ML20235U979

Forwards Facility Biweekly Status Rept for 870911-25.Status Repts Intended to Provide NRC Mgt & Public W/Overview of Plant Activities & NRC Insp Activities.Subsequent Insp Repts Will Address Many Topics in More Detail

ML20235U979
Person / Time
Site:	Dresden
Issue date:	10/08/1987
From:	Ring M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 8710140361
Download: ML20235U979 (6)

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L OCT 8 1987 MEMORANDUM FOR: Charles E. Norelius, Director, Division of Reactor Projects FROM: . Mark A. Ring, Chief, Reactor Projects Section 1C

SUBJECT:

DRESDEN STATUS REPORT FOR THE PERIOD SEPTEMBER 11 - 25, 1987 Enclosed is the Dresden bi-weekly status report from the NRC Resident Office at Dresden. The NRC resident staff (made up of seven (7) individuals including two (2) from AE0D) and two (2) region-based inspectors monitored activities at the plant during the report period.

These status reports are intended to provide NRC management and the public with an overview of plant activities and NRC inspection activities.

Subsequent inspection reports will address many of these topics in more detail.

Original Signed by Mark A. Ring Mark A. Ring, Chief Reactor Projects Section 1C

Enclosure:

As stated l

cc w/ enclosure D. Butterfield, Nuclear Licensing Manager J. Eenigenburg, Plant Manager DCS/RSB (RIDS)

Licensing Fee Management Branch -

Resident Inspector, RIII Richard Hubbard l 1

J. W. McCaffrey, Chief, Public l Utilities Division kkU DobK$ y0 8.

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DRESDEN 2 & 3 STATUS REPORT FOR PERIOD SEPTEMBER 11 THROUGH 25, 1987

1. PLANT STATUS: ,

A. Unit 2 On September 25,1987, as of 4:00 p.m. (CDT), the Unit was operating at 95% power.

B. Unit 3 As of 4:00 p.m. (CDT), on September 25, 1987, the unit was operating at 80% power for feedwater Regulating Valve Tuning as required for Feedwater System Testing.

2. FACILITY OPERATIONS

SUMMARY

A. Unit Operating Status (September 11 through 25)

1. Unit 2 9/11 Operating at 55% power.

9/12 - 9/17 Operating between 90 and 100% power.

9/18 The unit commenced a shutdown from 95% power because the Standby Gas Treatment System could not maintain the Technical $ specification required .25 inch H7 0 differential pressure between the secondary containment and atmosphere.

This affected both units due to common secondary containment.

9/19 - 9/21 Cold Shutdown for repairs on various secondary containment seals.

9/22 The Unit commenced a normal startup and achieved criticality at 5:10 a.m. (CDT).

9/23 - 9/24 Operating between 50 and 80% power.

9/25 Operating at 95% power.

2. Unit 3 ,

9/11 The unit was critical and increasing power for Feedwater System Testing.

9/12 The High Pressure Coolant Injection (HPCI) system failed to pass the 920 psi surveillance.

Region III Management discussed and approved l

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1 e ;ec continued. testing of the Isolation Condenser and Main Generator Reverse Power Trip circuits with

? an immediate unit shutdown following completion

. of testing.

9/13 The unit commenced a shutdown at 5:50'a.m. (CDT) after completion of the above tests.

9/14' The unit commenced a normal startup after completion of repairs to HPCI. The unit was-critical-at1:00p.m.-(CDT).

9/15 - 9/17 The unit was operating between 40 and 65%;for l "d- Feedwater Regulating Valve (FRV) tuning and testing. HPCI successfully passed the surveillance testing on 9/15.

S/18 'he unit commenced a norma 1' shutdown because of the secondary containment to atmosphere differential not-being greater than .25 inch H 0.

2 9/19 - 9/20 Cold shutdown.

9/21 The unit commenced a normal startup and was critical at 5:50 p.m. (CDT).

9/22 - 9/23 The unit was critical and maintaining less than 5% power while repairing several minor Main Condenser tube leaks.

9/24 - 9/25 Operating between 50-and 80% power for FRV tuning and testing.

B. EQUIPMENT-00T-0F-SERVICE STATUS

1. Unit 2, Same as'last report.

2. Unit 3 Same as last report except HPCI and the Isolation Condenser were returned to service.

~[ Region III Management receives and reviews weekly reports of out-of-service equipment for Dresden Units 2 and 3. Significant equipment out-of-service (such as HPCI) which places the plant into an LC0 action statement would also be expected to be discussed in the Facility Operations Summary and the Items of Special Interest sections of this report. Consequently, Region III intends to delete this section from. future biweekly status reports unless special circumstances warrant an Equipment Out-of-Service section.

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C. Performance Indicators During the past three bi-weekly status reports, most of the performance indicators have maintained improved trends: Total reactor scrams; the last scram was during the first bi-weekly reporting period on August 21 (Unit 2), Personnel errors; only one in six weeks, Licensee Events Reports; only six in six weeks; and Personnel contamination reports; the lowest number of occurrences in the last 24 months.

3. ITEMS OF SPECIAl. INTEREST A. Unit 3 High Pressure Coolant Injection (HPCI) System Failures During the reporting period, HPCI was declared inoperable on two occasions between September 12 and 15. In addition, the unit conrnenced a startup on September 11 after HPCI had been declared inoperable on September 6 (noted in the previous bi-weekly status report). The September 12 failure was related to the gland seal leakoff condenser's pressure control valve located in the cooling water discharge line. The pressure control valve's diaphragm had failed and was replaced. The second failure, on September 15, was due to a valve thermal overload breaker tripping because the minimum flow valve's motor operator seized. The seizure was determined to be caused by inadequate lubrication of the motor operator gear box.

Although the failure rate of HPCI was high during this period, neither of these failures were related to other HPCI failures since January 1987.

B. Shutdown of Both Units Because of Secondary Containment Leakage On September 18, 1987, Units 2 and 3 were shutdown from power operation of 93 and 56 percent respectively, because the Standby Gas Treatment System could not maintain the Technical Specification required limit of .25 inches H p0 differential pressure between the secondary containment and the atmosphere. This differential pressure is required to prevent possible release of airborne contamination during the Design Bases Accident, and, as such, shutdown of both units was required to maintain the design bases.

Several instances of minor seal leakage were repaired and the secondary containment successfully met the Technical Specifications on September 21, 1987.

C. Unit 2 Low Pressure Coolant Injection (LPCI) Minor Water Hanrner On September 22, 1987, Unit 2 experienced piping vibration on the LPCI "A" Torus cooling line. No evidence of damage was discovered and the system was not declared inoperable. However, Region III inspectors will independently assess the event and piping during the week of September 28, 1987.

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D. Unit 3 Feedwater System Performance Testing As of September 25, 1987, most of the Phase I testing (tuning of the control system to the modified Feedwater Regulating Valves) had been completed for the 3B Feedwater Regulating Valve (FRV). During the testing, a 6% valve position oscillation was observed at the 70 and 80% power plateaus. These oscillations are believed to relate to the response time of the mechanical valve position feedback in the pneumatic system. The oscillation was easily controlled and the data collected will be evaluated for further design identifications.

Completion of the 3A FRV portion of Phase I testing is expected around September 30 and Phase II testing will commence then.

4. BI-WEEKLY STATUS REPORTING This is the third bi-weekly status report. The next reporting period (bi-weekly) will be September 25 to October 9, 1987.

5. NRC STAFF ACTIVITIES DURING THE PERIOD A. NRC Resident Staff During this period the staff was comprised of the following personnel:

S. DuPont, Acting Senior Resident Inspector P. Kaufman, Resident Inspector Assisting Inspectors (Unit 3 Startup Special Testing)

N. Gilles, Project Inspector - Region III D. Hills, Operator Licensing - Region III R. Lerch, Reactor Projects Branch 1 Assistant - Region III T. Silko, Headquarters Duty Officer - AE0D R. Stransky Headquarters Duty Officer - AE0D

1. Routine Inspections Observed Units 2 & 3 Startup on September 11, 12, 13, 14, 21 and 22, 1987. Observed Unit 3 Shutdowns on September 13 and 18, 1987, and Unit 2 shutdown on September 18, 1987. The Unit 3 shutdown on September 13, was due to the HPCI system being inoperable and not testing the other ECCS and Isolation Condenser. HPCI 2301-46 valve was found stuck open. This valve is located in the cooling water discharge line from the HPCI booster pump. Shutdown of Units 2 & 3 on September 18, was due to loss of Secondary Containment. (See items 3A and 38).

2. Reactive Inspections The resident staff responded to a Unit 3 Unusual Event on September 13, 1987, (HPCI Inoperable and not testing other ECCS and Isolation Condenser) and to the Unusual Event on both 4

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units when secondary containment couldn't be maintained on y

September 18, 1987.

B. Regional Staff-1, Routine Inspections September 15-18, 1987, R. Sutphin and N. Choules from Region III's Quality Assurance Program section conducted a followup inspection to a 1985 Procurement Inspection to address previous inspection items.

2. Reactive Inspections No reactive inspections were conducted during this period.

C. Headquarters Staff Two Headquarters (AEOD) Duty Officers assisted the resident staff with around-the-clock coverage of Unit 3 Feedwater Performance Testing on September 17-25, 1987.

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