ML19319B980
| ML19319B980 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/02/1977 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001290709 | |
| Download: ML19319B980 (6) | |
Text
Neceona 195 u.s. NUCLE AA REGULATC3Y CIM*tlSSl!N DOCKET NUMIE R i8x g;a-3 4 (,
NRC DISTRIBUTION coR PART 50 DOCKET MATERIAL TO:
FROM:
DATE OF DOCUMENT Mr J f'S tolz Toldeo Edison Co 3-2-77 Toledo, Ohio o,7,,, c,,y, o a
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One Signed DESCRIPTION ENCLOSU R E Ltr re their 2-22-77 ler...trans the follow:
Amd t di to Enclosure I of Preeperahional, test program s tatus (relie f re;;uest)....
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BENAROYA DENTON & "rT T r2 OELD
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IPPOLITO ENVIRO TECR.
MIPC MACARRY KTRKWOOD ERNST CASE
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BOSUAK BALLARD MANAUER
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SIHWEIL OPERATING REACTORS SPANGLER HARLESS
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Docket No. 50-346 D
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March 2, 1977 f
Director of Nuclear Reactor Regulation
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Attention:
Mr. John F. Stolz, Chief 9 g
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b U. S. Nuclear Regulatory Commission Washington, D. C.
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Dear Mr. Stolz:
In confirmation of a conference call between members of my staff, your staff and OI&E Region III on February 28, 1977, regarding the material contained in my letter of February 22,1977 (Serial No. 223), we are sub-mitting an Amendment to Enclosure I contained in my February 22, 1977 letter, which provides additional information discussed in the conference call on the test program status and plans for completion of the preopera-tional tests for the Davis-Besse Unit 1.
We understand this additional information documents our agreed upon plans for orderly completion of the preoperational test program. The program contained in Enclosure I to my February 22, 1977 letter and the Amendment to Enclosure I has been reviewed by the Station Review Board and has been approved by them and the Davis-Besse Station Superintendent.
Yours very truly,
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Mr. James G. Keppler Regional Director, Region III 2573 THE TOLEGO EDISON COMPANY EDiSCN PLAZA 300 MADISCN AVENUE TCLECO. CHIO 4365?
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AMENDMENT TO ENCLOSURE I OF PREOPERATIONAL TEST PROGRAM STATUS (Relief Request)
Dated February 22, 1977 1.
TP 100.01 - Communication System Test A.
Load speaker and alarm verification is approximat ty 20% complete.
Testing has revealed the need for further system tuning. Those portions within the radiation access control area will be completed prior to fuel load - The remainder will be completed prior to Mode 2.
B.
Portable station, portable headset, handset and jack station testing will be completed prior to Mode 2.
C.
A temporary fix for problems with carrier phones on fuel handling bridge will be tested prior to fuel load; the permanent fix is being evaluated and will be completed at a later date.
The entire communication system is installed and in service. The system was demonstrated to be functional during the Emergency Plan Drill and during normal plant activities. The test basically involves adjusting volume controls on speakers with equipment operating. As stated above, this test-ing will be completed prior to Mode 2.
Additional equipment needed when identified during testing will be installed and tested prior to Mode 1.
All equipment necessary for implementing the Emergency Plan will be opera-tional prior to Fuel Load.
3.
TP 130.06 - Polar Crane Acceptance Test a
This test will not be completed prior to fuel load due to required replacement of gears on main hoist. Rework will be completed af ter reactor vessel head is installed (Post Fuel Load), and testing will be completed before any head re-moval subsequent to initial criticality. Testing will not involve movement of substantial loads over the reactor vessel head.
4.
TP 160.02 - Containment Purge All SEAS related equipment testing is complete. All isolation valve testing is complete. All fan / valve interlock testing is complete.
EVS cross connect to CTMT Purge System testing is not complete. This cannot be completed until all penetrations are sealed and the negative drawdown test of the EVS System is complete. This testing will be completed prior to Mode 4.
6.
TP 170.01 - Auxiliary Building Radwaste Area Ventilation Testing of Main Station Exhaust, ECCS Room Coolers, Fuel Handling Area Fans completed. SEAS testing of radwaste area ventilation completed.
EVS to Auxiliary Building Radwaste Ventilation System yet to be completed. Testing will be completed prior to Mode 4 within Technical Specification requirements..,..
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7.
TP 203.03 - Decay Heat Removal System Test Testing will be completed prior to Fuel Load. DH-ll and DH-12 Reactor Coolant System Pressure Interlocks will be tested by simulating system pressures.
This will not violate Technical Specifications.
8 TP 230.01 - Clean Liquid Waste System Test Testing is in progress. Will complete all testing prior to fuel load except the following:
1.
One of the two clean waste booster pumps - replacement pump on order.
2.
One of the two reactor coolant drain pumps - being repaired.
Testing of the above compc. ants will be done when the pumps are on site and installed. Since these are redundant pumps, test completion can be done in any mode of operation.
9.
TP 231.01 - Miscellaneous Liquid Waste System Test Will complete all testing prior to fuel load except for the miscellaneous waste drain tank pump. Testing of the system pump will be completed when the repaired pump is installed.
Since an alternate pumping path is avail-able, (detergent waste drain tank pump is in parallel with the miscellaneous waste drain tank pump) test completion can be done in any mode of operation.
13 TP 256.02 - Station and Instrument Air Test Test complete except for portions related to capacity of the emergency air i
compressor. None of the engineered safety features depend on the supply of 1
instrument air for its operation per Section 9.3.1.4 of the FSAR. On loss of station air all safety related valves will assume their safe position and/or have their own reserve source of air for actuation as verified in TP 256.01. Requirements for breathing air on loss of station air will be i
met with portable self-contained breathing apparatus.
The test on the emergency air compressor vill be completed prior to Mode 3.
15. TP 271.09 - Main Steam Isolation Valve Test Test performed and valves cycled properly during hot functional testing; however, several minor problems will require retest during post fuel load hot functional testing:
1.
Test new pilot supply presante svitches to verify computer point indication and " solenoid energized" lights.
2.
SFAS SAM lights did not flash for MS 101 and MS 100 when taken to i
non-SA position after blocked.
3.
Gaskets on 3-way valves leaked.
Both main steam isolation valves will be operab.e during Mode 4 and testing will be completed in Mode 3. i
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,16. TP 315.01 - Steam and Feedwater Rupture Control System Test System logic and rssponse time testing complete.
Integrated systes testing will be completed prior to fuel load. Loss of four reactor coolant pump portion of test will have to be repeated af ter fuel load during post fuel load hat functional testing to resolve related respoase time testing problem.
- 17. TP 330.04 - Control Rod Drive System Integrated Test Test was conducted during Hot Functional Testing. The following deficiencies were identified and will require retest:
1.
RPI motors for rod 6, group 2 and 6.
Motors were found to be burned out and have been replaced.
2.
Zone reference lights on CRDM's 57 and 66 did not light. Lights were burned out.
3.
Resistance measurements between Phase II and neutral of mechanism
- 29 (core location MS). Value was 14.928 ohms - Max. is 14.92'4 ohms.
4.
Seven mechanisms did not meet the 3% acceptance criteria of refer-ence switch in API & RPI positions.
(Max. was 7.5%)
The above deficiencies will be retested during post fuel load hot functional testing prior to Mode 2.
- 19. TP 360.01 - Process and Area Radiation Monitoring Systen Test All testing of area monitors will be completed prior to fuel load. Testing on process monitors is in progress. Process monitors required for fuel load will be tested. The following process monitors, not required for fuel load, will be tested prior to Mode 2:
RE 8442 - Station Drainage RE 8443 & 8444 - Station Forebay Inlet / Outlet RE 5327 A, B, & C - Control Room Emergency Ventilation RE 5328 A, B, & C - Control Room Emergency Ventilation RE 600, 609 - Main Steam Line RE 1998 - Penetration Room #1 - EL 565 (Failed Fuel Detection)
Additional process monitors will not be tested prior to fuel load. These relate to request for relief from Technical Specifications which will be addressed in a separate letter to the Director of Nuclear Reactor Regulation.
- 20. TP 401.11 - Instrument Ground Grid System Test Test started but encounterad apparent difficulty with ground currents between __
instrument and station ground systems. Extensive investigation was conducted and many mutual ties between the ground systems were eliminated.
While perfect isolation would be desirable, it is impossible to obtain due to leakage across virtually any insulation. In order for the shielding system to function, it must drain noise signals to ground.
Based on Engineering's evaluation of the data obtained during the test, the calculated isolation value of 10 megohm resistance between the Instrument and the Station Ground Systems is acceptable. The test procedure will be revised to include an alternate but equally acceptable method of obtaining measurements and satisfy the intent of the system design. This revision will be completed and the test completed prior to Mode 2.
21.
TP 600.04 - Makeup & Purification Systen Test Test conducted during hot functional testing. Three deficiencies require retest with coolant letdown in service:
1.
Test redesigned letdown orifice.
2.
Verify system revision to provide manual override of temperature interlock on MU 3.
3.
Verify that temperature switch TSH 3745B will close MU 2B when actuated by high temperature. This valve is redundant to MU 3 which was tested satisfactorily.
The above deficiencies will be retested during post fuel load hot functional testing in Mode 4
- 22. TP 600.11 - Auxiliary Feedwater System & Steam Generdtor Level Control Test Testing conducted during Hot Functional Testing resulted in five deficiencies:
1.
Auxiliary Feed Pump 1-1 would not accelerate to 3600 rpm but would stick at As2600 rpm.
(Could be unstuck by taking manual control) 2.
Governor valve leaked.
3.
Suction pressure oscillated during pump acceleration.
4.
Both pumps maintained steam generator level but with excessive hunting and valve.ycling.
5.
AF 360 (1-1 AFW Pump Discharge Valve) occasionally failed to open (torqued out).
Retest after deficiency correction will be accomplished during post fuel load hot functional testing in Modes 4 and 3 since testing requires system pressure and temperature during test performance. All testing will oe completed to comply with Technical Specification requirements for Mode 3. __ _
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f 23. TP 600.14 - Reactor Coolant System Expansion & Restraint Test Testing essentially complete except for two points which will require re-
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verification during ;>ost fuel load hot functional testing.
l 1.
Whip restraint interference on pressurizer spray line - Liner removal to permit pipe movement during HFT.
2.
Whip restraint interference on pressurizer surge line. Liner removal and excess protion of bolt cut off to permit line movement during HFT.
Testing of the above deficiencies will be completed prior to Mode 2.
- 25. TP 600.19 - Power Conversion System Expansion & Restraint Tests Hot Functional Testing portions of test were completed with two items identi-fled as requiring testing during post fuel load heat up.
1.
South crossover line (steam line to Auxiliary Feed Pump) could not be heated up due to inoperable steam supply valve, MS 106A. This 1
will be tested prior to Mode 2.
2.
Movement of one line to moisture separator-reheaters will require I
operation of the MSR's and will be retested during power escalation in Mode 1.
2,5,10,11,12,14,18,24.
These items of our February 22, 1977 Enclosure I were identified by NRC representatives during our February 25, 1977 conference call as being accepted.
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