ML19261D751
| ML19261D751 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/25/1979 |
| From: | Heishman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wachter L NORTHERN STATES POWER CO. |
| Shared Package | |
| ML19261D752 | List: |
| References | |
| NUDOCS 7906260321 | |
| Download: ML19261D751 (2) | |
See also: IR 05000282/1979008
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G L E N E LL Y N. IL LINDIS 60137
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APR 2 51979
Docket No. 50-282
Docket No. 50-306
Northern States Power Company
ATTN:
Mr. Leo Wachter
Vice President
Power Production and
System Operation
414 Nicollet Mall
Minneapolis, MN 55401
Gentlemen:
This refers to the inspection conducted by Messrs. L. G. McGregor,
J. D. Smith, B. M. K. Wong and J. F.
Streeter of this office on
February 12-16 and March 14-16, 1979, of activities at the Prairie
Island Nuclear Generating Plant, l' nits 1 and 2, authorized by NRC
Operating Licenses No. DPR-42 and No. DPR-60 and to the discussion
of our findings with Mr. F. P. Tierney at the conclusion of the
inspection.
The e losed copy of our inspection report identifies areas examined
during the inspection. Within these areas, the inspection consisted
of a selective examination of procedures and representative records,
observations, and interviews with personnel.
During this inspection, certain of your activities appeared to be
in noncompliance with NRC requirements, as described in the enclosed
Appendix A.
This notice is sent to you pursuant to the provisions of Section
2.201 of the NRC's " Rules of Practice," Part 2, Title 10, Code
of Federal Regulations.
Section 2.201 requires you to submit to
this office within twenty days of your receipt of this notice a
written statement or explanation in reply, including for each
item of noncompliance: (1) corrective action taken and the results
achieved; (2) corrective action to be taken to avoid further non-
compliance; and (3) the date when full compliance will be achieved.
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790626039\\
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A
.
Northern States Power
-2-
APR 2 51979
Company
In accordance with Section 2.790 of the NRC's " Rules of Practice,"
Part 2, Title 10, Code of Federal Regulations, a copy of this
letter, the enclosures, and your response to this letter will be
placed in the NRC's Public Document Room, except as follows.
If
the enclosures contain information that you or your contractors
believe to be proprietary, you must apply in writing to this office,
within twenty days of your receipt of this letter, to withhold such
information from public disclosure.
The application must include a
full statement of the reasons for which the information is considered
proprietary, and should be prepared so that proprietary information
identified in the application is contained in an enclosure to the
application.
We will gladly discuss any questions you have concerning this
inspection.
Sincerely,
o
R. F. Heishman, Chief
Reactor Operations and
Nuclear Support Branch
Enclosures:
1.
Appendix A, Notice
of Violation
2.
IE Inspection Reports
No. 50-282/79-08
and No. 50-306/79-07
cc w/encls:
Mr. F. P. Tierney, Jr.,
Plant Manager
Central Files
Reproduction Unit NRC 20b
Local PDR
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066
John W. Fe rman, Ph .D. ,
Nuclear Engineer, MPCA
/
.
Appendix A
Northern States Power
Docket No. 50-282
Company
Docket No. 50-306
Based on the inspection conducted on February 12-16 and March 14-16,
1979, it appears that one of your activities was in noncompliance
with SRC requirements as noted below. This item is a deficiency and
applies to Units 1 and 2.
Technical Specifications 4.16.A.1 and 4.16.A.2 became effective
February 14, 1978, and require, respectively, that fire detectors
exterior to primary containment be functionally tested once every
six months and that the detector alarm circuits also be tested
every six months.
Contrary to the above, the initial tests (SPll89) of the fire
detectors and alarm circuits were not conducted until (December 28,
1978) approximately ten and one-half months after the technical
specifications became effective.
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.
U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-282/79-08; 50-306/79-07
'%
Docket No. 50-282; 50-306
Licensee:
Northern States Power Company
414 Nicollet Mall
Minneapolis, MN 55401
Facility Name:
Prairie Island Nuclear Generating Plant, Units 1 and 2
Inspection At:
Prairie Island Site, Red Wing, F5
Inspection Conducted:
February 12-16 and rarch 14-16, 1979
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Inspectors:
L. G. "cGregor (February 12-16, 1975)
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J. D. Smith (March 14-16, 1979)
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-
J.
F.
Streeter (February 14-15, 1979)
B. M. K. Wong (February 14-15, 1979)
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F. Streeter, Chief
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Approved By:
Nuclear Support Section 1
Inspection Summary
Inspection on February 12-16 and March 14-16, 1979 (Report No. 50-282/
79-08: 50-306/79-07)
Areas Inspected: Routine, unannounced inspection of calibration and
surveillance of safety related components and equipment and implemen-
tation of ASME Code Section XI and pump and valve test program.
The
inspection involved 93 inspector-hours onsite by four NRC inspectors.
Results: Of the three areas inspected, no Items of Noncompliance were
identified in two areas. One Item of Noncompliance (Deficiency -
delayed conduct of fire system surveillance, Paragraph 5.c) in one area.
.
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7906260330
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DETAILS
1.
Persons Contacted
+*F.
Tierney, Plant Manager
+E. Watz), Superintendent, Plant Engineer, Radiation Protection
A. Hunsted, Staff Engineer
- J.
Hoffman, Plant Engineer, Technical
G.
Sundberg, Instrument Engineer
- R.
01schlager, Instrument and Control Coordinator
+B . Stephens, Mechanical Engineer
D. Walker, Shift Supervisor
R. Hoffey, Shift Supervisor
R. Ryan, Shift Supervisor
The inspectors also talked with and interviewed several members of
the operations, techanical and engineering staffs.
- Denotes those present at the exit interview on February 16, 1979.
+ Denotes those present at the exit interview on March 16, 1979.
2.
Calibration of Safety Related Components Recuired by Technical
Specifications (Units 1 and 2)
The inspector reviewed plant calibration records, selected logs and
records for the below listed calibration activities.
This review
was performed to determine that the frequency of calibration was
met; the service status of the system was in conformance with the
applicable limiting conditions of operations; the procedures used
to calibrate the components were reviewed and approved as required
by the Technical Specifications; the procedures used contained
acceptable trip settings using applicable technical specification
requirements; the procedures used contained detailed stepwise
instructions; the technical content of the procedures would result
in satisfactory calibration; the qualifications of two individuals
in the I6C group having responsibilities for performing calibra' ions
were adequate.
" Reactor High Flux Intermediate Range Calibration,"
a.
Test 2007 and 1007A
b.
" Reactor High Flux Power Range Calibration,"
Test 2009 and 1009
c.
" Pressurizer Level Control Calibration,"
Test 2001, 2048, 2182, 1048, 1001 and 1182
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d.
" Emergency Core Cooling Temperature Element Calibration
Safety Injection System,"
Test 108 and 2088
" Residual Heat Removal Pump Flow Calibration,"
e.
Test 2020
f.
" Accumulator Boron Concentration Tests,"
Tests 1065 and 2065
g.
" Containment System Emergency Charcoal Filter Pressure Drop
Calibration,"
Tests 1114 and 2114
h.
" Containment Pressure Calibration Sensing Instrumentation,"
Tests 1001, 2001 and 2045
i.
" Containment Temperature Calibration,"
Tests 1038 and 2038
j.
" Station Battery Load Test,"
Test 1098 and 2098
k.
"4 KV Volt and Frequency Calibration,"
Tests 1014 and 1015
1.
" Containment Sump Level Instrument Tests and Calibration,"
Tests 1030 and 2030
"Ref ueling k'ater Storage Tank Level Calibration,"
m.
Test 2023
n.
" Volume Control Tank Level Channels Calibration CVC System,"
Test 2025
" Boric Acid Makeup Flow Channel Calibration,"
o.
Test 2029
p.
" Accumulator Level and Pressure Test and Calibration,"
Test 2031
q.
" Control Rod Drive Exhaust Air Temperature Calibration,"
Test 2043
No items of noncompliance or deviations were identified.
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3.
Calibration of Safety Related Components Not Specified by .achnical
Specification (Units 1 and 2)
The inspector reviewed plant calibration records for the below listed
components. This review was performed to determine if the operating
range / accuracy of components were consistent with applicable Technical
Specifications /SAR; the procedurer, used to calibrate the components
were reviewed and approved as required by Technical Specifications;
the procedures used contained acceptance criteria consistent with
Technical Specifications /S AR; the procedures used contained detailed
instructions commensurate with the complexity of the calibration and
that the technical content of the procedures would result in satis-
factory calibration.
a.
Systems
(1) " Analog Reactor Control System,"
Test 1548 and 2548
(2) " Diesel Fire Pump Weekly Test and Calibration,"
Test 1524
(3) " Fire Protection System Test and Calibration,"
Test 1568
(4) " Explosive Detector Calibration,"
Test 1621
(5) " Turbine Bearing Fire Protection Test and Calibration,"
Test 1592 and 2592
(6) " Electrical Penetration Surveillance Test and Calibration,"
Test 2537
b.
Instruments
(1) " Mixed Bed A EFF Conductivity Cell,"
CEC-6 System ODE
(2) " Reactor Coolant Drain Tank N Supply Pressure,"
9
'
IPC 1014 System OWL
(3)
"WST Tank Rad Monitor,"
Inst. 59062 System DRD
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,
(4) " Station Air Compressor Receiver Pressure Switch and Valve,"
Inst. 16086 and 31191 System OSA
(5)
"Decon Area Sump Level Switch,"
Inst. 16677 System OWL
(6) " Turbine High Pres' re Cylinder Flange Temperature,"
Inst. 42083-04 System ITB
(7) " Hydrogen Recombiner Product Gas Oxygen Analyzer,"
10 AR-1119 System OWG
20 AR-1119 System OWG Recorder and Alarm
No items of noncompliance or deviations were identified.
4
Surveillance Test Witnessing
The following surveillance testing was witnessed to verify that all
test prerequisites were met and the stepwise procedures were completed
as required:
a.
Test SP 1186 Emergency Diesel Generator Start and Operation,
Unit 1 (Rev. June 16, 1978).
b.
Test SP 1106A Diesel Driven Cooling Water Pump, Unit 1
(Rev. June 16, 1978).
c.
Test SI 1088 Operational Test of Safety Injection Pumps,
Unit 2 (Rev. June 16, 1978).
No items of noncompliance or deviations were identified.
5.
Surveillance of Safety Related Components or Equipment (Units 1
and 2)
a.
Purpose of Review
The inspector reviewed plant surveillance records to determine
if test procedures are approved in accordance with the Tech-
nical Specifications; test procedures include appropriate (1)
prerequisites and preparations, (2) acceptance criteria, and
(3) instructions to ensure tested item is restored to operation
following the test; rechnical content of procedures assures
compliance with the Technical Specifications and Inservice
Inspection Program; tests were performed within the time
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frequencies specified in the Technical Specifications and
Inservice Inspection Program; tests were performed by qualified
individuals; test results were reviewed as required by facility
administrative requirements; test results were in conformance
with Technical Specifications and Inservice Inspection Program;
appropriate action was taken for test results not meeting the
acceptance criteria.
b.
Administrative Documents, Personnel Qualifications and Test
Records Reviewed
(1) Test Records
Test Procedure
Date of Tests
SP 1072-45, " Local Leakage Rate Test
3/25/77, 3/19/76
of Penetration 45"
4/29/75 and 4/26/75
SP 1089, " Residual Heat Removal
2/13/79, 1/30/79,
Pumps and Suction Valves from the
1/31/79
Refueling Water Storage Tank,"
Rev. 10
SP 1090, " Containment Spray Pump
2/22/79, 1/25/79
Test" Rev. 14, dtd 11/26/78
12/21/78
SP 1099, " Main Steam Isolation
4/12/78, 3/28/78,
Valves Closure Test," Rev. 2,
12/9/77
7/5/77
SP 1102, " Turbine-driven Auxiliary
1/31/79, 12/27/78,
Feedwater Pump Test," Rev. 8,
11/28/78
8/2/78
SP 1106, "12 Diesel Cooling Water
2/23/79, 2/15/79,
Pump Test," Rev. 4, 6/26/78
2/14/79 and 2/8/79
SP 1151, " Cooling Water System
1/23/79, 10/17/78,
Test," Rev. O, 4/16/77
7/18/77
SP 1155, " Component Cooling System
1/18/79, 12/13/78,
Test," Rev. 5, 10/30/78
11/15/78
SP 1156, " Low Level Gas Decay Tanks
12/5/78, 9/8/78,
to Plant Vent Control Valve Test,"
6/6/78
Rev. 2, 6/5/78
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SP 1157 6 2157, " Post LOCA Hy'drogen
4/10/78, 12/9/78
Control System Valve Operation,"
Rev.
2, 6/5/78
SP 1160, " Chilled Water Crossover
12/19/78, 9/19/78,
Control Valve Test," Rev. 1,
6/22/78, 3/21/78,
6/5/78
12/20,77, 9/20/77,
6/21/77
SP 1161, " Control Room Chilled
2/20/79, 1/23/79,
Water Pump Test," Rev. 3, 6/20/78
12/19/78, 11/21/78,
10/17/78, 9/19/78,
8/22/78, 7/18/78,
6/22/78, S/23/78,
4/18/78, 3/21/78,
2/21/78, 1/17/78
SP 1180, " Diesel Cooling Water
1/26/79, 12/22/78,
System Test," Rev. 3, 12/1/78
11/24/78
SP 1159, " Reactor Vessel Injection
2/27/79, 11/27/78,
Isolat'on Valve Test," Rev. 1,
8/29/78
6/5/78
SP 1002, " Analog Protection
2/16/78
Functional Test," Rev. 5,
8/29/78
SP 1178, "CVCS Check Valve Test"
4/2/78, 12/9/78
SP 1187, " Diesel-driven Fire
1/78 thru 1/79
Pump Battery Inspection,"
Rev. 3, 8/2/78
SP 1096 6 1097, " Station Battery
1/78 thru 1/79
Monthly Test and Station Battery
Quarterly Inspection," Rev. 4,
10/30/78
SP 1053, " Fire Protection System
9/15/78, 10/13/78
Monthly Fire Pump Running Test,"
11/17/78, 12/15/78,
Rev. 6, 10/13/78
1/19/79
SP 1189, " Safety Related Fire
12/28/78
Detector Check," Rev. O, 9/28/78
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a
SP 1190, " Emergency Diesel Generator
8/78 thru 1/79
011 Storage Tanks Sampling Procedure,"
Rev.
O, 11/15/78
SP 2130, " Containment Vacuum Breakers
12/29/77, 3/28/7F,
Quarterly Test," Rev. 3, 8/2/77
6/27/78, 0/26/78,
12/28/79
SP 2171, " Tech Spec Shock Suppressor
11/14/77, 12/2n/78
Check,"
Rev.
O, 10/17/77
SP 1046, " Full Length Control Rod
12/14/78
Drop Timing," Rev.
4, 6/20/78
(2/
Personnel Qualification Records
The qualification records for two individuals involved in
the tests identified above were reviewed to determine if
the individuals were qualified in accordance with the
Technical Specifications and ANSI N18.1.
(3) Administrative Documents
The fcllowing facility administrative documents were used
during the review:
(a)
Operations Manual Appendix G, Section 6, " Surveil-
lance," dated January 31, 1977.
(b)
" Northern States Power Company, Prairie Island
Nuclear Generating Plant, ASME Code Section XI
Inservice Inspection and Testing Program and
Information Required for NRC Review of Requests
for Relief from ASME Code Section X1 Requirements,"
Rev. 1, dated September 15, 1978.
c.
Findings
(1) Technical Specifications 4.16.A.1 and 4.16.A.2 became
effective February 14, 1978, and require, respectively,
that fire detectors exterior to primary containment be
functionally tested once every six months and that the
detector alarm circuits also be tested every six months.
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(
e
Contrary to the above, the initial tests (SP 1189) of
the alarm circuits were not conducted until (December 28,
1978) approximately 10 1/2 months after the technical
specifications became effective.
This is an Item of Non-
compliance (50-282/79-0-01; 50-306/79-0-01) of the
Deficiency level.
(2) The monthly emergency diesel generator fuel oil sample
analysis for viscosity, water, and sediment was not
performed during the period November 21, 1978 through
January 12, 1979, as required by Technical Specification 4.6.A.1.c.
However, the inspector verified that this
was an isolated example.
(3) A few examples were noted where the tester was identified
in the test documentation but the tester's signature was
not documented, where there were delays in forwarding
test results from the group supervisor to the Surveil-
lance Coordinator, where temporary test equipment used
to obtain performance data was not specifically identi-
fied, and where test documentation did not indicate
abnormal conditions were promptly brought to the attention
of the appropriate supervisor.
The licensee instructed
personnel involved in the conduct and review of tests of
the importance of the proper conduct, review, and docu-
mentation of tests.
No other items of importance were noted.
6.
Plant Tour (l' nits 1 and 2)
The inspector conducted a tour of various areas of the plant to
observe operations and activities in progress, general housekeeping
and cleanliness, and equipment caution or lockout tags.
Exceptional
cleanliness was observed throughout areas toured.
No items of noncompliance or deviations were identified.
7.
Exit Interviews
The inspector met with licensee representatives (denoted in Paragraph
1) on February 16, 1979, and at the conclusion of the inspection on
March 16, 1979. The inspectors summarized the purpose, scope, and
findings of the inspection.
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