IR 05000293/1991010
| ML20024H645 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/17/1991 |
| From: | Bores R, Jang J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20024H644 | List: |
| References | |
| 50-293-91-10, NUDOCS 9106070225 | |
| Download: ML20024H645 (7) | |
Text
_
.
.
.
U.S. NUCLEAR REGULATORY COMMISSION REGION 1 Report No.
$0-293/91-10 Docket No.
50-293 License No.
DPR 35 Licensee:
Ikilen Edison Cornpany RFD #1 Rocky _ Hill Road Plymouth. Musachttsetts 02360 Facility Name:
Pilgrim Nuclear Power Station inspection At:
Plymouth Ma51achtlic11$
Inspection Conducted: May_6-10.1921
/
,
inspector:
. JWE
-
N#h U~ /[ -
Jaso6 C. Jang, Sr. Radiation Specialist date
[Section (ERPS),
Effluents Radiation Protection Facilities Radiological Safety and Safeguards llranch (FRS&Sil)
/
-
%_
Approved by:
M. \\1
/r" jv
_f-n
'l (
Jobert J. Bore (, Chief, ERPS, FRS&SB date
,f Division of Radiation Safety
/
and Safeguards in3pection Summary; Intocction on May 6-10.1901 (InspectioiLReport No.
50-203/91-10)
Areas inspected; Routine, announced inspection of the licensee's radiological liquid and gaseous etBuent control programs for operations including: management controls, effluent and process radiation monitor calibrations, and implementation of the above programs.
EcSu]13; Within the areas inspected, no violations were identiGed. The licensee implemented the above programs effectively.
$
.
Olf'6070h~fff'~f{03.,,
' 'i' God ll7.,
Pop, *
.
-
.
.
.
.
.
.
DETAILS
1.0 Infhyldttals Contacted
1.1 Lkensee Personnel
,
- R. Anderson, Vice President, Nuclear Operations
- J. Ikilefeville, Technical Section hianager (Acting)
- W. Crawford,1&C Division hianager
- N. Desmond, Compliance Division hianages i
- 11. Eldredge, Sr. QA Engineer, Surveillance
- C. Goddard, Radwaste/ Chemistry Section hianager (Acting)
- L. Loomis, Chemistry Division hianager (Acting)
- T. hicElhinney, Sr. Compliance Engineer
- H. Oheim, Regulatory Affairs hianager
- L. Schmeling, Radiation Control / Chemistry Pro;ess Department hianager
" Sejkora, Sr. Environmental Engineer
.
1.2 NRC Personnel
'J. hiacdonald, Sr. Resident Inspector
- A. Cerne, Resident inspector
- Denotes those individuals present at the exit interview on hiay 10,1991. Other licensee personnel were also contacted or interviewed during this inspection.
,
2.0'
Purpo.3c The purpose of this inspection was to review the licensee's ability to control and quantify radioactive liquids, gases, and particulates during normal and emergency operations through its radiological effluent control program.
3.0 hianagement Controls 3.1 Prokram Changes Since the pievious inspection of this area conducted in January 1990, the Senior Environmental Engineer was transferred from the Radiological Section to the Radwaste/ Chemistry Section. This individual had been responsible for administering programs to control radioactive liquid and gaseous effluents. The inspector reviewed this change and its effect on the prograin.
- As a result of the change, the Radwaste/ Chemistry Secoon, rather than the
_
__
_ _ _
.
.
..
..
.....
.
. - - - _ _ _ - _ _ _
_ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
.
.
Itadiological Section, now has the complete responsibility for the radioactive liquid and gaseous effluent control programs, and the radiological environmental monitoring program. The inspector determined that the change did not affect the implementation of the ef0uent control programst in fact, it appeared to enhance the noility t, conduct the ef0uents programs.
3.2 Audits The inspector reviewed the most recent QA audit (Audit No. 9106) Deficiency iteport No.1919. The Quality Assurance (QA) audit repo.t for Audit 91-06 was not yet issued as of the time of this inspection, however, the deficiency report (No.1919)
had been issued by the Q A Department. This denciency report contained two notable
-
audit findings in the effluents programs areas (See Section 4.2 of this inspection report for details). The inspector noted that the scope and technical depth of the audit findings renected a good assessment of the radioactive effluent control program. The Chemistry Department provided excellent, timely responses to these findings No violations were identified in this area.
3.3 Ikyjew of Semiannual Itadioactive Ef0uent Reoorts The inspector reviewed the semiannual radioactive ef0uent release reports for 1990, and determined that the licensee met the Technical Specl0 cation requirements. No anomalous measurements, omissions or trends were noted. No violations were identified.
4.0 RadicattiYc.Liguld and Gneous Pfnuent Controls 4.1 LigttiiEffluent Controls The inspector reviewed selected licensee's procedures and radioactive liquid efnuent release permits as part of the examination of the implementation of Section 3/4.8.A,
" Liquid Ef0uents Concentration", of the Technical Speci0 cations (TS) and of the Offsite Dose Calculation Manual (ODCM). The inspector noted that the lleensee met the requirements for sampling and analysis at the frequencies and lower limits of detection established in Table 4.8-1 of the TS. All reviewed release permits met TS requirements, llased on the above review, the inspector determined that the licensee implemented the radioactive liquid efnuent control programs effectively. No violations were identifie a
.
.
.
.
.
I
4.2 Gaigous Effluent Controls The inspector reviewed selected licensec's procedures and radioactive gaseous efnuent release records as part of the examination of the implementation of Section 3/4.8.D,
" Gaseous Ef0uent Dose Rate", of the Technical Specificationc (TS) and of the ODCM. The inspector noted that the licensee met the requirements for sampling and analysis at the frequencies and lower limits of detection established in Table 4.8 3 of the TS. All reviewed release permits met TS requirements.
4.2.1 Turbine Btillding Roof Vents During a previous NRC inspection (Inspection Report No. 50 293/9103) conducted on Fetnuary 25 March 1,1991, an inspector discussed with the licensee possible unmonitored radioactive gas releases through the turbine building vents (QA Audit Observation, QA Audit No. 90-33). The inspector also noted that this issue was reviewed by the QA Audit No. 9106. During this inspection, the inspector reviewed the aforementioned QA deficiency report (No.1919) and corrective actions taken by the Chemistry Department in regard to this issue. The inspector also toured the turbine building and observed the turbine building air sampling systems.
The turbine building exhaust system was initially designed such that the air in the immediate vicinity of the turbines and three (3) reactor feed pumps would be drawn downward into the condenser bay and then exhausted to the reactor building vent.
The radiation monitoring system was installed to monitor the rc;.uor building vent effluents. However, the licensee observed that the air from the lower areas of the turbine building and/or condenser bays exhausted to the turbine deck, from wl ch it could potentially be exhausted to the environment through one of nine (9) turbme building roof vents. The Dow rate of the each turbine building vent was about 35,000 cubic feet per minute (cfm). The licensee had since installed air sampling systems on two of the nine turbine building roof vents and treated collected samples as regular ef0uent samples.
On March 1,1991, the Chemistry Department identified iodine-131 (1 131) in the one-of two turbine building air sample charcoal cartridges [1131 activity: 3.lE-13 microCuries/cuole centimeter (uCi/cc)]. Charcoal cartridges collected on March 3, 1991 from both sampling systems identified 1-131 (2.8E-12 uCi/cc) and I 133 (6.5E-12 uCi/cc). The licensec detected lanthanum-140 (3.58E-13 uCi/ec) in air particulate samples. At this time reactor coolant iodine activity concentration increased by a factor of ten due to fuel failures.
.
.
...
.
-.
_
_
- _ - _ - _ _ _ _ _
.
.
.
.
.
5 The licensee's corrective actions included the installation of four additionil air sampling systems in order to better assess turbine building effluent releaset through the turbine building vents. In addition, Chemistry now coordinates with Operations to ensure that when the turbine building vents are operating, at least one of vents with an rir sampler is operating. The licensee stated that additional upgrades are planned for the turbine building air sampling systems.
The inspector also reviewed the iodine measurement results, as well as the line loss study conducted by the lleensee of the sampling system. The average activities and standard deviations of 1131 and 1-133 between March 1,1991 and May 4,1991 were (1.1+/ 0.6)E-12 uCi/cc and (3.1 +/-l.5)E-12 uCi/cc, respectively. The licensee conservatively estimated the total amount of iodine released through the turbine building vents and calculated the projected dose commitment to the public. The contribution of lodine release through the turbine building vents was about 0.1% of total release from the Pilgrim site.
11ased on the above review, the inspector determined the following.
o Chemistry's actions to monitor iodines and particulates released to the environment through the turbine building vents were excellent. The line loss assessment was good and there was little line loss in the air sampling system.
,
o There were minimum impacts on the environment and/or to the public health and safety as a result of this release pathway (0.1% of total release),
o The licensee has the capability to perform the necessary radiological dose assessment, as necessary.
The licensec has enhanced the capability to monitor radioactive gaseous o
releases through the turbine building vents.
4.2.2 In leakage ofthe Reactor 13uilding Vent Air Sampling System During the licensee's QA audit (Deficiency Report No.1919), a leak in the reactor building vent air sampling system was identified at a slip joint connection containing an "O" ring. A leaking sampling system could lead to inaccurate sampling volume and total effluent calculations.
To account for this leak, the Chemistry Department measured the leakage rate at different air How rates (0.80 to 2.05 cfm). The Dow rate of the air sampling system is normally set at about 1.3 cfm. The inspector reviewed the measurement technique
_
. _.,. -
_.
_
~_ _ _ _ _ _ _ _ _ _
_ _ _ _ _ _ _ _ _.---
- - _ _ _ - - _ _ - - - - - - _ _
_ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _.
.
.
.
,
and calculational method to determine the correction factor. The inspector determined that the technique and the calculation method were sound. The correction factor was 1.65 and the licensee applied this correction factor to calculate total radioactive gas releases through the reactor building vent. Since the main stack releases comprise most of the Pilgrim radioactive gaseous ef0uent releases (about 90% of total release),
the application of the correction factor to the reactor building vent efnuents resulted in offsite doses still remaining well below Technical Speci0 cation limits. The licensec will revise the semi-annual effluents reports, submitted to the NRC, accordingly. The inspector determined that there were minimum impacts on the environment and/or to the public health and safety as a result of this event.
4.3 Calibration of Efauent/ Process Radiation Monitors The inspector had reviewed the calibration results for efnuent/ process radiation monitors during a previous inspection conducted in January 1990, llased on discussions with the licensee and a review of records, the inspector had determined that all calibrations were performed in accordance with the requirements. The inspector reviewed the most recent quarterly functional test results for the following radiation monitors to determine the implementation of the Technical Specification requirements, o Main Steam Line Monitor o Augmented Offgas Post Treatment Monitor o Reactor BuildinF Vent Monitor o Main Stack Monitor o Liquid Radwaste Efnuent Monitor All reviewed functional test results were within the licensee's acceptance criteria.
Based on the above review, the inspector determined that the licensee met the Technical Specification requirements. The inspector observed the radiological calibration process for the main stack high range monitor. The licensee followed the calibration procedure and the calibration results were within the licensee's acceptance criteria.
The inspector noted that the licensee has upgraded the radiation monitoring systems.
Twelve out of the 15 plant radiation monitors were replaced by new units (GE, NUMAC System). The licensee also replaced gamma sensitive detectors with beta scintillation detectors for the main stack and reactor building vent effluent :aonitors.
These new detectors are more sensitive to gaseous ef0uents. The inspector stated that the licensce's effort to upgrade radiation monitoring systems was very good.
- -
-. -...
.
-
-
-
_ ________ ___ _
.
..
..
,
-o
.
The inspector, however, noted that the licensee did not have an effluent radiation monitoring system for the salt service water system. Installation of this alt service water effluent radiation monitor was not required either by the Technical Specifications or FSAR. Weekly grab sample analysis is required by Table 4.8.1 of the Technical Specifications. The licensee initiated an increase in the sampling frequency from a weekly grab sample to a daily sample. The grab samples are analyzed using a gamma spectrometry system. The inspector reviewed daily grab sample measurement results and noted that no measurable radionuclides were
'dentined.
Based on the above review, no violations were identified.
5.0 Air Cleaning Systems The inspector reviewed the licensee's most recent surveillance test results as part of the examination of the implementation of the Technical Specification requirements for the Standby Gas Treatment System and Control Room Air Cleaning Systems, o Visual Inspections o In' Place liEPA Irak Tests o in I> lace Charcoal Leak Tests o System Air Capacity Tests o Delta Pressure Tests o Laboratory Tests for the lodine Collection Efficiencies All reviewed test results were found to be within the licensee's acceptance criteria.
Based on the above reviews, the inspector determined that the licensee implemented the requirements for the above systems effectively. No violations were identined.
6.0 Exit Interview The inspector met with the licensee representations denoted in Section 1.1 of this inspection report at the Pilgrim Nuclear Power Station on May 10,1991. The inspector summarized the purpose and scope of this inspection, and discussed the inspection findings.
i
I
-
, - _
. - -. -
-.
.
.. -
- - - -
-
.