(m) of Operating License NPF-3, the licensee modified the existing low pressure and high pressure injection flow indication system to one wh?ch was seimically qualified and powered from essential power sources with flow indicatior, in the main control room.
The inspector reviewed QC documentation (FCP-97) en the procurement, installation and calibration to verify that the subject flow indication systems had been seismic qualified, installed, and calibrated in accordance with the commitment.
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9.
Diccel Oil Storage Tai.k Modification.
Per Condition C.(3)(b) of Cperating License NPR-3, the licensee modified the diesel fuel oil etorage and transfer system to provide each diesel generator with a 40,000 gallon seismic Category 1 fuel oil storage and transfer system.
Final tie into the new system is subject to a licence amendment.
Tha inspector reviewed and examined the implementation of the subject modification as designated en Bechtel drawing change notice No.
C-37-1 for Job No. 7749.
No deficiencies were identified by this review.
The review effort included review and examination of procurement records, engineering calculations relative to design requirements, earth compaction records for burial portions of the system, pro-tective coating tests for steel plates used for missile shields, (Close out of NCR 1232) and construction testing.
10.
Natural Circulation Test
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The licensee raised the question as to whether Condition 3 (a) of the operating licensee was in conflict with the test exception o'
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in Section 3.10.3 of the Technical Specifications regarding the number of reactor coolant pumps required in Mode 1 and Mode 2 operation.
The inspector conferred with the Project Manager in NRR and it was concluded that Section 3.10.3 provides the required centrol for performance of the Natural Circulation Test without operatinF reactor coolant pumps during the performance of the test.
1.1.
Preparations for Initial criticality The inspectors reviewed the prequisites requirements for initial criticality covered in the operating license (Paragraphs 2, 5, and 8), status of deferred preoperational tests (Paragraphs 3 and 4) and tour of the plant and control room.
The tour of che plant included a walk-through the plant to observe operations, housekeeping, status of operating equipment, chec>
of ventilation boundaries, doors, and locking of control cabinets in remote areas.
i Tour of control room included discucsions with the operators concerning status of outstanding annunicator lights, out of service equipment, boration paths, operating parameters, on
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going surveillance testing, :nd rev#.aw of operating logs.
Y No items of noncompliance or deviations were identified.
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12.
Initial Review of Zero Power Physic Testing (ZPPT)
The inspector examined the control copy of TP 710.01, ZPPT and observed testing in progress for a temperature coefficient of reactivity.
The inspector verified that analysis of data was being kept current (although it was preliminary in nature).
All results to date appeared to be within acceptance criteria.
No items of noncompliance or deviations were identified.
12.
Exit In te rview
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The inspector met with licensee representatives (denotes in Paragraph 1) at the conclusion of _ the inspection on July 21 i
and August 19, 1977.
The inspector summarie-d the scope and findings of the inspection.
The licensee representative made the following remarks:
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Acknowledged the statements by the inspector with respect
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to nonroutine event reports and the noncompliance reported l
and corrected by the licensee.
(Paragraphs 6 and 7)
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b.
Acknowledged the inspcetors statements concerning the
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natural circulation test.
(Paragraph 10)
c.
Acknowledged the inspector scutemen::s concerning the close out of conditions of the operating license.
(Paragraphs
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I d.
Acknowledged the inspectore statements concerning outstand-
ing preoperational tests.
(Paragraph 4)
a e.
The licensee stated that ZPPT shculd be completed August 20,
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1977, with final analysis and review of the data completed
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early the next week.
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DETAILS b
St.CTION II
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['//77 Prepared By:
L.
R. Gre er Wxnk
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Reviewed By:
W. L. Fisher, Chief 7 [77
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Fuel Facility Projects and Radiation Support Section 1,
Persons Contacted i
W. Alton, Senior Assistant Engineer
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D. Briden, Chemist and Health Physicist J. Evans, Station Superintendent W. Green, Assistant to Station Superintendent J. Hickey, Training Supervisor D. Lee, Test Program Manager
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Zell, Assistant Engineer 2,
Radiation Protection /Radwaste ?rocedures The radiation protection and radwaste related procedures for startup and power ascension testing have been completed and are
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ready for implementation.
Review of these procedures by the inspector did not identify any significant discrepancies.
De test results will be revieued during a subsequent inspection.
No items of noncompliance or deviation.= were identified.
3, Radiation Protection /Radwaste Preoperational Testing The inspector selectively reviewed the licensee's radiation protection, radwaste, process monitor, and ventilation related preoperational test results.
The licensee was noted to have completed the preoperational testing required for initial criticality (Mode 2).
Additional testing, to be completed during startup, will be reviewed during subsequent inspections.
The, additional testing to be completed is identified in the FSAR, in correspondence from the licensee to NRR dated February 22, 1977 and March 2, 1977, and in Attachment No. 2 to NRC License No. NPF-3.
No items of noncompliance or deviations were identified.
4, Startup Source Leakage
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The inspector reviewed documentation from the startup source
's supplier regarding material specifications cnd initial leak
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test results.
The use of thoristed tungsten in the source
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welding process was confirmed by the supplier.
Such use plausibly sN- '
explains the protactinium-233 identified by the licensee in the fuel pool water.
The supplier's leak test prncedures, apparently not as sophisticated as those utilized by the licensee, did not detect the activation nuclides originating from the encapsulation material.
No significant discrepancies in the licensee's evaluation of radionuclide analyses of the startup sources were identified.
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.No items of noncompliance or devia*. ions were identified.
5.
Ventilation Stack Samplers The inspector reviewed the results of the collection test conducted as a check of the efficiency of the ventilation stack samplers.
A polydispersed DOP (dioccyl phthalate) mixture was released in a ventilation line.
Simultaneous samples were extracted from the ventilation stack and the ventilation stack sampler and compared.
The test, performed by contract personnel, showed a one-to-one re:ationship betueen the two semple points according to the licensee.
The licensee did not have documentation to identify the extraction points nor was the accuracy of the quantitative results specified.
Licensee personnel stated that additional documentation of the test would be procured from the contrcc organization.
This documentation will be reviewed during a subsr.quent inspection.
C Uo itcas of neucomplicnce or d'eviations were identified.
6.
Respiratory Protection The licensee has not completed the required modifications to bring the respiratory protection program into conformance with Regulatory Guide 8.15 and, therefore, cannot take credit for the use of respiratory protection equipment ~ in estimating exposures of individuals to airborne radioactive material.
No items of nonecmoliance or deviations were identified.
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