ML20236B712
| ML20236B712 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/15/1987 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 2NRC-7-176, NUDOCS 8707290206 | |
| Download: ML20236B712 (8) | |
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2NRC-7-176 Telecopy 2 4h Ext.160 Deaver Valley No. 2 Unit Project Organization S.E.G. building P.O. Box 328 July 15, 1987 Shippingport, PA 15077 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 l
ATTENTION:
Mr. Edward C. Wenzinger, Chief Division of Reactor Programs
SUBJECT:
Beaver Valley Power Station Unit No. 2 Docket No. 50-412 Inspection Report 50-412/87-34, Interim Response
REFERENCE:
- 1) Letter dated June 11, 1987, (E. C. Wenzinger to J. J. Carey)
Gentlemen:
The above referenced letter transmitted the NRC contractor report of a comparison of draf t Beaver Valley Power Station Unit No. 2 Technical Specifica-tion 5 and the Unit 2 facility.
The attachment to this letter provides Duquesne Light Company's (DLC) Interim response to that report.
A final response will be issued no later than August 12, 1987.
DUQUESNE LIGHT COMPANY
/
By 7
J<' J(Jarey (f7 Senior Vice PresideMt DLC/ijr NR/DLC/IR/8734 achment NAR cc: Mr. P. Tam, Project Manager (w/a)
Mr. J. Beall, NRC Sr. Resident Inspector (w/a)
Mr. L. Prividy, NRC Resident Inspector (w/a)
INP0 Records Center (w/a)
NRC Document Control Desk (w/a) j l
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ATTACHMENT Response to Inspection Report 50-412/87-34 The following response is divided into sections corresponding to the sections presented in Inspection Report 50-412/87-34.
1 Section 2.1.a The required circuitry modification to correct the potential undetectable f ailure with the online test circuitry for the master relays in the Engineered Safety Features systems has been completed (letter 2NRC-7-093, dated April 24, 1987, "Information on Technical. Specification Changes").
With the completion of the circuitry change the Beaver Valley Unit 2 Techni-cal Specifications were revised to require slave relay testing be done on a quarterly (in lieu of monthly) basis as stated in surveillance item 4.3.2.1.1.
Section 2.1.b The Technical Specifications surveillance item 4.8.1.1.1 requires that the capability to manually and automatically transfer unit power supply from the unit circuit to the system circuit be demonstrated at least once every 18 months. The technical specifications do not require this surveillance to be done at shutdown.
However, this test is typically done during power reduc-tion for shutdown when a bus transfer would already be required or in mode 5, either situation which should minimize any concerns with potential for plant transients created during this testing.
Section 2.1.c The Technical Specifications surveillance item 4.8.1.1.2.b.6 requires that the autoconnected loads to each diesel generator do not exceed the 2,000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> rating of 4,535 kw be verified once per 18 months.
This requirement is consistent with the Beaver Valley Unit 1 Technical Specification and the Standard Technical Specifications.
The 2,000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> rating of 4,535 kw is consistent with the value provided in the FSAR and therefore no FSAR changes are required.
Section 2.1.e As noted in the Inspection Report the Technical Specifications Table 3.3-5 list the maximum response times for SI from containment pressure - high and pressurizer pressure - low as 27 seconds while the FSAR Table 15.6-1 speci-fies a time of 25 seconds.
A discussion and justification for the l
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Page 1 of 4
difference has been addressed in letter 2NRC-7-10So dated May 7,
- 1987,
" Technical Specifications Additional Information."
The response time of'12 seconds for valves to be in their final position and pumps at full speed following a main steam line rupture, as stated on FSAR page 15.1-17 includes sensor and signal processing delays.
Therefore, with the additional 10 seconds for starting the Emergency Diesel Generators the total response time is consistent with Technical Specifications Table 3.3-5.
It should be noted that since the time of the inspection, Table 3.3-5 response time for steam line pressure-low has been revised to include an additional 15 seconds to account for the Volume Control Tank and Refueling l
Water Storage Tank isolation valves interlocks to operate (letter 2NRC 108, dated May 7, 1987).
I Sections 2.3a through 2.3.f, 2.4.a, 2.4.b.2 through 2.4.b.5, 2.5.a 2.5.b and-l 2.5.d The NRC inspection results and findings presented in these sections have been reviewed.
Affected operating procedures and the Technical Specifica-tions Matrix are being changed to reflect the issued Technical Specifica-tions, as well as, the NRC inspection results and findings.
These changes are being made on an Operating Mode priority basis.
Procedure changes are completed prior to required procedure implementation.
In addition, for:
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Section 2.3.b, OST 2.1.3 and 2.1.4 have been revised and address this finding.
- Section 2.3.c.
maintenance surveillance procedures (calibrations and channel functionul tests) are being reviewed for compliance to issued Technical Specification setpoints prior to initial procedure issuance for use during plant startup.
Calibration procedures for Pressurizer Pressure Reactor Trip, Steam Generator Level Reactor Trip and Nuclear Instrument System Interlocks have been revised to comply with the issued l
Technical Specifications.
I Section 2.3.d, valve 2SDS-A0V129A has been determined to not be a containment isolation valve.
Therefore no TS or FSAR change is required.
l Section 2.4.b.5, OST 2.36.3, Attachment G, has been revised and addresses j
this finding.
Section 2.5.a, Operating Manual Chapter 11, Rev. 2 provides updated valve numbering designations and now identifies valves 2 SIS *MOV8888 A/B.
Section 2.5.b, the Data Sheets for OSTs 2.36.8 and 2.36.9 have been revised and address this finding.
Page 2 of 4
- Section 2.3.g As stated in this finding, 0.36 seconds is used as an assumed time response value in BVT 2.1-1.1.2 for the installed slave relays.
This value is more than four times longer than actual measured slave relay response times from BVPS-preoperational testing, P0-2.01A.02.
Since the assumed slave relay response time is longer than actual measured times, this represents a conservative approach to the determination that ESFAS time response' meets Technical Specification limits.
Justification for not reverifying slave response. time by test is provided in response to RI-SVG 2612 (attached).
Prior to implementation of BVT 2.1-1.1.2, all (laters) will be eliminated from the procedure.
l Section 2.3.h Operating Manual Deficiency Reports have been submitted to revise the OST's discussed in this finding to obtain the necessary equipment response times.
Section 2.4.b.1 Technical Specification time response requirements are verified in the test program for initial startup.
Maintenance Surveillance Procedure., 2MSP1.15-1, will be prepared and approved prior to use at the end of the first refueling interval.
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Section's 2.5.c, 2.5.f, 2.5'.g and 2.5.h These findings are under evaluation and will be responded to in the Final Report.
Section 2.5.e Equipment labeling items are addressed as follows:-
Items 1 & 2, the labels on the inside of these DC switchboards were not permanent and have been removed.
- Item 3, station equipment labeling uses a distinct mark number indepen-dent of the asterisk.
Equipment labeling follows the color coding convention discussed in FSAR Section 8.3.1.3 which effectively identifies proper power train.
This labeling convention provides a more relevant identification of safety status for station operation.
Item 4, the station battery cells have been identified.
Individual cell tags have been ordered and will be installed when received.
Page 3 of 4 i
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Item 5, lighting panel identification is not complete and is being worked on an as available basis with no priority assignment.
Item 6, this problem was identified to security.for resolution.
This item will be responded to in the Final Report.
Item 7, conduit penetration tagging problems will be addressed and corrected on a case by case basis,.already identified by DLC QC, as part-of the construction close-out program.
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Grcup September 13, 1978 Mr. Dennis Zona Distuaane Light Co.
Beaver Valley Power Station P. O. Boa - 4 Stippins yrt, Pa.
15077
Subject:
AR malay l
Dear Mr. Zonas Referring to our phone conversation of this morning,' the Westinghouse AR Ratay - l AC Cott has been tested a awaber of times in our Elastrical Lab and the pickup tLee is:
4 pole, normally opes, the pickup time is 12-18 milliseconds until the N.O. contaats close. This any vary slightly due to the number of poles and combination of normally open-normally closed cartridges.
Also, this ytti very with appited voltage 907.-1107, rated voltage.
I hope this is satisfactory, as you can see it is much less enan seconds.
Very truly yours, WEEINGEUS ELECTRIC CORP.
J. H. Mullen Developeant Engineer Standard Control Division 5jw 4
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