IR 05000289/1977027
| ML19256D215 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/20/1977 |
| From: | Caphton D, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256D200 | List: |
| References | |
| 50-289-77-27, NUDOCS 7910170714 | |
| Download: ML19256D215 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
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Region I aport No.
77 ;7 Docket No.
50-289 License No.
DPR-50 Priority Category _ C
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Licensee:
Metrooolitan Edison Comoany P. O. Box 542
Readina, Pennsylvania 19603 Facility Name:
Three Mile Island Nuclear Power Station Unit 1 Inspection at:
Middletown, Pennsylvania Inspection conducted:
Auguth30 -gber 2,1977
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Inspectors:
lh Wlldb}'
T/$D/77 T. F. St'etEa, Reactor Inspector date signed
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{j date signed date signed i
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Approved by: \\
24/ 7 '7 D.L.Cappon, Chief,Nc3HearSupport dpesffgned'
Section No. 1, RO&NS Bfanch i
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Inspectir,n Summary:
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Inspection on August 30-September 2,1977 (Report No. 50-289/77 27)
Areas Inspected:
Routine, unannounced inspection of licensee strike plans;
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post refueling plant operations; post refueling Startup Report; licensee action on previously identified unresolved items.
The inspection involved 23 inspector hours onsite by one NRC inspector.
Results:
Of the three areas inspected, no items of noncompliance were found in two areas; one item of noncompliance was identified in one area (infraction-use of superseded procedures to perform operations and surveillance-paragraph 4c).
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Region I Fonn 12
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(Rev. April 77)
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DETAILS
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Persons Contacted Principal Licensee Employees
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- Mr. M. Bezilla, PORC Administrator i
Mr. D. Good, Technical Analyst III - Nuclear
Mr. W. Heysek, QC Specialist l
Mr. J. Hilbish, Station Nuclear Engineer i
Mr. G. Kunder, Operations Supervisor l
Mr. G. Miller, Station Superintendent
- Mr. J. O'Hanlon, Unit 1 Superintendent Mr. V. Orlandi, I&C Engineer The inspector also interviewed eight other licensee employees
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during the course of this inspection.
They included scheduling personnel, a nuclear engineer, reactor and auxiliary operators, and general office personnel.
- denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (0 pen) Unresolved Item (289/76-29-02): The licensee has developed a draft procedure IC-56, calibration of Heat Balance Instrumen-tation, that will be used to calibrate the computer input channels.
The licensen stated that this procedure will be reviewed and approved by the end of September,1977.
The inspector verified by review of completed data sheets, that these computer input channels were calibrated during the past refueling outage (March 19-May 16, 1977). These calibrations were conducted during the period of March 28 to April 20, 1977.
3.
Licensee Strike Planning
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The inspeci:or arrived on site, unannounced, at 8:00 a.m. on August 30; a labor un'on picket line tss visually observed at the north
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gate site entrance.
The inspector discussed the picket line with licensee management personnel ii cluding actions taken or planned.
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The licensee stated that the picket line was the result of a dispute between the Operating Engineers Union and a licensee contractor, Catalytic Inc.
The licensee's union employees scheduled to relieve the backshift were honoring the picket line and were not reporting to work.
The back shift personnel were being held on shift until the licensee could remove the picket line, which was expected to occur by 11:00 a.m.
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At 11:15 a.m. the picket line was removed and licensee union personnel began reporting for work.
By 1:00 p.m., licensee activities had returned to normal.
The inspector disctissed staffing requirements with the licensee. No j
inadequacies were identified, j
4.
Post Refueling Plant Opert.tions
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a.
The inspector reviewed facility records (see below) to deter-mine the following:
Systems disturbed during the refueling outage were
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returned to service in accordance with approved pro-cedures;
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Control rod withdrawal authorization was received prior
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to startup after refueling; and Weekly, biweekly or monthly surveillance tests were per-
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formed during the refueling outage as required by the Technical Specifications.
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b.
The following operations and surveillance procedures were reviewed to verify the items identified in 4.a above.
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0peratiens Procedures
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(1)
OP 1104-4, Decay Heat Removal System, Revision 12 per-
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formed May 8, 1977.
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(2) OP 1104-2, Makeup and Purification Demineralization, Revision 17 performed May 6-16, 1977.
(3)
1303-9.2, Control Rod Program, Revision 9, completed on May 9, 1977.
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(4) 1102-1, Plant Heatup to 525', Revision 23, completed on May 16,1977 (5)
1102-2, Plant Startup, Revision 23, completed on May 21, i
1977.
I (6) 1103-8, Approach to Criticality, Revision 5, completed on
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May 13, 1977.
i Note:
Startup authorization; shutdown margin verification j
and estimated critical rod postion (ECP) are performed in conjunction with procedures 1102-2 and 1103-8.
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c.
Surveillance Procedures (1) The emergency sequence loading test and high pressure and low pressure injection component tests are required by TS 4.5.1.2 and 4.5.2.4 respectively to be performed quarterly and is accomplished by surveillance procedure 1303-5.2, Loading Sequence and Component Test and HPI Logic Channel,
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Revision 8.
Data was reviewed for test performed January m
6,1977; May 9,1977 and July 13, 1977.
(2) Spent fuel pool sampling for boron is required by TS Table 4.1-3 to be performed monthly and is accomplished by surveillance procedure 1301-5.7, Spent Fuel Pool, Revision 1.
Data was reviewed for sampling performed Feburary 19,1977, March 21,1977, April 21,1977 and May 21,'1977, (3) Reactor coolant sampling for baron is required by TS Table 4.1-3 to be performed two times a week 3.nd is accomplished by surveillance procedure 1301-3, Reactor Coolant System, Revision 2.
Data was reviewed for sampling
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performed March 7,14, 21, 28,1977; April 5,11,18, 25, j
1977; and May 2, 9, 16, 23, 1977. (Note: These 9mples
are taken and analyzed each day.)
(4) The emergency feedwater operational test is required by TS 4.9 to be performed quarterly and is accomplished by surveillance procedure 1303-5.4, Emergency Feedwater
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Pumps, Revision 1.
Data was reviewed for tests performed
February 16,1977; June 2,1977; August 24, 1977.
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i (5) The control room emergency filtering system operational test is required by TS 4.12.1 to be performed quarterly and is accomplished by surveillance procedure 1303-5.5, Control Room Emergency Filtering System Operational Test,
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Revision 5.
Data was reviewed for tests perfomed January 9,1977 (A unit), January 10,1977 (B unit),
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April 25,1977 (A unit), May 4,1977 (B unit), and June l
24,1977 (A&B units).
i (6) The emergency diesel generator operational test is required by TS 4.6.1 to be performed quarterly and is accomplished by surveillance procedure 1303-4.16, Emergency
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Power System, Revision 12.
Data was reviewed for tests I
perfomed for the A unit on February 14, 1977; March 9, j
1977; March 18, 1977; April 19, 1977; May 9, 1977 and i
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June 16,1977.
Data was reviewed for. tests performed for l
the B unit on February 9,1977, March 10,1977, March 18, i
1977, April 18,1977, May 9,1977 and June 10, 1977.
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(7) The station batteries a^re checked monthly as required by TS 4.6.2.9 in accordance with surveillance procedure
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j 1301-5.8, Station Batteries, Revision 1.
Data was reviewed for tests performed Janaury 21, 1977 February 25,1977, March 23,1977(B), March 25, 1977 (A), April
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25,1977, May 27,1977, June 23,1977, July 28,1977, and August 18, 1977.
e (8) The station batteries are checked weekly as required by TS 4.6.2.b in accordance with surveillance procedure
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1301-4.6, Station Storage Batteries-Required Interval-
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Weekly, Revision 3.
Data was reviewed for checks performed March 10, 1977, March 17, 1977, March 25, 1977, April 1,1977, April -7,1977, April 15,1977, April 22,
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1977, April 29,1977, May 6,1977, May 13,1977 and May 20, 1977.
These reviews identified an item of noncompliance as
described in section 4.d following.
d.
During the inspector's review of procedures 1104-4, 1104-2, 1103-8, and 1303-5.8, it was determined that the licensee had used superseded procedures to perform the necessary operations.
and surveillance as follows:
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Procedure 1104-4, Decay Heat Removal System, was performed
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on May 5,1977 using Revision 12.
Revision 13 to this procedure, which involved locking closed of already closed valves DH-V68A and B, was approved on March 13, 1977.
Procedure 1104-2, Makeup and Purification Demineralization,
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was perfonned on May 6-16, 1977 using Revision 17.
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Revision 18 ta this procedure which modified wording in steps 2.3.9.1.3 (Note) and step 2.3.9.2, was approved on March 29,1977.
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Procedure 1103-8, Approach to Criticality was performed
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on May 13, 1977 using Revision 5.
Revision 6 to this
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procedure, which changed the Boron Shutdown Curve (Enclosure 1) for cycle 3, was approved on April 22, 1977.
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Procedure 1301-5.8, Station Batteries, was performed on
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January 21, 1977, February 25,1977, April 25,1977, May l
27, 1977, June 23, 1977 July 28, 1977 and August 18, j
1977 using Revision O.
Revision 1'to this procedure
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A which required recording of digital voltmeter model<
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number, serial number and calibration dates, was approved on August 5, 1976.
l These discrepancies and breakdown in document control were discussed with the licensee.
The inspector stated that these findings are contrary to the requirements of 10 CFR 50, Appendix B, Criterion VI and is considered to b2 an item of noncompliance (289/77-27-01) at the infraction level.
5.
Post Refuelino Startup Report Review
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The inspector and licensee discussed the licensee's plans to submit a Startup Report to Region I.
The licensee stated that a Startup i
Report would not be submitted to Region I because no changes had t
taken place during the refueling which would require a report -
submittal as specified in the Technical Specifications.
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The inspector reviewed fuel receipt forms (NRC-741), shipping records and the Three Mile Island Unit 1 Cycle 3 Reload Report to verify the licensee's action.
No items of noncompliance were identified.
6.
Exit Interview The inspector met with licensee representatives (denoted in para-graph 1) at the conclusion of the inspection on September 2, 1977.
The inspector summarized the scope and the findings of the in-spection as they are detailed in this report.
During the meeting, the item of noncompliance was 'Jentified.
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