IR 05000395/1979031
| ML19256G202 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/13/1979 |
| From: | Kellogg P, Skolds J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19256G201 | List: |
| References | |
| 50-395-79-31, NUDOCS 7912280157 | |
| Download: ML19256G202 (6) | |
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIETTA ST N.W., sulTE 3100
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Report No. 50-395/79-31 Licensee: South Carolina Electric and Gas Company Post Office Box 764 Columbia, South Carolina 29218 Facility Name: Summer Nuclear Station Docket No. 50-395 License No. CPPR-94 Inspection at Summe N ear Station near Parr, South Carolina j
Inspe! tor:
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i Date i/gn d Approved by:
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SUmiARY Inspection on September 15 - October 12, 1979 Areas Inspected This routine inspection by the Resident Inspector involving 153 inspector-hours onsite in the areas of preoperational test procedure review, witnessing of preoperational tests, followup of open items, review of inservice inspection program, receipt inspection of safety relation components, independent inspec-tion effort and a meeting with local officials.
Results Of the seven areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
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- 0. S. Bradham, Plant Manager
- J. G. Connelly, Assistant Plant Manager
- S. Smith, Maintenanance Supervisor A. B. Harrison, Operations Supervisor R. W. Campbell, Technical Support Supervisor K. Beale, Health Physics Supervisor D. Hembree, Assistant Startup Supervisor
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A. Smith, QA Site Coordinator C. L. Ligon, Administrative Supervisor A. Koon, Technical Staff Engineer P. Fort, QC Coordinator Other licensee employees contacted included construction craftsmen, technicians, operators, mechanic, security force members, and office personnel.
Other Organizations C. W. Bowman, Westinghouse Startup Group Supervisor W. Pairier, Westinghouse Lead Fluid Systems Test Engineer
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on September 28, -
October 5-12, 1979 with those persons indicated in Paragraph 1 above. The inspector observed the folle.ing crit interviews of Region II personnel:
T. Donat on 9/27/79, K. Walters on 9/28/79.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Meeting with Local Officials On October 12, 1979 the inspector, P. J. Kellogg, Acting Chief, RPS No. 3 and F. J. Long, Acting Deputy Director, Region II met with local officials of Fairfield County, South Carolina. The meeting took place in Winnsboro, 1(554 183
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Donald P. Reed, Fairfield County Administrator and George Douglas, Fairfield County Disaster Preparedness Director. The purpose of the meeting was to acquaint the officials with the NRC and to explain the purpose of the Resident Inspector Program.
6.
Receipt Inspection The inspector observed the receipt inspection of the "B" Charging Pump lith stage impeller. The inspector reviewed the Purchase Order, Certificate of Conformance, Balancing Verification, Heat Treatment and NDE Verification.
The inspector verified the inspection complied with ANSI 45.2.2-1972 (Packaging, Shipping, Receiving Storage and Handling of Items for Nuclear Power Plants) and V. C. Summer Administrative Procedure AP-904 " Receiving Inspection".
The licensee's inspection was performed properly with the exception that the inspector felt a better visual inspection could have been performed. The inspector identified. a rust colored material on the vane of the impeller, which later was determined to be an NDE solution which was not removed by the vendor.
7.
Preoperational Test Procedure Review The inspector reviewed the following preoperational tests:
SI-3 Accumulator Blowdown Test SI-6 Safety Injection Flow Balancing RH-1 Residual Heat Removal CS-1 Volume Control Tank Auto Makeup CS-7 Boric Acid Flow Test SP-3 Caustic Addition Drawdown Test Results were acceptable with the following exceptions:
SI-3 - In reviewing SI-3, the inspector noted that Section 6.3.2.2.6.3 a.
of the FSAR states that "when the RCS is being pressurized during normal plant heatup, the check valves are tested for leakage when pressure reaches about 1000 psi across the valve".
The inspector informed the licensee that this statement in the FSAR indicates that a formal leak test would be required every time the plant is pressurized.
The inspector noted that there were no specific details concerning the conduct of this test, i.e.
when and how the test will be accomplished.
This item will remain open pending future review by the inspector (79-31-01).
b.
SI-6 - In reviewing SI-6, the inspector noted that the procedure allowed the CKV/SI pumps to operate up to 680 gpm which would be a predicted runout condition. However, the Technical Manual on this type of pump indicates a maximum flow of 650 gpm. The licensee indicated that the vendor representative for the pump said that the pump could be run up to 680 gpm without having run out occur. The inspector informed the licensee that if the pump is going to operate
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at greater than 650 gpm on a Safety Injection, the fact that the pump will be operating at greater than the Technical manual maximum flow should be documented either in the Technical Manual or the Preopera-tional Test. This item will remain open (79-31-02) pending licensee documentation of this condition.
RH-1 - In reviewing RH-1, the inspector noted that a limit and pre-c.
caution of the test required a minimum recirculation flow of 500 gpm while running the pump. The pumps were run with no indication of recirculation flow other than the recirculation valve being open. The assumption was made that the 500 gpm requirement could be met as long as the recirculation valve was open.
The inspector informed the licensee that it was not adequate to assume a limit and precaution was met.
The licensee agreed to install a gage to measure recirculation flow prior to running the pump again.
This item will remain open until the inspector verifies that adequate recirculation flow exists.
(79-31-03)
The test indicates that the interlock between lolo RWST coincident with a SI signal giving an auto open signal to the RHR sump suction valves would be added to RH-1 at a later date.
This item will remain open until this interlock is tested.
(79-31-04)
d.
CS-1 - In reviewing CS-1 the inspector noted that there was no alarm on the control board which warned the operator that suction for the charging pumps had switched over from the VCT to the RWST. This occurs at approximately 5% level in the VCT. The inspector informed the licensee that this was not a safety concern but the inspector felt that the operators should be alerted to the fact that the charging pumps were pumping in 2000 ppm Boric Acid solution from the RWST instead of the water in the VCT. The licensee acknowledged this issue and agreed to look into it.
CS-7 - In reviewing CS-7 the inspector had the following comments:
e.
(1) Section 3.9 of the procedure incorrectly referred to level tap LT 101 as LT 110.
(2) Step 6.1.14 states open valve 8303 to fill the batching tank.
This step should open valves 8308 and 8302 to fill the batch tank and line up the tank for the next step in the procedure.
(3) Step 6.1.19 requires valve 8311B to be open to perform the step.
On step 6.1.17 valve 8311B was closed and not reopened.
(4) Steps 6.2.6.1 and 6.2.6.2 are identical.
(5) Section 6.4 tests the temperature controls on the batch tank and storage tank.
The test does not include tolerences for alarm actuation and clearing. For instance, 6.4.1.3.1 states that the low temperature alarm clears at less than 95 F.
There is no tolerance given around 95*F.
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(6) The steam admission valve to the batching tank in never checked for proper cycling.
(7) There is no signoff in the acceptance criteria for proper func-tioning of the temperature alarms.
(8) Step 8.1.4 requires acceptance criteria be checked for shutoff head and design flow of the boric acid pumps. However, no data
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is taken in the test to verify either of these parameters.
(9) One of the stated purposes of the test is to verify the steam delivery system is sufficient to raise the temperature of the batching tank. This is never checked in the procedure. All of these comments will remain open until the inspector reviews the revised procedure.
(79-31-05)
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SP-3 - In reviewing SP-3, the inspector noted the following:
(1) A Limit and Precaution in the test stated that the Spray Pumps should be stopped when the lolo alarm on the RWST is actuated.
Step 6.2.8 of the test notes that the lo lo alarm will actuate but to run the pump for 4 minutes past the alarm.
(2) A Limit and Precaution states that all applicable limits an'
precautions in the RHR and CHV/SI pump technical manuals should be followed. The inspector noted that clearer guidance should be given to the operators of the pumps during the test since the RWST would be pumped to a low level.
(3) The acceptance criteria did not contain a step to sign off the drawdown rate as being acceptable.
The above items were corrected by initiating minor changes to the procedure and the inspector had no further questions.
8.
Preoperational Test Witnessing The inspector witnessed portions of the following preoperational tests:
MS01-H1 Secondary Hydro a.
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SI-6 Safety Injection Flow Balancing c.
RH-1 Residual Heat Removal The inspector verified the tests were done in accordance with the proce-dures, verified the acceptability of the results and evaluated the performance of the personnel performing the tests. Finds were acceptable.
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9.
Inservice Inspection Program In reviewing the proposed pump and valve list for the Inservice Inspection Program, the inspector noted that not all motor operated valves had stroke time limits listed.
ASME Section XI, Article IWV-3410 (c) (i) states that the limiting valve of full stroke time of each power operated valve of shall be specified by the owner. This item will remain open pending future review of the pump and valve list by the inspector (79-31-06).
10.
Independent Inspection Effort The inspector toured the plant at various times during the period of inspec-tion. Findings were acceptable with the exception of the following:
The inspector noted that the "B" CHV/SI Pump was being worked on a.
September 26, 1979 without the pump being tagged out electrically.
b.
The inspector noted on September 26, 1979 that valve 8130A was red tagged with a tag for valve 8130B. The index sheet for the red tag indicated that the tag was cleared but the operator could not find the tag to actually clear it.
He could not find it because the tag was on the wrong breaker.
The licensee's administrative program requires them to have a tag out system and procedures exist for administrative control of the tags themselves.
However, since the plant does not have an OL and therefore do not have Technical Specifications the problems identified in the tagout system do not represent a plant safety concern. However, the inspector informed the licensee that these problems indicate a serious personnel safety concern and a potential plant safety concern after an OL is issued.
This item will remain open (79-31-07) pending future tagout review by the inspector. The inspector also observed a Tag Out lecture given by the licensee on October 1, 1979.
11.
Followup of Open Items a.
Open Item 78-29-01 This item dealt with a statement in the FSAR which indicated that the control rods are inspected prior to removal of the fuel assembly from the shipping container. The FSAR has been amended to indicate that the control rods are inspected after the fuel assemblies are removed from the shipping container. This item is closed.
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b.
Open Item 78-29-02 This item dealt with the lack of documentation concerning periodic testing of the diesel driven fire pump. The weekly tests are now being documented in the control room. This item is closed.
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