ML20024A878
| ML20024A878 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/13/1983 |
| From: | Kanga B GENERAL PUBLIC UTILITIES CORP. |
| To: | Allan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| REF-SSINS-6820, REF-SSINS-SSINS-6 4410-83-L-0099, 4410-83-L-99, IEB-79-15, IEB-82-01, IEB-82-02, IEB-82-03, IEB-82-04, IEB-82-1, IEB-82-2, IEB-82-3, IEB-82-4, NUDOCS 8307010117 | |
| Download: ML20024A878 (8) | |
Text
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GPU Nuclear Corporation a Nuclear
- 'l3:eoss48 Middletown, Pennsylvania 17057 717 944-7621 TELEX 84-2386 Writer's Direct Dial Number:
June 13, 1983 4410-83-L-0099 Office of Inspection and Enforcement Attn: Mr. J. M. Allan, Acting Regional Administrator US Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406
Dear Sir:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. OPR-73 Docket No. 50-320 IE Bulletins contains GPUNC's response to IE Bulletin 79-15.
Inspection Report 82-05 discussed, in Unresolved Item 82-05-01, outstanding responses to five IE Bulletins. Responses to four of these Bulletins were submitted previously; this is the response to the last of the Bulletins identified in the Unresolved Item.
Additionally, responses to IE Bulletins 82-02 and 82-04 are provided in attachments 2 and 3 respectfully.
IE Bulletins 82-01 and 82-03 reauired no response.
If you have any questions, please feel free to contact Mr. J. J. Byrne of my staff.
Sincerely, B. K. Kanga Director, TMI-2 BKK:RDW:sle Attachments cc:
Mr. L. H. Barrett, Deputy Program Director - TMI Program Office Dr. B. J. Snyder, Program Director - TMI Program Office 8307010117 830613 DR ADOCK 05000 GPU Nuclear Corporation is a subsidiary of the General Public Utahties Corporation
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4410-83-L-0099 RESPONSE TO IE BULLETIN 79-15 TITLE:
Deficiencies in deep draft pumps REQUEST:
The number of deep draft pumps similar to those shown in Figures 1 and 2 of the subject bulletin, utilized in safety related applications in each facility.
RESPONSE
TMI-2 has six (6) deep draft pumps utilized in safety related applications.
There are four nuclear services river water pumps (NR-P-1A,18,1C, ID), and two screen wash pumps (SW-P-1A, 18).
REQUEST:
Manufacturer, model, capacity and plant application.
RESPONSE
A)
Nuclear Services River Water Pumps (NR) 1)
Manufacturer - Byron Jackson 2)
Model No. - 42 RXL 3)
Capacity - 17,100 gpm 4)
Plant application - supplies cooling water for all nuclear related and fuel handling requirements and various HVAC services.
B)
Screen Wash Pumps (SW) 1)
Manufacturer - Byron Jackson 2)
Model No. - 2 CKM 3)
Capacity - 850 gpm 4)
Plant application - Provide flushing water for the traveling water screens and sluice water for the traveling water screens and trash rack troughs.
REQUEST:
Overall dimensions of pumps.
Hr. J. M. A1lan 4410-83-L-0099
RESPONSE
A)
Nuclear Services River Water Pumps 1)
Length from suction bell to discharge centerline - 48' 6" 2)
Suction bell 0.D. - 2' 6" 3)
Discharge flange - 18" 4)
Column Diameter - 18" (Reference Drawing No. 2C-4942)
B)
Screen Wash Pumps 1)
Length from suction bell to discharge centerline - 47' 9" 2)
Suction bell 0.D. - 11 1/4" 3)
Discharge flange - 8" 4)
Column Diameter - 8 5/8" (Reference Drawing No. 2C-4940)
REQUEST:
Summary of startup, testing and routine maintenance history.
RESPONSE
A)
Startup and Testing:
A review of the startup and tasting history of the NR and SW pumps indicated no significant defects with the operation of either pumps.
B)
Routine Maintenance History:
J A review of a representative sample of the routine maintenance history for the NR and SW pumps revealed only minor deficiencies such as:
excessive packing leak, mechanical seal leakage, shaft vibration, etc.
REQUEST:
Operational problems and major repair efforts.
RESPONSE
A)
Operational problems experienced by the NR pumps at TMI-2 have resulted primarily from worn bearings due to restricted lube water flow. The restriction has been attributed to rust and silt accumulation in the lube water piping. The following are examples of the aforementioned problems:
On May 20, 1980, a lab analysis was performed on six bearings from pump NR-P-lD.
The wall thickness for each bearing was less than the original thickness, and the wall thickness varied for each bearing. Originally, the bearings were all the same thickness. The lab analysis attributed the bearing wear to restriction in the lube water flow.
Attcchment 1 Mr. J. M. Allen 4410-83-L-0099 Licensee Event Report 81-11, reported that on April 23,1981, pump NR-P-1A exhibited high vibrations and high current readings as a result of e>.cessive bearing wear.
The following actions were taken to correct the lube flow restriction problems:
1)
The pre-lube piping from the domestic water system and leak-off piping has been replaced with stainless steel piping to prevent rust accumulation.
2)
The pumps are run on a rotating basis in order to prevent excessive silt accumulation in the suction bell area.
3)
Pump vibration is recorded on a monthly basis.
This enables pump wear to be detected in time to allow for routine overhaul.
Major repair efforts have included the overhaul of pumps NR-P-1A, 18, and 1C.
The last of these overhauls was completed in May 1982.
The pumps have been in service for approximately 6 years, which is the average service life for this type of pump.
Pump NR-P-lD was replaced with a new pump in April 1983.
B)
Screen Wash Pumps:
Operational problems with the SW pumps have been similar to those of the NR pumps. Actions to correct these problems are identical to those previously mentioned.
Pump SW-P-1B currently is out of service due to bearirg wear, and has been returned to the manufacturer for repairs.
REQUEST:
The longest interval that each pump has been available for operation without corrective maintenance.
Identify the number of cycles of operaticn during this interval, the duration of each cycle and the operating mode (s)
(recirculation, rated flow, etc.).
Identify the longest continuous operation at or near rated flow conditions for each pump and the status of the pump operability at the end of the run.
RESPONSE
A review of corrective maintenance records indicates the following longest j
intervals that each pump had been operating without corrective maintenance:
Pump Interval I
NR-P-1A 1 yr 1 mo.
(02/04/80 - 03/13/81)
NR-P-18 1 yr 7 mos.
(02/13/80 - 09/01/81)
NR-P-lC 11 mos.
(03/17/80 - 02/04/81)
NR-P-lD 8 mos.
(02/13/80 - 10/29/80) _
SW-P-1A 1 yr. 5 mos. (01/07/82 - present) l SW-P-18 1 yr. 7 mos. (01/03/79 - 07/15/80) l The remaining data requested above is not readily available for accumulation by the licensee.
If additional information is needed, please inform us.
Attechment 1 Mr. J. M. Allrn 4410-83-L-0099 The subject bulletin requested the following information be accumulated by the licensee and made available for inspection at the licensee plant site.
Although we have not accumulated the information as requested, it is available as part of the plant records and is identified below.
REQUEST:
Drawings, sectional assemblies and parts list.
RESPONSE
The above information is contained in the Byron Jackson (BJ) Installation and Operating Instructions filed in the TMI Technical Library under No. 97-00, C-0063.
REQJEST:
Detailed history of pump maintenance (alignment, parts replacement, etc.)
including bearing wear data, replacement frequency and a comparison with the manufacturers rated life for wearing surfaces.
RESPONSE
Maintenance history for the deep draf t dumps is stored in the Plant Maintenance component history report.
REQUEST:
Quality assurance and reliability testing requirements.
RESPONSE
The above requirements are documented in the " Inservice Inspection Program for TMI Unit 2 Pumps."
REQUEST:
Design specifications
RESPONSE
The desig1 specifications for the nuclear river and screen wash pumps are contained in Specification 2555-97.
REQUEST:
Results of tests performed during operation or prior _ to licensing.
t l
Att:chment 1 Mr. J. M. Allan 4410-83-L-0099
RESPONSE
The above tests are maintained in the Plant Maintenance computer history files.
REQJEST:
Details of the procedures used to align the pump column.
RESPONSE
Pump column alignment is performed in accordance with procedure 1410-P7.
REQUEST:
For those cases where the maintenance or operating history of a particular pump indicates that the desip specifications are not being met, initiate appropriate actions that will demonstrate conformance to design requirements.
Provide a description of planned actions within 60 days including a schedule for implementation of any actions that will not be completed within 120 days.
In addition describe any planned or completed tests involved long term operation of prototypes or pumps of similar desig1, which demonstrate the long term operability. of such deep draft pumps at your facility.
RESPONSE
The maintenance and operating history of the NR and SW pumps have not indicated that design specifications are not being met. GRJN has not planned or completed any tests involving long-term operation of the NR or SW pumps.
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4410-83-L-0099 RESPONSE TO IE BULLETIN 82-02 TITLE:
Degradation of threcded fasteners in the reactor coolant pressure boundary of PWR plants (RCPB)
REQUEST:
The Bulletin identified incidents of severe degradation of threaded fasteners in closures of the RCPB due to a) stress - corrosion cracking facilitated in large part by high temperature and high pressure conditions, and b) boric acid corrosion in reactor coolant pumps and valve components.
All PWRs holding and operating license were reauested to perform examinations on the threaded fasteners, and report the results of the examinations.
RESPONSE
In accordance with GPU's letter of May 29, 1980, this bulletin is classified as a long term action bulletin based on the following:
1)
Due to the post-accident condition, the TMI-2 facility is at a low-temperature and low-pressure (< 100 psi and < 1000F) status, thereby eliminating the opportunity for degradation of the RCPB closure fasteners caused by stress-corrosion cracking.
2)
Following the accident, in order to inhibit boric acid corrosion of the RCS components due to the high level of boration utilized in the RCS' system, appropriate levels of sodium hydroxide have been injected into.
the RCS piping.
3)
At present contamination levels, compliance with the requested information would be extremely difficult since many of the components requiring inspection are located in high radiation areas.
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4410-83-L-0099 RESPONSE TO IE BULLETIN 82-04 TITLE:
Deficiencies in primary containment electrical penetration assemblies
RESPONSE
There are no Bunker Ramo Electrical Penetrations installed or planned to be installed in the Unit 2 facility. No further action is reqJired.
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