ML18086B525
| ML18086B525 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/24/1982 |
| From: | Clemons P, Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18086B523 | List: |
| References | |
| 50-311-81-23, NUDOCS 8206170111 | |
| Download: ML18086B525 (7) | |
See also: IR 05000311/1981023
Text
Report No. 50-311/81-23
Docket No. 50-311
U.S. NUCLEAR REGULATORY COMMISSION
Region I
License No. DPR-75
Priority
Category _c_
Licensee:
Public Service Electric and Gas Company
80 Park Place
- Newark, New Jersey
07101
Facility Name:
Salem Nuclear Generating Station, Unit 2
Inspection At:
Hancocks Bridge, New Jersey
Inspection Conducted:
September 2-3, 1981
Inspector:
Approved By:
e~
P. Clemons, Radiation Specialist
E.c¥.~£.~es
Radiation
Protection Section, Technical Programs Branch
_sk~/'1f~
date ?igned
6 /diha2
date signed
Inspection Summary:
Inspection on September 2-3, 1981 (Report No. 50-311/81-23)
Areas Inspected:
Routine, unannounced safety inspection by one NRC region based
inspector of three startup tests required by Section 13.4 of the Final Safety
Analysis Report.
The tests required at various power levels were Chemistry and
Radiochemistry, Radiation Monitoring and Shielding Evaluation, and Effluent
Monitoring Systems.
This inspection was concerned with tests performed at
70%, 75% and 100% power to verify that the required startup tests were
satisfactorily completed (test results at other power levels were examined
during prior inspections).
The inspector also reviewed a moisture carryover
test that was associated with steam generator blowdown on August 29, 1981.
The
inspection involved 11 inspector hours onsite by one NRC region based inspector.
Results:
One violation was identified regarding moisture carryover testing -
(steam generator blowdown monitors were inoperable and blowdown flow was not
diverted to the waste management system - paragraph 2) .
8206170111 820526
PDR ADOCK 05000311
G
. PDR
DETAILS
1.
Persons Contacted
Mr. s.
Mr. E.
Mr. p.
- Mr. H.
Mr. J.
Mr. J.
- Mr. R.
NRC
Forker, Administrative Staff Engineering Technician
Keating, Associate Engineer
Mergen, Technical Supervisor, Chemistry*
Midura, Plant Manager
O'Connor, Senior Performance Superv~sor-Radiation Protection
Ronafalvy, Senior I and C Supervisor
Swetnam, Radiation Protection Engineer
- Mr. L. Norrholm, Senior Resident Inspector
- Denotes those present at the exit interview.
2.
Steam Generator Blowdown Monitors
On August 29, 1981, the licensee conducted a moisture carryover test
using Na-24.
As a result of a condenser tube leak, steam generator
blowdown was initiated to restore steam generator chemistry.
The blowdown,
containing radioactive Na-24, went to the non-radwaste basin, and was
released with the blowdown radiation monitors serving as the release
monitors.
The steam generators contained 0.5 curies of Na-24 during the
blowdown.
No Technical Specification or 10 CFR 20 Appendix B limits
were exceeded as a r~sult of the release.
The inspector reviewed the approved startup procedure, "Steam Generator
Moisture Carryover Test,
11 SUP No. 82.7, dated February 14, 1979.
The
inspector noted that Item 10.2.23 of SUP No. 82.7, states, "Raise the
warning setpoint on steam generator blowdown radiation monitors."
The
inspector asked a licensee representative the basis for raising the alarm
setpoint on the monitors, and was told that Reactor Engineering Work
Order No. 931891 was the document authorizing the change. The inspector
reviewed Work Order No. 931891, and noted that the alarm setpoint for the
steam generator blowdown monitors had been raised to 9.99x 10 9 counts per
minute (CPM), the maximum range of the monitors which resulted in de-
activation of the system isolation features.
The setpoints remained at
the maximum range for 51 hours5.902778e-4 days <br />0.0142 hours <br />8.43254e-5 weeks <br />1.94055e-5 months <br />; from 6:00 p.m. on August 28, 1981 to 9:00
p.m. on August 30, 1981.
The inspector reviewed Procedure No. 2PD-4.2.029, "Channel Functional
Test-2Rl9A Steam Generator Process Monitor,
11 and noted that the specified
setpoint for the warning signal was 5.4 x 10 3 CPM, and the setpoint for
the alarm signal was 2.6 x 10 4 CPM.
Technical Specification 2.3.2.g states, "the radioactivity in steam
generator blowdown shall be contin~ously monitored and recorded.
Whenever
these monitors are inoperable, the blowdown .flow shall be diverted to the
waste management system and the direct release to the environment terminated."
\\'
DETAILS
1.
Persons Contacted
2.
Mr. s.
Mr. E.
Mr. p.
- Mr. H.
Mr. J.
Mr. J.
- Mr. R.
NRC
Forker, Administrative Staff Engineering Technician
Keating, Associate Engineer
Mergen, Technical Supervisor, Chemistry*
Midura, Plant Manager
O'Connor, Senior Performance Superv~sor-Radiation Protection
Ronafalvy, Senior I and C Supervisor
Swetnam, Radiation Protection Engineer
- Mr. L. Norrholm, Senior Resident Inspector
- Denotes those present at the exit interview.
Steam Generator Blowdown Monitors
On August 29, 1981, the licensee conducted a moisture carryover test
using Na-24.
As a result of a condenser tube leak, steam generator
blowdown was initiated to restore steam generator chemistry.
The blowdown,
containing radioactive Na-24, went to the non-radwaste basin, and was
released with the blowdown radiation monitors serving as the release
monitors.
The steam generators contained 0.5 curies of Na-24 during the
blowdown.
No Technical Specification or 10 CFR 20 Appendix B limits
were exceeded as a r~sult of the release.
The inspector reviewed the approved startup procedure, "Steam Generator
Moisture Carryover Test,
11 SUP No. 82.7, dated February 14, 1979.
The
inspector noted that Item 10.2.23 of SUP No. 82.7, states, "Raise the
warning setpoint on steam generator blowdown radiation monitors. 11
The
inspector asked a licensee representative the basis for raising the alarm
setpoint on the monitors, and was told that Reactor Engineering Work
Order No. 931891 was the document authorizing the change. The inspector
reviewed Work Order No. 931891, and noted that the alarm setpoint for the
steam generator blowdown monitors had been raised to 9.99x 10 9 counts per
minute (CPM), the maximum range of the monitors which resulted in de-
activation of the system isolation features.
The setpoints remained at
the maximum range for 51 hours5.902778e-4 days <br />0.0142 hours <br />8.43254e-5 weeks <br />1.94055e-5 months <br />; from 6:00 p.m. on August 28, 1981 to 9:00
p.m. on August 30, 1981.
The inspector reviewed Procedure No. 2PD-4.2.029, "Channel Functional
Test-2R19A Steam Generator Process Monitor," and noted that the specified
setpoint for the warning signal was 5.4 x 10 3 CPM, and the setpoint for
the alarm signal was 2.6 x 10 4 CPM.
Technical Specification 2.3.2.g states, "the radioactivity in steam
generator blowdown shall be contin~ously monitored and recorded.
Whenever
these monitors are inoperable, the blowdown .flow shall be diverted to the
waste management system and the direct release to the environment terminated."
3.
A.
B.
c.
L
3
The Final Safety Analysis Report (FSAR), Chapter 11.3,
11Steam Generator
Blowdown Processing System,
11 indicates that if a steam generator should
develop a primary to secondary leak while the blowdown system is discharging,
a high radiation signal from any of the blowdown sample radiation monitors
will close the isolation valves and terminate the blowdown.
The inspector determined that when the alarm set points on the blowdown
sample radiation monitors were positioned at the maximum range of the
instrument, the automatic isolation feature discussed in the FSAR became
Consequently, the potential for inadvertent release of
radioactive material to the environment in excess of the Technical Spec-
ification limit was created.
Failure to maintain the capability of
~utomatically isolating a steam generator blowdown discharge on a high
radiation signal coristitutes a violation of Technical Specification 2.3.1.g (81-23-01).
Startup Test Program
Section 13.1 of the FSAR states,
11A carefully conceived and executed
startup testing program, under the control, responsibility, and authority
of PSE&G, will be implemented to accomplish a safe, orderly, and com-
prehensive startup. This program will demonstrate that the plant operates
satisfactorily and presents no danger to the health and safety of the
public.
11
Table 13.4 of the FSAR includes the following tests that were required to
be performed at various power levels:
Test
Chemistry
and Radio-
chemistry
Tests
Radiation
Monitoring
and Shielding
Evaluation
Effluent
Monitoring
Systems
Condition
Specific analyses
at low power and
30%, 50%, 75%
and 100% power.
Low power and
during power
escalation at
30%, 70%, 100%.
As early in power
operation as
possible and
repeated after
operation at 30%,
50%, 75%, and
100% power.
Objectives
To demonstrate
ability to control
water qua 1 ity.
To measure and
record radiation
1eve1 s in
accessible areas
of the plant.
To verify
calibration of
effluent monitors
by lab analysis
of radioactive
waste samples.
Comments
Ability to
control water
qua 1 ity verified
at each power
1eve1 .
Radiation
levels are
verified to
be within
the shielding
design
criteria.
Verification of
calibration of
plant effluent
monitors.
4
A.
Chemistry and Radiochemistry Tests
The inspector reviewed Startup Procedure No. 81.15,
11Chemistry and
Radiochemistry Tests,
11 to determine the acceptance criteria. The
acceptance criteria specified by Procedure No. 81.15 were as follows:
11Acceptance Criteria
Table I lists the analysis to be performed Qt the various power
levels on the reactor coolant system and the limits for acceptance.
- Table II lists the analysis to be performed at the various power
levels on the steam generator blowdown and the limits for acceptance.
11
Table I
Reactor Coolant Specificatio~s
Analysis
Acceptance Criteria
pH
4.2 to 10.5
< 0.15 ppm
Fluoride
< 0.15 ppm
0.7 to 2.2 ppm
Dissolved Oxygen
< 0.10 ppm
11 Dose Equivalent I-131
< 1.0 uCi/gram
Gross Beta-gamma
N/A
Table II
Steam Generator Specifications
Analysis
Procedure Number
Acceptance Criteria
Dose Equivalent I-131
PD-3.3.003
< 0.10 uCi/gram
Gross Beta-gamma
PD-3.3.001
N/A
11
The inspector reviewed the test data for the tests performed on
August 3, 1981, at 75% power, and August 19, 1981, at 100% power, for
the reactor coolant and the four steam generators associated with
Unit 2.
The data indicated that all of the required analyses had
been performed and all were within the acceptance criteria.
No violations were identified.
5
B.
Radiation Monitoring and Shielding Evaluation
The inspector reviewed Startup Procedure No. 81.13,
11 Radiation
Monitoring and Shielding Evaluation,
11 to determine the acceptance
criteria.
The acceptance criteria specified by Procedure No. 81.13
were as follows:
Acceptance Criteria
11 Dose rates shall be considered acceptable if the measurements taken
are within the levels designated by the Radiation Zone in which each
dose poit1t is located.
Radiation Zone
The radiation levels acceptable for each zone are as follows:
Zone
Occupancy
Dose Rate (mR/Hr)
Zone 1
Unlimited
<.25
Zone 2
Normal-continuous
.25-2.5
Zone 3
Periodic
2.5-15
Zone 4
Contro 11 ed 15-100
Zone 5
Controlled
>100
11
The inspector reviewed the results of radiation surveys made on
August 4, 1981, at 70% power, and on August 19-20, 1981, at 100%
power.
The data indicated that all survey results were within the
acceptance criteria.
No violations were identified.
C.
Effluent Monitoring System Test
The inspector reviewed Startup Procedure No. 81.14,
11 Effluent Monitoring
System Test, 11 to determine the acceptance criteria.
The acceptance
criteria specified by Procedure No. 81.14 were as follows:
Acceptance Criteria
11The actual response of the monitor compared to the calculated
response expected from radio-analysis in the laboratory must be
within a factor of +2 to -0.5.
11
The inspector reviewed the effluent monitor data for eight monitors
for testing performed on August 6, 1981, at 75% power, and on August
6
18, 1981, at 100% power, to determine if the monitors met the acceptance
criteria.
The data indicated that the instruments met the acceptance
criteria.
No violations were identified.
4.
Exit Interview
The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on September 3, 1981.
The inspector
summarized the purpose, the scope, and the findings of the inspection .