IR 05000412/1987028
| ML20214E401 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/12/1987 |
| From: | Mark Miller, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20214E385 | List: |
| References | |
| 50-412-87-28, NUDOCS 8705220070 | |
| Download: ML20214E401 (6) | |
Text
T
.
.
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-412/87-28 Docket No.
50-412 License No.
CPPR-105 Category B
Licensee: Duquesne Light Company Post Office Box 4 Shippingport, Pennsylvania 15077 Facility Name: Beaver Valley Power Station, Unit 2 Inspection At:
Shippingport, Pennsylvania Inspection Conducted: April 6-10, 1987 Inspectors-Td*
J6
M. T. M111er Sent r Radiation Specialist
/ d&te j
Approved by:
2.
' e xce 6[// [<f h
.
W. J. P4tciak, Chief, Effluents Radiation
/ ddte Protection Section Inspection Summary:
Inspection on April 6-10, 1987 (Report No. 50-412/87-28)
Areas Inspected: Routine, announced safety inspection of the licensee's preoperational test program with regard to effluent controls and radioactive waste systems. One regionally based inspector was onsite for this inspection.
Results: No violations were identified.
The pre-operational test program for the radioactive waste systems had begun and are expected to be completed by the projected fuel load date.
0705220070 870512 PDR ADOCK 05000412 O
-
l
.
.
.
Details t-
' 1. 0 Personnel Contacted Licensee Personnel l
- T. Nocnan,. Assistant Plant Manager
- N. Daugherty, Director, System Testing (
- J. Godleski, Senior. Test Engineer l
- J. Kosmal, Manager, Radiological Controls
!
- R. Martin, Manager, Regulatory Affairs
- D. Girwood, Director, Radiological Operations
- D. Hunkele, Director, QA Operations
- V. Linnenbam, Director, Plant Chemistry l
- R. Vento, Cirector, Radiological Engineering
'
- T. Zyra', Director, Site T&PP
- W. Wirth, Director, Effluent Control / Environmental Monitoring
- G. Wargo, Assistant Director, Quality Control
- J. Johns, Supervisor QA Surveillance R. Berner, Supervisor Test Engineer T. Pietrangelo, Senor Test Engineer
- S. Palian, Senior Chemist
- R. Rabenau, Lead Compliance Engineer
- J. Wenkhous, Senior Health Physics. Specialist
- K. Winter, Senior Health Physics Specialist
- D. Evans, Chemistry Trend and Analysis Coordinator-
- A. Lonnett, Health Physics Specialist K. Maloney, Test Engineer S. Moore, Test Engineer 1.2 NRC Personnel l
- J. Beall, Senior Resident Inspector l
- L. Prividy, Resident Inspector i
- D. Florek, Lead Reactor Engineer
- H. Van Kessel, Reactor Engineer
- H Zibulsky, Chemist
- Denotes attendance at Exit meeting on April 10, 1987.
2.0 Purpose The purpose of this peroperational inspection was to determine if the licensee's Chemistry and Radioactive Effluent Control Programs comply with the regulatory requirements and commitments made in the Final Safety
.
Analysis Report (FSAR) and draft Technical Specifications with respect to
'
radioactive effluent sampling / monitoring and analysis procedures and the l
initial test program for the radioactive waste systems.
I
-
-
o -
.
3.0 Effluent Control Procedures The licensee had completed drafting site specific manuals for both chemistry and radiological controls, which share the effluent control responsibilities.
Generally, approximately fifty percent of the
.
procedures had been finalized. Surveillance procedures for the process monitors had not been completed. The licensee had submitted an Offsite Dose Calculation Manual and Process Control Program. The licensee also requested on March 5, 1987 a schedular exemption from the requirements of RM-50-2 regarding combined site effluents to remain in effect six months after the issuance of a full power license for Unit 2.
Approval by the NRC of these documents and exemption request is expected prior to core load.
The adequacy of the licensee effluent control procedures were reviewed against Regulatory Guide 1.33, the Beaver Valley Unit I and draft Beaver Valley Unit 2 Technical Specifications, and the Unit 2 Final Safety Analysis Report Chapter 11. Discussions were held with cognizant chemistry and radcon personnel.
Selectad procedures were also reviewed, including:
6.1, " Liquid Waste Holdup Tank Sampling," Issue 2 (in final review)
6.4, " Unit 2 Gaseous Waste Tank 3ampling", Issue 2 (in final review)
6.5, " Radioactive Waste Discharge Authorization at Unit.1 & Unit 2, Hand Calculation Method," Issue 4 6.6, " Batch Radioactive Waste Discharge Authorization - Gas, Hand Calculation Method, " Issue 3, Revision 6 6.10 " Monthly Release Permit for the Continuous Ventilation Pathways, Hand Calculation Method" Issue 1, Revision 5 6.12A, " Qualification of Unplanned Releases", Issue 2 (in final review)
Radeon Manual, Chapter 4 l
RIP 2.2 " Effluent Monitors," Unit 1 i
RIP 2.21 " Effluent Monitors," Unit 2 Chemistry Manual Unit 2 Chapter 3, " Sampling and Testing", (draft)
Chapter SPI, " Radiochemical Procedures, Bench Analytical Procedures", (draft)
Chapter 5, " Primary to Secondary Leakage", (draft).
-
-
-
- -
.
- - - - - -.
--
-
_ - _ _ _ _ _ - _ _
..
Within the scope of this review, no violations were identified.
However two FSAR documentation changes would be required to reflect the intended monitoring capabilities. These required changes were:
FSAR Chapter 11.5.3 presently states that main steam line monitoring will include noble gas, particulate and iodine sampling during accident conditions. The licensee intends to provide noble gas monitoring only.
- FSAR Chapter 11.2.2 states that grab sa.nples will-be collected weekly from the turbine building drains and sumps.
The licensee intends to perform sampling of the continuous liquid pathway contingent upon exceeding 10' uCi/ml in the secondary coolant. The inspector requested that the basis for this threshold value be documented to ensure a maximum permissible concentration (MPC) would not be exceeded in the effluent pathway.
The licensee stated that these FSAR changes would be submitted and the basis for not performing weekly sampling of the continuous liquid pathway when 10* uCi/ml is not exceeded would be documented. These actions will _
be reviewed during a subsequent inspection.
The inspector also requested that Technical Specification 3.3.9b and 3.3.3.10b be deleted or clarified. Currently, these specifications would allow a liquid or gaseous discharge when the monitor would be inoperable.
Provisions to take two independent grab samples were not specifically required. The inoperable monitor conditions, should be further delineated either in the Technical Specifications or a required implementing pro-cedure, e.g., RIP 2.21, DRMS Effluent Monitoring Subsystem. The licensee stated that this concern would be reviewed to ensure acceptable effluent monitoring.
4.0 Preoperational and System Operability Verification Testing The inspector examined preoperation and safety testing of the following systems:
.
Liquid Radioactive Waste System
Gaseous Radioactive Waste System
Process Monitoring System
Primary Sampling System The review was with respect to criteria contained in the following:
Final Safety Analysis Report, Chapter 14
Regulatory Guide 1.68, Revision 0
Beaver Valley Station Unit 2, Technical Specification (draft).
I
-
-
-
-
-
.-.
-
,
.
,
The evaluation of the licensee's performance in this area was based on
review of documentation, observations by the inspector, and discussions with cognizant personnel. The review in this area examined, among other matters, the following:
Procedure test objectives and acceptance _ criteria l
Status of Testing Program
Review and evaluation of Test Change Notices.
,
Adherence.to test procedures
Adequacy of licensee review and resolution of test exceptions.
.
4.1 Liquid Radioactive Waste System
~
The inspector reviewed the test results for test procedure S0V-2.17.01, " Waste Drain Tank Pumps and Control Test," which was
<
'
initially completed on February 19, 1987.
The licensee demonstrated l
the ability to transfer from a BVPS-2 Waste Drain Tank to a BVPS-1 High Level Waste Drain Tank. The Joint Test Group recommended a test procedure change to include testing the system after adding a time delay to a low level pump trip. The completion of this retest was scheduled to be completed by April 17, 1987. The inspector determined that the commitments to demonstrate system operability were met in accordance with the FSAR, Initial Test Program.
4.2 Gaseous Radioactive Waste System
,
The inspector witnessed preliminary testing of the waste gas sweep
,
system to prepare the system for test' procedure SOV-2.19.01 " Waste
Gas Sweep System." The inspector was informed that the major portions of the gaseous waste system would be tested by SOV-2.19.02
which was scheduled to be completed by April 16, 1987. Howaver, a major revision to the test procedure was initiated on April 9,1987.
Testing of the gaseous waste systems is now
.
scheduled for April 20-30, 1987, to be completed prior to fuel load.
4.3 Process Monitoring System The licensee installed General Atomics (GA) digital radiation
monitoring system (DRMS) skids throughout' the plant. The licensee had not issued the test section of test procedure PO-2.43.01, which would functionally test the process monitors, at the time of this
'
inspection. The inspector was also informed that the licensee evaluated the process monitoring system and determined that only
!
three monitors would be required by core load. The licensee
'
determined that the fuel pit bridge (2RMF-R 202) and containment purge monitors (2HUR-RQ104A&B) would be needed for fuel load
.
,
conditions and would complete testing of those monitors prior to
'
core load. The licensee further stated that all the effluent monitors would most likely be tested by core load, but were not
,
)
.
- -
'
r
.
.
.
'
committed to complete this testing until prior to initial criticality. The inspector agreed with the licensee's evaluation because sufficient radioactive effluent releases would not occur with the fuel in the unirradiated state.
The inspector verified that the gas surge tank line monitor had been re-installed to properly be used as a line monitor. No other problems were identified.
4.4 Primary Sampling System The inspector was told that the primary sampling system had undergone major modifications to prevent sample clogging, to provide a pressurized sample and to address ALARA concerns. A retest to SOV-2.14A.01 " Primary Sampling System Test" is now required to demonstrate primary sampling capabilities at the sample panel. This retest will be completed prior to core load.
5.0 Exit Interview The inspector met with the licensee's representatives (denoted in paragraph 1) at the conclusion of the inspection on April 10, 1987.
The inspector summarized the purpose and scope of the inspection and identified findings as described in this report.
At no time during this inspection was written material provided to the licensee by the inspector.
l
,
.