ML19289C329
| ML19289C329 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 01/02/1979 |
| From: | Parker W DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19289C330 | List: |
| References | |
| NUDOCS 7901120026 | |
| Download: ML19289C329 (1) | |
Text
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Duxe POWER COMPANY
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January 2, 1979 Vice Patsier uv Testo-o%c Asta 704 St rans Peoovctiog 373-4083 Mr. J. P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region TI 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 RT:
RII:WTC 50-369/78-38
Dear Mr. O'Reilly:
Duke Power Company does not consider any information contained in IE Inspection Report No. 50-369/78-38 to be proprietary.
Very truly yours,
')l t(L.,,, C R, w William O. Parker, Jr.
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RII Rpt. No. 50-369/78-38 II-1
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/J/MF Prepared by:,J. A. Dy r, Reactor Inspector DETAII.S II D" ate Nuclear upport Section No. 1 Reactor Operations and Nuclear Su ort Branch fdt&dL,
/zkhs A. G. Wagner, Reactor / Inspector D4te/
Nuclear Support SectMn No.' 1 Reactor Operations and Nuclear Support Branch Dates of Inspection:
November 13-17, 1978
/ L /5 Y?g' Reviewed by:
A/
R. D. Wartin, Chief Date' Nuclear Support Section No. 1 Reactor Operations and Nuclear Support Branch 1.
Persons Contacted Duke Power Company D. Marquis, Assistant Engineer G. Massey, Assistant Engineer
- M. McIntosh, Plant Manager T. Meadows, Junior Engineer
- M.
Pacetti, Test Engineer
- M. Sample, Technical Services Engineer D. Simons, Assistant Engineer A. Suddath, Assistant Engineer R. White, Associate Engineer
- Denotes those present at the exit interviews on November 15 and 17.
2.
Licensee Action on Previous Inspection Findings (Closed) Deficiency 78-29-01:
Failure to sign data or test step completion as required by " Station Directive". The inspector reviewed records and interviewed licensee representatives. These records and the interviews indicate that increased emphasis has been placed on proper sign-offs.
3.
Unresolved Items None.
RII Rpt. No. 50-369/78-38 II-2 4.
Exit Inte rview The inspectors met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on November 15, 1978, and November 17, 1978. The inspector emphasized the need of a formal procedure for the inspection of ASME Section III, Class 1, 2, and 3 piping during initial heatiip of the plant for hot functional testing. A licensee management representative shared the inspector's concern and stated that p.ocedure would be developed or existing procedures revised to include Anspection of this piping. The inspector summarized the purpose at findings of the inspection as reported in the following paragraphs.
5.
Review of Test Procedures Pertaining to Hot Functional Testing Test procedures were reviewed for conformance to Regulatory Guides 1.68 and 1.79, FSAR Tables 14.1.3-1 and 14.1.4-1, FSAR Sections 6.3, 9.3.2, 10.3.2, 10.3.4, 10.4.4, and 15.2.7, McGuire Station Directives 3.2.2 and 4.2.1 and McGuire Proposed Technical Specifications.
a.
No discrepancies were noted during review of the following procedures:
1.
TP/1/A/1100/01 Controlling Procedure for Hot Functional Testing. Approved November 10, 1978.
2.
TP/1/A/1150/04A Preliminary Spr$y Flow Functional Test.
Approved November 1,1978.
3.
TP/1/A/1150/09 Chemical Addition and Sampling of Primary and Secondary Systems. Approved November 10, 1978.
4.
TP/1/A/1250/06 Main Steam Isolation Valve Timing Functional Test. Approved October 27, 1978.
5.
TP/1/A/1250/08 Test Procedure for The Steam Generator Wet Layup System. Approved November 11, 1978.
6.
TP/1/B/J300/02 Initial Roll of No.1 Main Turbine During Hot Functional Testing. Approved October 24, 1978.
7.
TP/1/B/1600/06 Steam Du=p Control System. Approved July 21, 1978.
8.
IP/0/A/3000/07A In-core Thermocouple and RTD Cross Calibration.
Approved July 3,1978.
9.
OP/I/A/6100/11 Controlling Procedure for Unit Heatup During Hot Functional Testing. Approved November 14, 1978.
RII Rpt. No. 50-369/78-38 II-3 10.
PT/1/A/4250/01A Main Steam Isolation Valve Movement Test.
Approved January 26, 1977.
b.
Discrepancies were noted during review of the following procedures which will require resolution by the licensee prior to implementation of these procedures:
1.
TP/1/A/1200/03E Safety Injection System Check Valve Functional.
Draf t Procedure.
(a) The inspector noted, during review of the procedure that the ECCS flow throttling valves, that were locked in position subsequent to the performance of test TP/1/A/1200/03C, were required to be manipulated.
A licensee representative stated that TP/1/A/1200/03C was invalidated and would be performed subsequent to the completion of test TP/1/A/1200/03E. The inspector will review these test results during a subsequent inspection (369/67-38-01).
(b) Reactor coolant system accumulator check valves 159, 170, 181, and 193 are located in close proximity to check valves 160,171,182 and 194 whose operability is verified during conduct of this test. The inspector stated that the temperature of valves 159, 170, 181, and 193 should be monitored during hot functional testing and an analysis made to determine if these valves will require insulation and/or if an operational check of the valves should oe performed at hot plant conditions.
This item will be reviewed during a subsequent inspection (369/78-38-02).
2.
TP/1/A/1250/05 Main Steam Safety Valve Setpoint. Approved procedure. The setpoint of 8 valves in the procedure differs from the setpoints listed in FSAR Figure 10.3.2-1 and Table 10.3.2-1.
The procedure lists the setpoints for ISV2, 8, 14, and 20 as 1170 psig; the FSAR lists these setpoints as 1175 psig. The procedure lists the setpoints for ISV6, 12, 18, and 24 as 1225 psig. The FSAR lists these setpoints as 1230 psig. This is identified as an open item pending reso-lution of these differences (369/78-38-03).
3.
TP/1/A/1150/15 Hot Functional Testing of Pressurizer Pressure and Level Control, Steam Generator Level Alarms, Power Operated Relief Valves and Reactor Coolant Low Flow Ala rms.
Draft Copy.
RII Rpt. No. 50-369/78-38 II-4 (a) No sign-offs for the following paragraphs:
1) 4.0 Prerequisite Tests 2) 7.0 Required Station Status 3) 8.0 Prerequisite System Conditicos 4) 8.3 System Prerequisites (b) The procedure does not specify the proposed technical specifications trip setpoint of the Reactor Coolant Loop Low Flow /.la rm either in the data sheet or in the acceptance criteria.
(c) The S/G level trip setpoint is checked in the procedure at the 0% rated thermal power setpoint only. The pro-posed technical specification in Table 2.2-1 lists the trip setpoint as "g15% of the span from 0 to 15% of rated thermal power increasing linearly to 385% of span at 100%
of rated thermal power".
The procedure does not check the trip setpoints at the upper setpoints or any of the intermediate points.
(d) The enclosures containing the trip setpoint specifications and tolerances state tolerances which oo not agree with the proposed technical specifications, i.e. :
1)
High Pressure reactor trip 2385133 psig versus 12385 psig.
2)
Low Pressure reactor trip 1960 1 33 psig versus 11960 psig.
3)
Pressurizer Low pressure safety injection 1845 ! 33 psig versus 31845 psig.
Similar errors were noted throughout procedure in pressurizer level and Steam Generator level section.
(e)
It should be pointed out that the Precautions Limitations and Setpoints manual does not agree with the proposed technical specifications in the area listed in (d) above.
It is our understanding that it is currently in the process of being revised. These items are designated as open items for follow-up during a subsequent inspection (369/78-38-04).
On November 20, 1978, a senior licensee representative contacted the inspector by telephone concerning TP/1/A/1150/15; Hot Functional Testing of Pressurizer Pressure and Level Control, Steam Generators Level Alarms, Power Operated Relief Valves
RII Rpt. No. 50-369/78-38 II-5 and Reactor Coolant Low Flow Alarms. The licensee represen-tative stated that the intent of the procedure was not to verify the trip setpoints as stated in the purpose section of the procedure. The intent is to perform a functional check to the accuracy of control board instrumentation. The licensee representative further stated that the test description as stated in the Final Safety Analysis Report would be checked and the procedure would then be changed to retlect the intent of performing a functional check. This,will be carried as an open ites pending review and/or revision of the FSAR (369/78-38-05).
6.
Inspector Identified Area of Concern Other than inspection of the reactor coolant system at the specified temperature plateaus identified in TP/1/A/1150/07, there is no formal program for inspection of ASME Section III, Class 1, 2, and 3 piping during heatup of the plant for hot functional testing. Specific piping systems were identified by the inspector. A licensee canagement repre-sentative stated that a procedure would be developed or existing procedures revised to include inspection of ASME Section III, Class 1, 2, and 3 piping. The inspector will review the:e procedures during a subsequent inspection (369/78-38-06).
.