IR 05000289/1977022
| ML19256D309 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/28/1977 |
| From: | Kellogg P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256D305 | List: |
| References | |
| 50-289-77-22, NUDOCS 7910170817 | |
| Download: ML19256D309 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
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Region I t
Report No.
77_p9 Docket No.
50 9R4 License No.
Opp-50 Priority Category C
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Licensee:
htennolitan Edison Comoany P. O. Rnx 542 Readino. Pennsylvania 19603
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Facility Name:
Three Mile Island. Unit 1
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Inspection at: Middletown, Pennsylvania
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Inspection conducted-July 18-22, 1977 Inspectors:
d rd 7/2f/'77
<( P. J. Kellogg, Reactor Inspector dat'e signed
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date signed
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date signed Approved by:
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b 7/LP/77 A. B. Davis, Chief, Reactor Projects
/date' signed Section No. 1, RO&NS Branch Inspection Summary:
Insoection on June 18-22, 1977 (Recort No. 50-289/77-22)
Areas Inspected:
Routine, unannounced inspection of storage battery hydrogen monitoring capability; previot.ly identified unresolved items; followup on previously identified items of noncompliance; review of annual and 50.59 reports.
The inspection involved 33 inspector hours onsite by one NRC inspector.
Resul ts : No items of noncompliance were identified.
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Region I Form 12 7910170 (Rev. April 77)
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l DETAILS
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1.
Persons Contacted Mr. R. Barley, Lead Mechanical Engineer Mr. K. Bryan, Shift Foreman
- Mr. W. Cotter, Supervisor, Quality Control Mr. D. Deiter, Control Room Operator
- Mr. C. Hartman, Lead Electrical Engineer Mr. G. Kunder, Supervisor of Operations
- Mr. J. O'Hanlon, Unit Superintendent Mr. V. Orlandi, I&C Engineer
- Mr. M. Shatto, Engineer Arsociate III Mr. E. Sheets, Engineer II The inspector also talked with and interviewed n'ine other licensee employees during the course f the inspection.
- denotes those present at the exit interview.
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2.
Licensee Action on Previous Inspection Findings (Closed)Unresolveditem 289/75-24-01:
Pressure testing of fire hoses. The inspector reviewed procedure 1104-45, Fire Protection, Revision 15. The inconsistencies previously noted between Appendix B and the body of the procedure have been corrected.
(Closed) Unresolved item 289/76-24-07: Completion of corrective action for LER 76-33/3L.
Change / Modification 682 was not completed on the Westinghouse instruments.
The instruments were replaced by Rosemount Model 1152 Transmitters aad this information was contained in Amendment 28 to the Technical Specifications.
(Closed) Unresolved item 289/76-24-08: Technical Specification change for RCS pressure setpoints.
The licensee submitted a pro-posed Technical Specification change to NRR for new RCS pressure trip setpoints. Amendment 28 to the Technical Specification contained these new trip setpoints.
Subsequent review by the licensee indicated the flow rate for the pressurizer relief valves utilized in the bases for the new set-point was in error.
A flow rate of 280,800 lbs/hr should have been utilized vice the rate of 311,700 as is contained in the bases.
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The corrected flow rate has been analyzed by the licensee and appears acceptable. This item will remain unresolved pending submittal of a proposed Technical Specification change to NRR and the subsequent issuance of an amendment to the Technical Spec-ification (289/77-22-01). This information was reported to the NRC in LER 77-4/lT.
(Closed) Unresolved item 289/76-25-03:
Respiratory Equipment Inspection. The inspector reviewed the results of the HPP1616 survey of respiratory equipment for June and July 1977.
The re-sults iniicated the equipment was being maintained in an acceptable condition.
(Closed) Unresolved item 289/76-29-01:
Control of computer changes.
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The inspector reviewed procedure 1105-10, computer and software
change forms 1-3.
The procedure contains the requirements for review by the Nuclear Engineer prior to implementation of any software change which affects the NSS calibration.
The change form
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contains the reason for the change and a summary of the change.
t (Closed) Unresolved item 289/77-08-03:
Determination of baron
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concentration.
The inspector reviewed Revision 3 to CP1912.
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procedure now calls for another analysis to be completed if the baron concentration correction factor is greater than 3 ppm or the base differs from the unknown by greater than 15%.
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(Closed)Unresolveditem 289/77-08-04:
Revision of procedures 1302-5.27 and 1302-5.28.
The inspector reviewed Revision 6 of
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1302-5.27,1302-5.28,1301-6.5, and 1301-6.6.
These procedures now
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require a new alarm setpoint to be computed and set into the indication channels on the sodium hydroxide and sodium thiosulfate tanks.
(Closed) Unresolved item 289/77-09-07:
Snubber with empty reservoir.
(Closed) Unresolved item 289/77-09-08:
Snubber with corroded piston.
(Closed)Unresolveditem 289/77-09-0?.
Snubber with bullseye misoriented.
(Closed) Unresolved item 289-77-09-10:
Snubber with painted grease fittings.
These four items (77-08-07, 08, 09, and 10) are resolved by the licensee's surveillance program completed during the 1977 refueling outage.
All safety related snubbers were functionally tested during that outage.
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(Closed) Unresolved item 289/77-09-05:
Pipe restraint design basis.
The design basis for the piping restraint system was a dynamic analysis.
(Closed) Noncompliance 289/77-15-01.
Procedural nonadherence.
The inspector reviewed the revised procedure and the notes from the counseling session held on April 9, 1977.
The inspector had no further questions on this item at this time.
(Closed) Noncompliance 289/77-15-05:
Inadequate supervisory reviews.
The inspector held discussions with the facility staff and reviewed notes from a counseling session on supervisory reviews.
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The f *1spector had no further questions at this time.
l (Closed) Unresolved item 289/77-15-06:
Revision of SP 1303-4.11, i
High and Low Pressure Injection Analog Channels.
Procedure i
SP 1303-4.11 has been revised to include requirements for the
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notification of the reactor operator during the performance of
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the test at various specific points in the procedure.
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(Closed) Unresolved item 289/77-15-04:
TCN's to SP 1303-11.11.
Q Revision 5 incorporated the outstanding TCN's into the procedure.
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(Closed) Unresolved item 289/77-05-12: AP 1016 has been revised to include operational surveillance.
AF 1021 has been issued to
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cover plant modifications. AP 1021 contains provisions for sending modifications to the training department for inclusion in the training program.
(Closed) Unresolved item 289/76-01-01:
Reactor Building temper-ature.
The inspector reviewed the licensee's programs being conducted to evaluate and maintain Reactor Building temperature.
The inspector verified the actions required by NRR letter Reid to Arnold dated May 16, 1977 were in progress.
The inspector had no further questions at this time.
3.
Station Battery The inspector reviewed the station battery installation to establish the degree of hydrogen monitoring in conjunction with the use of large lead storage batteries.
The following findings were made:
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a.
The batteries installed are lead calcium LCU 19 manufactured by CSD batteries, Divi Ln of Eltra Corporation.
The batter-ies are all6 cell design with a fully charged specific gravity of 1.210 and a capacity of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1264AH to 1.71 volts at 77*F.
Two batteries are installed.
The approximate free volume for each battery (room is ll j00 b.
cubic feet.
This is the volume of the room 11,520 feet )
less the volume of the battery and other equipment installed in the room.
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Battery room air flow rates do not change for charging the battery.
The flow rates are 230CFM and 300CFM for room A and -
B, respectively.
Each room has one supply outlet over the i
center of the battery and one exhaust duct in the corner of the room.
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Hydrogen generation associated with the battery is not sampled
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by an instrument calibrated to detect hydrogen.
The exhaust
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from the battery rooms is mixed with several additional streams j
before being discharged. At the point of discharge, the air O
is sampled by a combustible gas detector.
No testing for hydrogen in the battery rooms has been conducted.
The licensee i
indicated that a test with a portable hydrogen detector /exploso-
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meter would be run during the next equalyzing charge.
This item is unresolved pending the subsequent review of the results of this test.
(289/77-22-02)
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The licensee currently performs the following checks on the batteries to determine general battery condition.
(1) Weekly The specific gravity, ICV's, temperature, and level of the four pilot cells; bank voltages, are total battery voltage (TBV).
(2) Monthly The specific gravity and ICV's of each cell; bank volt-ages, TBV, and charger float voltage.
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(3)
Refueling (Capacity Test)
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During this test, the following Acceptance Criteria
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apply:
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If ICV is lv or less, jumper out cell.
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In addition, the following checks were made:
All ICVs are taken hourly during the test discharge
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and at the end of the test.
All ICVs are taken hourly during the equalyzing
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i charge and at end of charge.
g All specific gravities are taken at end of charge.
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4.
Review of Periodic Reoorts The inspector reviewed the following reports to verify:
O the information required to be reported by NRC requirements
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had been included.
test results and/or supporting information discussed in the
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report are consistent with design predictions and performance specifications.
planned corrective action is adequate for the resolution of
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identified problems.
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if any information should be classified as an abnormal occur-
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rence.
The reports reviewed were the 1976 Annual Operating Report and the 197610 CFR 50.59 Sr.'ety Evaluation Report.
Findings were accept-able.
5.
Exit Interview The inspector met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on July 22, 1977.
The inspector summarized the scope and findings of the inspection as discussed in this report.
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