IR 05000263/1977004
| ML20024G335 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/23/1977 |
| From: | Barker J, Choules N, Fiorelli G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G333 | List: |
| References | |
| 50-263-77-04, 50-263-77-4, NUDOCS 9102110316 | |
| Download: ML20024G335 (10) | |
Text
.
.-
..
.
.
UNITED STATES NUCLEAR RECULATORY COMMISSION
,
OFFICE OF INSPECTION AND ENTORCEMENT
{
REGION III
Report of Operations Inspection IE Inspection Report No. 050-263/77-04 Licensee:
Northern States Power Company 411, Nicollet Mall Minneapolis, MN 55401
.
Monticello Nuclear Cencrating Plant License No. DPR-22 Monticello, MN Category:
C Type of Licensee:
BWR GE 1670 MWt Type of Inspection:
Routine, Unannounced Dates of Inspection:
March 7-10, 1977 hkcWW: f><-
(
Principal Inspector:
d. C. Choules
-
-S['>~l/77
.
,'
p (Date)
Accompanying Inspector: g. Ba f-7 77
'
/ (Datc)'
/
Other Accompanying Persor.nel:
None bas /2 5 <
m vrX.-
>'
ton Florell'l Acting Chief
.'i,!') )
s
'
Reviewed By:
Reactor Projects Section 2 JDate)
l l
[
l l
(
l I
9102110316 770324 PDR ADOCK 05000263
.
"'
l
- _ _
_ _ _ _ _ _ _ - - _
.
.
.
I.
SUMMARY OF FINDINGS (
,
Inspection Summary Inspection on March 7-10, 1977, (77-04):
Review of plant operations, nonroutine event reports, calibrations, quality assurance program, and safety limits, limiting safety systems setting and limiting conditions for operations.
No items of noncompliance were identified.
Enforcement Items
.
.
None.
Licensee Action on Previously Identified Enforcement Items Not applicabic.
,
Other Significant Items A.
Systems and Components None.
B.
Facility Items (Plans and Procedures)
None.
(
C.
Managerial Items None.
D.
Deviations None.
E.
Status of Previously Reported Unresolved Items None.
Management Interview Management interviews were conducted with Messrs. Eliason and Clarity on March 9, 1977, and with Messrs. Antony and Scheinost on March 10, 1977.
A.
Plant Operations The inspectors stated that they had reviewed general plant operations which included review of operating logs, night orders, significant (
i l
--
-
-- _ -- --- _-- ---
- - _ - _
- _ _
_
-.
.a
.
.
.
.,
.
,
(
operating events (SOE's), jumper and tog out logs, discussions with operators, reactor coolant chemistry records, and a tour of the plant.
Discrepancies which were noted during the plant tour were dis-
,
cussed. (Paragraph 2 Report Details)
'
B.
Reportabic Occurrences The inspector stated he had reviewed the corrective action for RO 77-03, and it appears to be adequate.
(Paragraph 3, Report Details)
C.
Calibrations of Equipment The inspector stated he had reviewed the calibration of equipment which are identified by the Technical Specifications as requiring specific calibrations and no items of concern were identified.
(Paragraph 4, Report Details)
D.
Quality Assurance Program Review The inspector stated he had reviewed selected Administrative Control Directives with licensee personnel regarding chat 4ges and awareness of requirements and no discrepancies were noted.
(Paragraph 5, Report Details)
E.
Safety Limits, Limiting _ Safety Systems Setting and Limiting Conditions for Operations The inspector stated he had reviewed the subject items and no significant concerns were identified.
(Paragraph 6, Report Details)
l l
l
-
I
'
,
l t
3_
l
- - - - - - -
.
.
.
-
-
^
-
.
.
.
_
...
.
.
REPORT DETAILS
l 1.
Persons Contacted l
L. R. Eliason, Plant Manager M.11. Clarity, Superintendent, Plant Engineering and Radiation Protection j
W. E. Anderson, Superintendent, Plant Operations and Maintenance D. D. Antony, Plant Engineer, Operations I
W. H. Shamla, Plant Engineer, Technical W.11. Sparrow, Operations Supervisor j
F. L. Fey, Radiation Piotection Supervisor W. J. Hill, Engineer, Instruments H. E. Nimo, Maintenance Supervisor J. R. Pasch, Training Supervisor i
P. A. Pochop, Quality Assurance Engineer i
R. L. Scheinost, Quality Assurance Engineer i
H. M. Kendall, Plant Office Supervisor R. A. Goranson, Engineer M. F. Hammer, Engineer
D. E. Nevinski, Engineer, Nuc1 car R. A. Knitch, Shift Supervisor R. A. Mielke. Shift Supervisor M. W. Onnen, Lead Plant Equipment and Reactor Operator E. W. Seedorff, Instrument and Control Specialist K. R. LaBau Instrument and Control Specialist W. C. Smida. Instrument and Control Specialist i
R. J. Rohland, Plant Equipment and Reactor Operator 2.
Plant Operations a.
Plant Tour (1) The inspectors performed a plant tour accompanied by a licensee representative.
The following items were noted during the tour and discussed with the licensee.
l (a) Open sacks of boric acid were stored in the standby liquid control area.
The licensee had these sacks placed in drums with lids prior to the conclusion of the inspection.
(b) An accumulation of oil which had 1 caked from the diesel motors was noted in the area of emergency diesel generators. The licensee was in the process of cleaning this up at the conclusion of the inspec-tion.
-4-
,
i
.
L
..
.
'g (c)
Several paper container drums were stored on the A
third and fourth floors of the reactor building presenting a possibic fire hazard.
The licensee stated they were aware of this and they are investi-gating ways to reduce or climinate the drums from these areas. The dtums are used for storage and shipping radiation protection clothing.
(d) The fire hose at station No. 52 showed signs of some deterioration.
The licensee is investigating this.
(2)
Selected savles for the torus watcr level instrumentation were checked for proper alignment and no discrepancies were noted.
(3) The inspector reviewed the status of various annunciators which were lit in the control room with a control room operator. Adequate explanations were given as to why these annunciators were lit, b.
The jumper-bypass and the hold and secure card logs were reviewed and no discrepancies were noted.
c.
Logbooks The inspectors reviewed the control room and reactor log, the shift supervisor log and the radwaste building log for selec-
'
ted days during the period November 16, 1977,to March 7, 1977, and confirmed that entries were filled out and initialed, that entries give sufficient details to identify the action, and the Operations Supervisor is reviewing and initialing the log sheets indicating his review.
d.
Night Order Book The subject orders were reviewed for the period December 15, 1977,to March 11, 1977,and no discrepancies were noted.
c.
Management Memos The subject memos which were in ef fect were reviewed and no discrepancies were noted, f.
Significant Operating Events (SOE's)
The following SOE's were reviewed and no items of concern were identified.
i (
-5-P
,
_ _.
.,
-
___
...
.
.
(_
(1) M-SOE-76-ll, Excessive Reactor Clean-up Recirculation
'
Pump Failures.
(2) M-SOE-76-12. TIP Ball Valve Connector Failure, October 7, 1976.
(3)
M-SOE-77-02, Exceeding PICOMR Envelope Ramp Decrease.
g.
Reactor Coolant Chemistry Subject surveillance test (ST) records reviewed for the period J
January 1, 1977 to March 1, 1977 are as follows:
(1) ST 0122, Reactor Coolant Iodine-131 Dose Equivalent Activity (2) ST 0125, Reactor Coolant Chloride / Conductivity
'
(3) ST 0228, Reactor Coolant I-133; Cleanup Flow Rate; Power Level Review of these records indicated:
(1) No evidence of fuel failure; and (2) Conductivity and chloride concentrations were maintained far below the Technical Specifications limit.
3.
Reportable Occurrences RO 77-031 was reviewed with the licensee.
This occurrence resulted t
when the No. 3 TIr ball valve failed to open and subsequently was tapped and it opened.
Investigation of the valve revealed no reason
why the valve did not open.
This is the fourth such occurrence.
The licensee replaced the valve with the latest model wh1Gi has an improved operator.
RO 77-01, ! noperable Accumulator on CRD HCN 14-19, was revicwed in I
the office and is considered closed.
4.
Calibrations of Equipment a.
Primary Calibrations Standard The inspector reviewed calibration records for the following
,
primary calibration standards.
,
(1) Manfield and Green Daad Weight Tester
!
The accuracy of the weights were recertified in December
'
(
1976.
The licensee plans to recertify these weights l
every five years.
l 1/
RO 050-263/77-03, NSP to RIII, dtd 2/9/77.
l 2/
RO 050-263/77-01, NSP to RIII, dtd 2/17/77.
(
-6-
.
g
.ll
,
..s-
.
.
..
.
,
,
(2) Hewlett Packard DC Voltage Standards
-
k This voltage standard is being calibrated quarter.y as
prescribed by the licensee.
(3) Fluke Digital Voltmeter This voltmeter is being calibrated quarterly as prescribed.
(4) ESI Resistance Bridge This resistance bridge is to be calibrated every two years as prescribed.
(5) Heise Pressure Gnune (2000 psigl
.
This gauge is being calibrated at two month intervals as prescribed.
The accuracies of these calibrations were traceable to the National Bureau of Standards.
The storage of equipment appears to be adequate.
b.
Component Instrumentation The inspector reviewed the previous year's calibration records for the following component instrumentation and determined that instruments were being calibrated using procedures as required by the licensee.
Procedure Number Procedure Title and/or Instruments 0019 Reactor High Pressure Scram Instrumentation Calibration 0041 APRM Downscale and Flow Variable Rod Block Calibration 0022 Condenser Low Vacuum Scram Calibrations 0055 Msin Steam Line Low Pressure Group I Isolation Instrument Calibration 0033 ECCS Pump Start Permissive Calibration 0028 Reactor Low-Low Water Level ECCS Initiating Instrument Calibration Procedure 0026 Recirculation Flow Instrument Calibration 0099 Core Spray Header Differential Pressure Calibration
-
~7-(
.
I
.
-
-
-
-
-
t
k
--
-
.
...
.
.
Review of the calibration procedures for the above instrument
'
f5 indicated that satisfactory calibration of related component will result. Trip points where applicabic for the above instruments comply with Technical Specification requirements.
The inspectors witnessed the calibration of the condenser low vacuum scram per calibration procedure 0022 and the calibration of main steam line isolation high flow instrument per calibra-tion procedure 0052.
No discrepancies were noted during the performance of the calibrations.
c.
I&C Specialist Qualifications The inspector reviewed qualifications records of two I6C
,
apecialists and verified they were in accordance with ANSI Standard 18.1.
,
5.
Quality Assurance Through review of Administrative Control Directives (ACD's) and by direct questioning of licensee personnel, the inspector established that changes and revisions made to the Operational Quality Assurance Plan were in conformance with the plan and that licensee personnel having responsibility for implementing the QA program were aware of applicable ACD's and changes to these ACD's.
6.
Safety Limits, Limiting Safety System Settings, and Limiting Condi-I tions for Operations The inspector verified that operations were in conformance with Technical Specifications safety limits, limiting safety system settings, and limiting conditions for operation.
The following systems were reviewed:
a.
Reactivity and Power Control c.
Power Conversion and Auxiliary Systems d.
Containment Systems e.
Emergency Core Cooling Systems
.
.
f.
Standby Liquid Control System g.
Elcetrical Systems (
-8-
.
P *
_
..
.
,
._
. _.
_
_.
_
...
The inspector conducted a detailed review of the following records:
Vessel Flange /Shell Temperature Chart - 2/23/77 and 2/24/77, a.
b.
Startup Packages 4106 (10/19/76), #107 (!!/11/76) #108 (2/23/77).
(1) Plant Restart Checklist (Form 2163)
(2) Startup Checkof f (Form 2167)
(3) Plant Prestart Checklist (Form 2152)
(4) Predicted Critical for Plant Startup (Form 215a)
Scram Report Packages #44 (10/15/76), #45 (11/11/76), #46 (2/23/77),
c.
d.
System Surveillance Schedule Summary - 1/2/77 to 3/2/77.
c.
System Surveillance Packages (1) Reactar High Pressure Scram Instrument Test and Calibration Procciture 0007/049 (Test / Calibration) - February 4, 1977, January 7, 1977, December 2, 1976.
(2) Reactor Low Level Scram and Low-Low Level Isolation Test and Calibration 0004/21 - January 26, 1977 December 21, 1976.
(3) Main Steam Line Radiation Monitor Test and Calibration 0015b/0024 - February 3, 1977, November 4, 1976.
i (4) Drywell High Pressure Test and Calibration Procedure, Scram and Group II Isolation 003/0020 - February 14, 1977. January 17, 1977.
(5) Reactor Low-Low Water Level ECCS Initiating Instruments Test and Calibration Procedure 0027/0028 - January 27, 1977, December 22, 1976.
(6) Automatic Pressure Relief System Low Pressure Core Cooling Pumps Discharge Pressure Interlock Instruments Test and Calibration Procedure 0037/0038 - February 2, 1977,
-
January 6, 1977.
(7) Shutdown Margin Demonstration Test 0073 - August 8, 1976.
'
(8) Control Rod Drive Scram Insertion Time Test 0081 -
-
February 23, 1977, November 11, 1976.
(9)
Standby Liquid Control System Monthly System Surveillance Test 0085 - February 9, 1977, January 20, 1977.
.
9-(
.
,e6
.
--..- -___ _.
-
-
Cs
.....
.
(10) Core Spray System Testa:
Flow Rate Test 0094, Fump opera-(
bility Test 0095 - January 30, 1977, January 2, 1977.
(11) Ri!R Pump Full Flow Test 0102 - January 2, 1977, October 3, 1976.
(12) AFR System Valve Operability Test 0112 - August 10, 1976.
(13) Reactor Coolant I-131 Dose Equivalent Activity Surveil-lance Record 0122 - February 22, 1977, February 23, 1977, February 21, 1977 February 17, 1977.
(14) Reactor Coolant Chloride / Conductivity Surveillance Record
,
0125 - February 24, 1977, February 23, 1977, February 21, 1977. February 17, 1977.
(15) Reactor Coolant Isotopic Analysis Surveillance Record 0123 - February 18, 1977, January 21, 1977, December 16, 1976.
(16) Reactor Building to Suppression Chamber Vacuum Breaker Operability Check 0141 - February 7, 1977, November 8, 1976.
(17) Drywell - Suppression Chamber Monthly Vacuum Breaker Check 0143 - February 8, 1977, January 11, 1977.
,
(18) Main Steam Line Isolation Valve Closure Timing Test 0159 -
February 23, 1977, November 21, 1976, August 29, 1976.
(19) Safety / Relief Valve Bellows Monitor Check Test 0131 -
January 12, 1977, October 13, 1976, August 7, 1976.
(20) Standby Diesel Generator Start and Load Test 0187 -
February 21, 1977, January 24, 1977.
(21) 125 VDC Battery Operability Check; weekly check 0194, Quarterly Check 0196 - February 25, 1977, October 19, 1976.
(22) Recirculation Syster Cross Tie Valve Interlock Checks Test 0206 - February 14, 1977, January 17, 1977, December 15, 1976.
.
The inspector noted during review of startup and scram packages that there were minor administrative errors (i.e., not dating every entry in the startup check list; nonspecific entries for varicus flowrates in the scram reports).
The licensee indicated these oversights would be corrected. The inspector had no further concerns.
[
- 10 -
("'
.
,
I