IR 05000410/1986035
| ML17055C212 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/08/1986 |
| From: | Kottan J, Pasciak W, Rabatin K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17055C211 | List: |
| References | |
| 50-410-86-35, NUDOCS 8608200166 | |
| Download: ML17055C212 (18) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-410/86-35 Oocket No.
50-410 License No.
CPPR-112 Category
Licensee:
Nia ara Mohawk Power Cor oration 300 Erie Boulevard West S racuse New York 13202 Facility Name:
Nine Mile Point Unit 2 Inspection At:
Scriba New York d
d:
~J1
1 986 Inspectors:
J.J.
Kotta
, Radiation Laboratory Specialist ate
~.L. Rabati, Ra tion Specialist ate Approved by:
(
W.J.
Pa ci k, Chief, Effluents Radiation Prote t'
Section d te Ins ection Summar:
Ins ection conducted on Jul 7-11 1986 Ins ection Re ort No. 50-410/86-35
~Ad:
R i, di i
f liquid radioactive waste area, and gaseous radioactive waste area.
The inspection covered:
status of previously identified items, process and effluent radiation monitors, pre-operational testing, procedures, and capability test samples.
Results:
No violations or.deviations were identified.
'608200166 860814 PDR ADOCK 05000410 G
V e,
DETAILS Individuals Contacted Princi al Licensee Em lo ees
- T. Lee, Special Projects h
"S. Agarwal, Special Projects
"W. Hansen, Manager Nuclear QA, Operations
- M. Ray, Manager Special Projects
- J. McKenzie, Supervisor Quality Assurance
"J. Duell, Supervisor Radiation Protection and Chemistry
"L. Lagoe, Unit I 5 C Supervisor
~E.
Leach, Superintendent Chemistry/Radiation Mgt
- R. Abbott, Station Superintendent P. Wilde, QA J.
Doud, ISI 0. Henderson, Supervisor Radwaste Operations T. Perkins, Site Superintendent J.
Bunyon, Engineering G. Afflerbach, Startup and Testing
"A. Ross, Unit Supervisor Chemistry L. Dick, Engineer B. Bock, Assistant Unit Supervisor Chemistry L. Ringlespaugh, Test Coordinator Stone and Webster
- J. Drake, Jr. Startup/Test Special Projects Supervisor
"J. Gallagher, Site Licensing Engineer
- C. Terry, Project QA Manager S.
Cook, Special Projects T. Farrell, Assistant Superintendent of Engineering D. Kryszczynski, Test Engineer New York PSC P.
Eddy, Site Representative
- Denotes those present at the exit interview.
Status of Previousl Identified Items (Open) Follow-up Item (410/85-20-01):
Complete review of liquid radwaste pre-operational testing.
The pre-operational testing of the liquid rad-waste system has been completed.
The completed test package is currently undergoing review and approval by the licensee.
This test package will be reviewed by the inspector when the licensee's review and approval is complet (Open) Follow-up Item (410/85-20-03):
Complete review of HVAC,- gaseous waste system testing.
Some pre-operational tests in this area have been performed.
However, several tests have yet to be performed.
(Open) Follow-up Item (410/85-32-05):
Review GEMS testing.
During this inspection the pre-operational testing of the GEMS system was in progress.
The test results will be reviewed by the inspector at a later date.
See Section 3.
(Open) Follow-up Item (410/85-32-06):
Review calibration of ORMS.
The ORMS calibration and pre-operational testing was in progress during this inspection.
The calibration and test results will be reviewed during a
subsequent inspection.
See Section 3.
(Open) Follow-up Item (410/86-17-01):
Calibration of counting equipment.
The licensee's counting room gamma spectrometers have been calibrated.
Simulated samples were submitted to the licensee by the inspector for analysis.
See Section 6.
However, testing of the GEMS system is not complete, and the inspector was unable to submit sources for analysis on the GEMS system.
Therefore, this item remains open.
(Open) Follow-up Item (410/86-17-02):
Review and approval of procedures.
Many of the licensee's chemistry and effluent measurement and control procedures are still in draft form.
In addition effluent surveillance procedures will require updating in order to implement the requirements of the Technical Specifications using the Offsite Dose Calculation Manual, methodology.
(Open)
Follow-up Item (410/86-17-03):
Laboratory QA program.
The lic-ensee has not yet finalized the Unit 2 laboratory gA program.
The proce-dure to implement this program is still under development.
Process and Efflue t Radiation Monitors The inspector toured selected portions of the facility and examined the gaseous effluent radiation monitors (GEMS) for both the main stack and the reactor building/radwaste building vent.
During this inspection the licensee was performing the GEMS pre-operational test, N2-POT-80A-2.
The inspector witnessed partial performance of this test.
Testing was still in progress at the conclusion of the inspection.
Because of the GEMS testing the inspector was unable to submit the NRC simulated radioactive charcoal cartridges and particulate filters to the licensee for analysis on the GEMS system.
This will be done during a subsequent inspection.
Preliminary and pre-operational testing of the digital radiation monitor-ing system (ORMS), which includes process and liquid effluent'radiation monitors, was also underway during this inspection.
The preliminary testing includes source calibration of the radiation monitors.
The in-spector attempted to witness the source calibration of the liquid radwaste
4e v>
effluent radiation monitor, but the licensee experienced electronic pro-blems with the monitor and was unable to perform the calibration.
The calibration data as well as the pre-operational test data will be reviewed during a subsequent inspection.
Pre-0 erational Testin The inspector reviewed the licensee's pre-operational tests results for tests involving chemistry and gaseous and liquid radioactive waste.
The reviews were conducted with respect to Final Safety Analysis Report
<j'SAR)'hapter 14, Initial Test Program, and NRC Regulatory Guide 1.68, Initial Test Programs for Water Cooled Nuclear Power Plants.
The following specific tests were reviewed:
N2-POT-17-1, Turbine Building Sampling System; N2-POT-17-2, Reactor Plant Sampling System; N2-POT-17-3, Radwaste Plant Sampling System; N2-POT-61-2, Standby Gas Treatment System; and N2-POT-80B, Main Steam Line Radiation Monitoring.
The licensee is evaluating, reviewing, and approving test data and results as required by the licensee's procedures.
Test exceptions and deficiencies were documen-ted and resolved.
I In addition to reviewing the above completed test results, the inspector toured the facility and examined the reactor plant, turbine plant and liquid radioactive waste sampling panels.
This review was conducted with respect to FSAR chapters 9 and ll.
The sample -collection points were easily accessible and properly ventilated.
The inspector also reviewed licensee data listing sample line volumes for the radwaste system, reactor building system, and turbine building system sampling stations.
The licensee stated that these volumes would be incorporated into the various sampling procedures to ensure that sample lines would be adequately purged and representative samples taken.
Procedures The inspector reviewed the following Unit 2 draft procedures:
N2-CSP-4, Liquid Radioactive Waste Chemistry Surveillance at Unit 2 N2-CSP-7, Gaseous Radioactive Waste Chemistry Surveillance at'nit
N2-CSP-5, Circulating and Service Water Chemical Surveillance at Unit 2 N2-CSP-.l, Reactor Chemistry Surveillance at Unit 2 The reviews were conducted with respect to the licensee's proposed Tech-nical Specifications and Offsite Dose Calculation Manual.
Technical Specification limiting conditions for operation action statements for the areas of, plant chemistry and radiochemistry and effluent measurement and control were incorporated into the above procedures with the exception of the following two items.
The two items are sections 3'.7. 10 and 3.4.3. 1 of the Technical Specifications; radioactive liquid effluent monitoring
instrumentation and reactor coolant leakage detection systems respect-ively.
The licensee stated these limiting conditions for operation action sta'tements would be incorporated into procedures after the Technical Specifications were finalized.
The inspector stated that the inclusion of the limiting condition for operation action statements into procedures would be reviewed during a subsequent inspection (86-35-01).
Also>differences currently exist between the draft Offsite Dose Calcul-ation Manual methodology and the methodology in the current version of the draft procedures.
Again, the licensee was aware of these differences and stated that the appropriate procedures would be revised after the Offsite Dose Calculation Manual was approved.
6.
Ca abi lit Test Sam les (
Test samples were submitted to the licensee in order to evaluate the licensee's capability to measure radioactivity in effluents.
The test samples duplicated the types of samples and nuclides that the licensee would encounter during operation.
The test samples were analyzed by the licensee using the licensee's normal methods and equipment.
The results'of the test samples measurement comparison indicated that all of the measurements were in agreement under the criteria used for inter-comparison of results.
(See Attachment 1.)
The intercomparison data is lised in Table 1.
7.
Exit Interview The inspector met with the licensee representatives denoted in Section
at the conclusion of the inspection on July ll, 1986.
The inspector summarized the purpose, scope and findings of the inspectio TABLE
NI E MILE POI T
U IT 2 CAPABILITY TEST RESULTS SAMPLE ISOTOPE RC ALUE RESULTS I
TOTAL MICROCURI LICENSEE ALUE COMPARISON Charcoal Cartridge Ge-5 Detector
cm shel f Charcoal Cartridge Ge-5 Detector contact Particulate Filter Ge-5 Detector Contact Cd-109 Co-57 Ce-139 Sn-113 Cs-137 Co-60 Y-88 Cd-109 Co-57 Ce-139 Sn-113 Cs-137 Co-60 Y-88 Cd-109 Co-57 Ce-139 Sn-113 Cs-137 Co-60 Y-88 (2.37 R 0.11)
(4.0 i 0.2)
E-2 7.9 2 0.4)
E-2 1.72 i 0.08)
E-1 1.02 R 0.04)
E-1 1.06 i 0.05)
E-1 2.66 i 0.12)
E"1 (2.37 i 0.11)
4.0 k 0.2)
E-2 (7.9 2 0.4)
E-2 1.72 2 0.08)
E-1 (1.02 + 0 ~ 04)
E-1 1. 06 + 0. 05)
E-1 (2.66
+ 0.12)
E-1 (2.22 + 0 ~ 11)
(3 ~ 8 2 0.2)
E-2 (7.4 R 0.3)
E-2 (1.61
+ 0.07)
E-1 9.5 + 0.4)
E-2 9.9
+ 0.5)
E-2 2 48 + 0 11)
E-1 (7.3 2 0.5) E-2 (1.80
+ 0.16)
E-1 (9.6 i 0.4)
E-2 (1 ~ 02 2 0.04)
E-1 2.4 2 0.2)
E-1 (1.97 R 0.10)
(3.66 R 0.12)
E-2 (6.4 i 0..3)
E-2 (1.45
+ 0.07)
E-1 (9.1
+ 0.3)
E-2 (9.3 2 0 ~ 3) E-2 (2.51 R 0.13)
E-1 (2.45
+ 0.12)
4.19
+ 0.14)
E-2 7.4 E 0.3)
E-2 E-1 E-1 E" 1 E-1 1.72 4 0.08)
1.02 i 0.03)
(1.06 i 0.03)
(2.63 2 0.14)
(2.23 R 0.11)
(4.01 R 0.15)
E-2 Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Particulate Filter Ge-5 Detector
cm shelf Cd-109 Co-57 Ce-139 Sn-113 Cs-137 Co-60 Y-88 (2.22 + 0.11)
(3.8 + 0.2)
E-2 (7.4 i 0.3)
E-2 (1.61
+ 0.07)
E-1 (9.5 + 0.4)
E-2 (9.9 + 0.5)
E-2 (2.48 i 0.11)
E-1 (2.56 i 0.13)
(4.4 + 0.2)
E-2 (8.4 2 0.5)
E-2 (1.94 + 0.16)
E-1 (1.06
+ 0.04)
E-1 (1.17 R 0.04)
E-1 (2.8 2 0.2)
E-1 Agreement Ag reement Agreement Agreement Agreement Agreement Agreement Charcoal Cartridge Ge-4 Detector
cm shelf Cd-109 Co-57 Ce-139 Sn-113 Cs-137 Co-60 Y-88 2.37 k 0.11)
4.0
+ 0.2)
E-2 7.9 2 0.4)
E-2 (1.72
+ 0.08)
E-1 (1.02 2 0.04)
E"1 (1.06 2 0.05)
E-1 (2.66 2 0.12)
E" 1 (2.28 2 0.12)
( LLD (7 '
2 0.5)
E"2 (1
~ 59 2 0.14)
E-1 (9.4 2 0.4)
E-2 (1.01 2 0.04)
E-1 LLD Agreement No Comparison Ag reement Ag reement Agreement Agreement No Comparison
TABLE
NINE MILE POINT U IT 2 CAPABILITY TEST RESULTS SAMPL ISOTOPE LICENSEE ALU NRC VALUE RESULTS I
TOTAL MICROCURIES COMPARISO Charcoal Cartridge Ge-4 Detector Contact Particulate Filter Ge-4 Detector Contact Particulate Filter Ge-Detector
cm shelf Cd-109 Co-57 Ce-139 Sn-113 Cs-137 Co-60 Y-88 Cd-109 Co-57 Ce-139 Sn-113 Cs-137 Co-60 Y-88 Cd-109 Co-57 Ce-139 Sn-113 Cs-137 Co-60 Y-88 (2.37 2 0.11)
(4.0 R 0.2)
E-2 (7.9 i 0.4)
E-2 (1.72
+ 0.08)
E-1 1.02
+ 0.04)
E-1 1.06
+ 0.05)
E-1 (2.06 R 0.12)
E-1 (2.22 i 0.11)
(3.8 + 0.2)
E-2 (7.4 2 0.3)
E-2 (1.61 2 0.07)
E-1 (9.5 i 0.4)
E-2 (9.9 + 0.5)
E-2 (2.48 2 0.11)
E"1 (2.22 2 0.11)
(3.8 f 0.2)
E"2 7.4 i 0.3)
E-2 1.61 2 0.07)
E-1 9.5 2 0.4)
E"2 (9.9 + 0.5)
E-2 (2.48
+ 0.11)
E-1 (2.00 2 0.10)
3.71 2 0.12)
E-2 6.7 2 0.3)
E-2 1.47 + 0.06)
E-1 9.2 + 0.3)
E-2 9.4 2 0.3)
E-2 2. 37 2 0. 13)
E-1 (2.55 2 0.12)
(4.68 i 0.15)
E-2 (8.3 + 0.3)
E-2 (1.86 R 0.08)
E-1 (1.13
+ 0.03)
E"1 (1.15 R 0.03)
E-1 (2.73 2 0.14 E-1 (2.50 2 0.12)
(4.26 2 0.14)
E"2 (8.3
+ 0.3)
E-2 (1.74 R 0.08)
E"1 1.06
+ 0.03)
E-1 1.09 + 0.03)
E-1 2.54 R 0.14)
E" 1 Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Ag reement Agreement Ag reement Agreement Agreement Agreement 4j g
~'
I E MILE TABLE
POINT U IT 2 CAPABILITY TEST RESULTS SAMPLE E
kev NRC VALUE LICE SEE ALUE COMPARISO OFFGAS VIAL Ge-4 Detector
cm shelf 186 242 295 351 609 1120 1238 1765 RESULTS 16049 344 a
851 i 42 1639 i 82 2062 2 103 682 2 34 271
+ 14 703 2 35 I
GAMMAS PER SECO 196 i 4.8%
334 i 3.2'%82 k 1.9%
1740 + 1.4%
2150
+ 1.6%
710 2 3.9%
307 2 7.1%
685 2 4.6%
Agreement Agreement Ag reement Agreement Ag reement Ag reement Agreement Ag reement OFFGAS VIAL Ge-4 Detector
cm shelf 186 242 295 351 609 1120 1238 1765 160 +
344 2 851
+
1639 i 2062 +
682 +
271 703 i
16
82 103
14
180 349 898 1760 2090 731 272 753 3.4%
2. 1%
1. 3%
1. O%%d 1.3%
2. 8%
5.4%
3 '%
Agreement Agreement Agreement Agreement Agreement Agreement Agreement Ag reement OFFGAS VIAL Ge-5 Detector
cm shelf 186 242 295 351 609 1120 1238 1765 16029 344 +-16 851
+ 42 1639 i 82 2062
+ 103 602 R 34 271 2 14 703
+ 35 198 357 841 1660
~ 9.8%
+ 5.5%
+ 3 2%
2110
+ 2.4%
5. 9%
7. 0%
727 +
< LLD 699 +
2 2 ~ 2%
Ag reement Agreement Agreement Agreement Agreement Agreement No Comparison Agreement OFFGAS VIAL Ge-5 Detector 3 cm shelf 186 242 295 351 609 1120 1238 1765 160 344 851 1639 2062 682 271 703
16
82 103
14
169 R 6.5%,
347
+ 3.6%
848 2 2.0%
1700
+ 1.4%
2180
+ 1.4%
720 2 3.9%
248 + 8.5%
722 i 4.4%
Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement
'
ATTACHMENT 1 CRITERIA FOR COMPARING ANALYTICALMEASUREMENTS This attachment provides criteria for comparing results of capability tests and verification measurements.
The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this program.
In these criteria, the judgement limits are variable in relation to the comparison of the NRC Reference Laboratory's value to its associated uncertainty.
As that ratio, referred to in this program as "Resolution",
increases the acceptability of a licensee's measurement should be more selective.
Conversely, poorer agreement must be considered acceptable as the resolution decreases.
Resolution Ratio For A reement
<3
8
51
)200
15
200.5 0.5 " 2.0 0.6 - 1.66 0.75 - 1.33 0.80 1.25 0.85 " 1.18 1 Resolution
= (NRC Reference Value/Reference Value Uncertainty)
~Ratio = (License Value/NRC Reference Value)
OFFICIAL RECORD COPY IR NMP2 86-35 0010
~ 0.0 07/28/86
~ ~