ML20215B877
| ML20215B877 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/10/1986 |
| From: | Williams J TOLEDO EDISON CO. |
| To: | De Agazio A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-1177 1319, NUDOCS 8612120347 | |
| Download: ML20215B877 (12) | |
Text
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TOLEDO
%ms EDISON Docket No. 50-346 JOE WILUAMS. JR.
sim am mo License No. NPF-3 l'"w ea sa3 Serial No. 1319 December 10, 1986 Mr. A. W. DeAgazio, NRR Project Manager Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue - Mail Stop P-220 Bethesda, MD 20014
Dear Mr. DeAgazio:
This letter is to provide confirmation that Toledo Edison has completed all the Restait Items identified in NUREG-1177, " Safety Evaluation Report related to the Restart of Davis-Besse Nuclear Power Station, Unit No.1, following the Event of June 9, 1985" (Log No. 1997), with the exception of Item Number 19 " Hands-on Training." This training is being performed now and is anticipated to be completed before December 17, 1986. Only operators who have received training will be allowed to stand shift. The 70 commitments identified in your letter of August 28, 1986 (Log No. 2062) are tabulated in Attachment 1, "Prestartup Commitments" and Attachment 2,
" Post Restart Commitments".
Very truly yours, Y:
M JW:SJS:plf Attachment cc: DB-1 NRC Resident Inspector C )\\ N 8612120347 861210 C
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IHE TOLEDO EDISON COMPANY EDISON PLAZA 300 MAO' SON AVENUE TOLEDO. OH'O 436SJ
SUBMITTAL IN RESPONSE FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 FACILITY OPERATING LICENSE NO. NPF-3 This letter is submitted in conformance with 10 CFR 50.54(f) in response to NRC letter dated August 28, 1986 (Log No. 2062).
By )
Am#
.% illiams, Jr.
[
Senior Vice Presidhnt, Nuclear Sworn to and subscribed before me this 10th day of December, 1986.
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Ihter Peter, asas of Ot bly Comminies Espbss Jens 3.is,198F
Dockst No. 50-346 Licanza No. NPF-3 S2 rial No. 1319 PRESTARTUP COMMITMENTS NRC COMMITMENT NUMBER DESCRIPTION STATUS REMARKS 2
MW0s that may affect plant performance will be completed closed P. Byron to close before Restart or will be scheduled commensurate with their for NRC significance (p 3-6).
3 Licensee will provide additional operator training before closed Restart to discourage premature reduction of steam system pressure (p 3-7).
4 Emergency procedures will be modified to include specific closed criteria to indicate lack of heat transfer requiring the initiation of MU/HPI cooling (p 3-8).
5 Errors [in EP 1202.01] will be corrected before Restart closed (p 3-8).
6 EP 1202.01 will be reviewed before Restart with regard to closed the adequacy of existing control room instrumentation (p 3-8).
7 Licensee will add guidance to SP 1106.06 regarding circuitry closed and control logic for valves AF599 and AF608 (p 3-9).
8 Specific criteria to determine when to transfer AFW suction from closed Service Water to CST will be added to procedures (p 3-9).
9 Verification of MSIV status will be added to emergency procedure closed supplementary actions (p 3-9).
10 Emergency procedures will be reviewed before Restart to ensure closed j
and clarify explicitness where significant actions are required (p 3-10).
4
Docket No. 50-346 Licenza Ns. NPF-3 Serial No. 1319 Attschment 1 PRESTARTUP COMMITMENTS NRC COMMITMENT NUMBER DESCRIPTION STATUS REMARKS 11 Licensee has changed Shift Technical Advisor (STA) shifts to closed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (p 3-10).
13 Training of all licensed personnel and STAS on the revised closed procedure [NRC notification] will be completed before Restart (p 3-11).
14 Each of the four zone operators will be provided a key ring closed with a locked-valve key (p 3-12).
15 AD 1639 30 governing conduct of shift operations will be revised closed before Restart to assure SRO will remain in control room once SRO has assume 4 duties of Procedure Director until relieved by another SRO.
Requirement to be included in requalification program (p 3-13).
16 All licensed operators will receive training relative to the closed results of specific loss-of-feedwater analyses and revised procedures relating to lack of heat transfer, before startup (p 3-14).
The program will include three points as listed on p 3-14.
17 Revisions to EP 1202.01 will be included in the training closed program (p 3-14).
18 All licensed individuals and STAS must pass a written exam-closed ination to ensure a complete understanding of the loss-of-feedwater analysis and the relationship of this analyste to EP 1202.01 (p 3-15).
e
Dockst No. 50-346 Licanas No. NPF-3 Serial No. 1319 PRESTARTUP COMMIDfENTS NRC COMMITMENT NUMBER DESCRIPTION STATUS REMARKS 19 Hands-on training for resetting the trip-throttle valve and open 1480.open-overspeed trip mechanism during a simulated accident will be Training going on a requirement for all. plant operators and licensed personnel now.- 'P. Byron (p 3-15),
will observe.
20 Operators will be trained on the Functioning of AF 599/608, closed including any modifications (p 3-15).
(See also No. 7).
21 Operators will be trained on proper actuation of SFRCS for cicsed all combinations of actuations before Restart (p 3-16).
22 Operations assessment program procedures will be in place by closed June 1986 (p 3-16).
23 Licensee proposes maintaining all steam lines from the steam closed generators to the AFPT at full temperature and pressure by keeping the cross-connect isolation valves open (p 3-18)..
24 Licensee proposed eight corrective actions related to the closed AFPT trip throttle valve as listed on p 3-19 and 3-20 to be completed before Restart.
25 Establish new electronic filter setting for SG level closed transmitters and test for proper calibration and response time (p-23).
27 Licensee will add seal-in to SFRCS control room annunciators closed (p 3-23).
e 8
_ = _.
Dockat No. 50-346 Lic:nse No. NPF-3 Serial No. 1319 PRESTARTUP COMMITMENTS NRC COMMITMEh"f NUMBER DESCRIPTION STATUS REMARKS 29 Licensee will perform tests prior to mode 1 to determine closed closed by P. Byron effects of Rosemount transmitter increased sensitivity used for RCS flow (p 3-24).
32 Licensee will test a representative sample of valves under closed Closed by their most limiting conditions in order to satisfy P. Wohld Davis-Besse NEP-091 and NEP-092 requirements (p 3-29).
33 Licensee will confirm that Davis-Besse procedures NEP-091 closed Closed by and NEP-092 are complete for all nuclear safety-related P. Wohld motor-operated valves before Restart (p 3-29).
34 Modifications to MSSV piping trains to provide adequate closed support before Restart (p 3-34).
37 Strainers ahead of each AFW pump to be removed and mesh closed l
size of strainers in common suction line from condensate storage tank (CST) to be increased (p 3-35).
38 Confirmation that the licensee has changed the low closed Closed by NRR.
suctions pressure set point and added a 10-second Testing verified delay to the AFW pump to provide greater margin and by P. Byron.
thereby reduce spurious transfers to the SWS resulting from rapid AFW pump speed changes (p 3-35).
39 SFRCS logic is to be modified to prevent isolation closed of AFW flow to both SGs (p 3-41).
9
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Dockat Ns. 50-346 Licznsa No. NPF-3 S2ric1 No. 1319 Attcchment 1 PRESTARTUP COMMITMENTS NRC COMMITMENT NUMBER DESCRIPTION STATUS REMARKS 40 Four modifications are to be made to SFRCS to improve closed system performance and reliabilit?? before Restart, as indicated in list on p 3-41.
42 SFRCS logic is to be modified to disable main steamline closed and main feedwater line isolation on steam Fenerator low level if analyses verify that this is acceptable (p 3-43).
48 Additional testing will be done to verify transfer closed setpoint on low CST volume (p 3-50).
49 Procedures are to require monitoring the temperature of closed the MDFP discharge piping as detailed on p 3-51.
SP 1106.28 on the motor-driven AFW pump to be approved by the licensee and implemented, and training to be completed before plant Restart from the current shutdown (p 3-51).
50 Suction valves to the CST must be locked in the open closed position with power removed (p 3-51).
51 Modifications to provide electrical independence between closed redundant Safety Features Actuation System (SFAS) instru-ment channels as detailed on pp 3-54 and 3-55.
52 Testing to assure electrical separation and isolation of closed SFAS channels as detailed on p 3-56.
53 ST 5031.03 to be performed after SFAS modifications and closed continuing monthly thereafter, including SFAS sensor commons testing, to detect degraded voltage conditions (pp 3-56 and 3-57).
Docket No. 50-346 Licenca No. NPF-3 Sarial No. 1319 PRESTARTUP COMMITMENTS NRC COMMITMENT NL'MBER DESCRIPTION STATUS REMARKS 60 Actions to be completed concerning 29 safety-significant HEDs:
- hardware modifications to be completed to correct six closed HEDs, before Restart; additional or special training of control room operators, closed before Restart, on hardware modifications made to correct six HEDs;
- confirmation, before Restart, for five HEDs that good closed human factors practices were followed in implementing hardware modifications; 61 Confirmation that all actions required before Restart, closed Closed by NRC review-as listed on p 3-64 and in Appendix D are completed.
and acceptance of Item Details of any hardware modifications should be made No. 60 (Above)'
available to staff (p 3-64).
67 Verify proper operation of anticipatory reactor trip system closed interlock during systems testing (p 3-72).
69 Control room isolation upon auxiliary building high radiation closed function is to be added to current list of system functions l
in the SRTP (p 3-72).
l l
9 9
9
Dockat.No. 50-346 Licznza No. NPF-3 Serial No. 1319 POST-RESTART COMMITMENTS NRC COMMITMEh7 NUMBER DESCRIPTION STATUS REMARKS 1
Licensee has committed to install plant-specific simulator open Scheduled 12/01/87 (p 3-2).
12 STAS will be SRO licensed. Training of these additional STAS open Scheduled 06/30/87-will be completed by 1/1/87 (p 3-10).
26 Licensee will develop surveillance procedures to test quarterly closed for proper SFRCS power supply operation (p 3-23).
28 Monitoring of SFRCS SG startup level to determine hydraulic open Prestartup testing and electrical noise. Before and after startup until adequacy completed.
100%
of corrective action is verified (p 3-23),
testing required.
30 Preventive maintenance procedures for turbine bypass valve open 5th RF0 will be modified by 11/86 (p 3-25).
31 Licensee will stroke test PORV at reduced pressure, at open Prestartup testing full pressure during Restart and at each cold shutdown completed.L Scheduled (p 3-27).
04/01/87 35 Licensee to document results of National Board of Boiler open 90 days after and Pressure Vessel Inspectors' tests on the adequacy of Restart.
MSSV valve inlet pipe size within 90 days following Restart (p 3-34).
36 Licensee to submit plan for inspection of MSSVs at each open 90 days after refueling outage within 90 days following Restart (p 3--34).
Restart 41 A licensee amendment is to be proposed requiring one open 90 days after second TSV response time within 90 days following Restart Restarc I
(p 3-42).
' Docket No. 50-346
'Licsnse No. NPF-3 Serial No. 1319 POST-RESTART COMMITMENTS NRC COMMITMENT NUMBER DESCRIPTION STATUS REMARKS 43 A backup safety-related source of water for the MDFP to open 5th RFO be provided by installing a connection to the.SWS before startup from the next refueling outage (p 3-45 and 3-52)..
44 Modifications to permit aligning all necessary MDFP.
epen 5th RFO associated equipment to either diesel generator from within the control room to be completed before Cycle 6 (p 3-47).
45 A manually initiated transfer system to be provided to the open 5th RFO SWS for the MDFP before Cycle 6 (p 3-48).
46 A Technical Specification for the MDFP similar to the open 60 days after existing Technical Specification for the turbine-driven Restart AFW pump is to be proposed within 60 days after Restart (p 3-49).
47 The startup feedwater pump (SUFP) to be returned to.
open 5th RF0 operable status before Cycle 6 operation. The manual valves that isolate the high-energy line of the SUFP will be replaced with remote, manually operated valves (p 3-50 and 3-52).
54 Licensee to use human factors specialists in its Systems open ongoing actions Review and Test Programs in the facility change request until 6th RF0 (FCR) process'during and after completion of the detailed control room design review (DCRDR) (p 3-60).
55 Systems function and task analysis (SFTA) to be updated open Scheduled 04/01/86 to include activities outlined (p 3-61).
Docket No. 50-346 Licsnsa No. NPF-3' Sarial No. 1319
' Attachment 2 i
POST-RESTART COMMITMENTS NRC l COMMITMENT NUMBER DESCRIPTION STATUS REMARKS
!i 56 Equipment availability and human engineering suitability open Scheduled 06/01/87 i
is to be verified for requirements developed from activities j
necessary to upgrade the SFTA (p 3-61).
l l
] 57 The control room survey is to be completed, and human open Scheduled 06/01/87 l
engineering discrepancies (HEDs) identified to satisfy
?
Supplement I to NUREG-0737 (p 3-61),
e i 58 The activities and the documentation of items outlined open Part I month l
on p 3-62, section (6) " Selection of Design Improvements",
after Restart, be completed to meet DCRDR and Supplement I to NUREG-0737 Part 5th RFO e
j requirements in accordance with the schedule given on-i p 3-63.
i i 59 Human factors specialists to be used as integral members open 6th RF0 l
of the DCRDR team to develop and verify human engineering design changes (p 3-63).
60 Completion, before the end of the next (5th) refueling open 5th RF0 j
outage, of special studies and associated hardware L
modifications for 18 HEDs (p 3-64).
1 e
62 All special studies and associated hardware modifications open
'Sth RF0 j
1 concerning 29 safety-significant HEDs are to be completed by end of next (5th) refueling outage (p 3-64).
- 63 All DCRDR HEDs are to be corrected by the end of the sixth open 6th RF0 1
refueling outage (p 3-64).
i 64 A review of the fuel handling area ventilation system is open 5th RFO to be completed after Restart (p 3-70).
)
65 Document the functions of systems included within scope open Scheduled 03/01/87 of SRTP (p 3-71).
f 1
Docket No. 50-346 Licznsa No. NPF-3 Sarial No. 1319 Attechment 2 POST-RESTART COMMITMENTS NRC COMMITMENT NUMBER DESCRIPTION STATUS REMARKS 66 Davis-Besse Updated Safety Analysis Report (USAR) is to be open 07/22/87 revised to clarify systems and system functions needed to mitigate letdown line pipe break discussed in USAR section 15.4 (p 3-72).
68 USAP. revision to update discussion provided in section 15.2 on open 07/22/87 turbine trip analysis as specified on, 3-72.
70 A detailed reliability study on the Auxiliary Feedwater System open 90 days after is to be submitted for review within 90 days after Restart Restart.
(p 4-2).
O
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