IR 05000250/1988015
| ML20206N065 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 11/18/1988 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML17345A546 | List: |
| References | |
| 50-250-88-15, 50-251-88-15, NUDOCS 8812050272 | |
| Download: ML20206N065 (10) | |
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ENCLOSURE 4 ERRATA SHEET - TURKEY PCINT SALP PAGE LINE NOW READS SHOULD READ
10-13 In addition, procedure Sentence deleted
...was required.
Basis for ci uge:
To properly address the facts in regard to licensee's procedures.
49 437 instances 252 instances Basis for change:
To correct administrative error.
50 186 events 187 events Basis for change:
To correct administrative error.
51-52 These numbers represented These numtaers are an increase relative to relatively unchanged 1986...were reported.
from 1986...were reported Basis for chi.nge:
To properly iddress the facts in regard to the number
cf reported contamination events.
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13-14
Tha higher number... outage sentence deleted work conducted in 1987.
Basis for change:
To properly address the facts in regard to the number
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of reported contamination events.
1-3 The total number...was The total number...was above everage...PWRs.
slightly below average
...PWRs.
Basis for change:
To properly address the facts in regcrd to the number
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of reported contamination events.
17-19 During 1987.. 4,300 cubic During 1987.. 10,800 feet...
cubic feet...
Basis for change:
To correct administrative error.
19-20 This volume...is one of This volume...is below the lowest of any the average for PWRs facility...
in...
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Enclosure 4
Basis for change:
To properly address the facts in regard to the volume of radioactive waste which the licensee shipped offsite.
21-26 Increased...resulted in a Increased...resulted in significant reduction a reduction...
Basis for change:
To properly address the facts in regard to the volume of radioactive waste which the licensee shipped offsite.
Section V.K.3.a 1987 1987 T3T W
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Basis for change:
To correct administrative error.
Section V.K.6.a 1987 1987 GO TOOO Basis for change:
To correct administrative error.
Section V.K.6.b 1987 1987 14,497 TT!500 Basis for change:
To correct administrative error.
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staff in the procedural upgrade and the comprehensiveness f
their technical reviews of procedures by the site and corp ate HP staf f were. less than adequate.
For example, a vio tion concerning inadequate procedure guidance for radiation ontrols during removal and transfer of reactor coolant syst (RCS)
spent filters was identified during the assessme period despite the fact that radiation controls for this ctivity had been previously reviewed earlier in the assess ent period follo. sing an event which exposed workers to h gh radiation levels.
In addition, procedures did not requi e documentation of personnel contaminations, even in an insta ce when extensive deconta nination of an individual was require.
Licensee action in replacing several pri ary components of the post accident sampling system was ti ly and demonstrated licensee initiative in problem solving The licensee did not effectively ad ess technical issues in the radiation protection area such a electronic drifting of the invivo counter.
The licensee d not develop complete and technically sound procedures.
ese findings, combined with the viciations identified in the adiation protection area. during the assesment period, indica e a decline in what had oeen in previous assessment period identified as a strong, aggressive and technically sound r diation protection program, with effective leadership fro management.
During the assessmen period, the licensee's radiation work permit and respirat y protection programs were found to be
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satisfactory.
Control of con mination and radioactive materials within the facility was generally adequate.
At the beginning of January 1987 approximately 27,000 square feet (ftr) or 38% of the radiati controlled area (RCA), excluding containment, were controlle as contaminated. Although the licensee had a goal of
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reducing. the area contaminated by 20% in 1987, the actual reducti n was less than 12%. At the end of December 1987, the
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licen e maintained 34% of the RCA as contaminated.
This is the larg st percentage of any Region II facility. Toward the end of thi assessment period, the licensee began an extensive upgrada o
the contaminated control program including decontamination of ant areas, use of contamination contair.nents and preventive maintenance of leaking valves.
As of July 15, 1988, the total area maintained as contaminated was reJuced to 12,600 f ti o r 18*.
of the RCA, which is still greater than most Region II facilities.
The Itcensee reported 43/ instances of personnel contamination
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in 1987, of which 186 events were identified as skin contamination.
These numbers represented an increase relative
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i to 1986, when a total of 257 contamination events were reported.
The higher number of personnel contaminations was related to the
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staff in the procedural upgrade and the comprehensiveness of their technical reviews of procedures by the site and corporate HP staff were less than adequate.
For example, a violation concerning inadequate procedure guidance for radiation controls during removal and transfer of reactor coolant system (RCS)
spent filters was identified, during the assessment period despite the fact that r6diation controls for this activity had been previously reviewed earlier in the assessment period following an event which exposed workers to high radiation levels.
Licensy action in replacing several primary components of the post ;ccident sampling system was timely and demonstrated licensee initiative in problem solving.
The licensee did not effectively address technical issues in the radiation protection area such as electronic drifting of the inviva counter.
The licensee did not develop complete and technically sound procedures. These findings, combined with the violations identified in the radiation protection area during the assesment period, indicate a decline in what had been in previous assessment periods identified as a streng, aggressive and technically sound radiation potection program, with effective leadership from management.
During the assessment period, the licensee's radiation work permit and respiratory protection programs were found to be satisfactory.
Control of contamination and radioactive materials within the facility was generally adequate.
At the beginning of January 1987, approximately 27,000 square feec (f t) or 38% of the radiation controlled area (RCA), excluding containment, were controlled as contaminated. Although the licensee had a goal of reducing the area contaminated by 20% in 1987, the actual reduction was less than 12%. At the end of December 1987, the licensee maintained 34% of the RCA as contaminated. This is the largest percentage of any Region II facility. Toward the end of this assessment period, the licensee began an extensive upgrade
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of the contaminated control program including decontamination of plant areas, use of contamination containments and preventive maintenance of leaking valves. As of July 15, 1988, the total area maintained as contaminated was reduced to 12,600 ft or 18%
of the RCA, which is still greater than most Region II facilities.
The licensee reported 252 instances of personnel contamination in 1987, of which 187 events were identified as skin contamination.
These numbers are relatively unchanged from 1986, when a total of 257 contamination events were reported.
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unscheduled outage work conducted in 1987. Tne total number
personnel contaminations for 1987 was above average fo Region 11 PWRs.
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The 1987 collective radiation dose was 645 person-rem r unit which was approximately 75% above the national av age of 368 person-rem per PWR. The increased collective do for 1987 was attributed to increase outage activities.
A mparison of Turkey Point radiation protection attributes to R gion Il plant averages is listed in section V. K.
During this SALP period, the chemistry sup visory staf f had been reorganized and administrative progra were initiated to more effectively address qualification of personnel and chemistry control new training staff and training laboratory had been provided, however, the smel size of the chemistry staff continued to be an impediment o initating the training
program.
Also, insufficient perso nel resources created an obstacle to upgrading chemistry rocedures.
In 1984, the licensee initiated a chemistry i rovement program for upgrading facilities, equipment and analy es for controlling chemistry in the secondary water cycle.
T is program was in line with the recommended guidelines of e Steam Generators Owners Group (SGOG) and the Electric ower Research Institute (EPRI).
Completion of the total mprovement program has been delayed because of assignment o lower priorities as part of the Turkey Point Nuclear Plant tegrated Schedule.
Completion of the seconda ry chemistry inline monitors is scheduled for November 1991, an November 1992, for Units 3 and
respectively.
C struction of a new secondary chemistry laboratory is s eduled for March 1992.
The licensee ontinued to encounter dif ficulties in controlling chemistry b cause of degrad.tton of condenser tubes and problems associate with the equip.nent conditions of the makeup water treatmen plant.
Liqui radwaste processing, using a contractor and a portabh dem eralizer system, maintained excellent control over tb re ease of radioactive effluents.
The mixed fission enu tivation products in liquid effluents for 1987, were
.75 curies for both units, which was consistent with previous years and less than the 0.5 curies per unit industry average for PWRs for 1983, the last jear for which industry data was available.
There were no significant changes in the gaantities of gaseous A
effluent during this SALP period from previous periods.
The effluent releases for the past three years are summarized in the Supporting Data and SumariesSection V.K.
The licensee's quality assurance program for the counting room
was adequate.
Tne licensee participated in a quarterly
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The total number of personnel contaminations for 1987 was slightly below average for Region II PWRs.
The 1987 coliective radiation dose was 645 person-rem per unit which was approximately 75% above tra national average of 368 person-rem per PWR. The increased collective dose for 1987 was attributed to increase outage activities. A comparison of Turkey Point radiation protection attributes to Region II plant averages is listed in section V. K.
During this SALP period, the chemistry supervisory staff had been reorganized and administrative programs were initiated to more effectively address qualification of personnel and chemistry control. A new training :taff and training laboratory had been provided; however, the small size of the chemistry staff conti1ued to be an impediment to initating the training program.
Also, insufficient personnel resources created an obstacle to upgrading chemistry procedures.
In 1984, the licensee initiated a chemistry improvtment program for upgrading facilities, equipment and analyses for controlling chemistry in the secondary water cycle.
This program was in line with the recommended guidelines of the Steam Generators Owners Group (SGOG) and the Electric Power Research Institute (EPRI).
Completion of the total improvement program has been delayed because of assignment of lower priorities as part of the Turkey Point Nuclear Plant Integrated Schedule.
Completion of the secondary chemistry inline monitors is scheduled for November 1991, and November 1992, for Units 3 and 4,
respectively.
Construction of a new secondary chemistry laboratory is scheduled for March 1992.
The licensee continued to encounter difficulties in controlling chemistry because of degradation of condenser tubes and problems assnciated with the equipment conditions of the makeup water treatment plant.
Liquid radwaste nrocessing, using a contractor and a portable demineralizer system, maintained excellent control over the release of radioactive effluents The mixed fission and activation products in liquid effluents for 1987, ve-t 0.75 curies for both units, which was consistent with v,
. :s years and less than the 0.5 curies per unit industry ev'
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<t PWRs for 1983, the last year for which industry data a,
available.
There were no significant changes in the quantities of gaseous effluent dur"ng this SALP period from previous periods. The effluent releaset for the past three years are summarized in the Supporting Date and SummariesSection V.K.
The licensee's quality assurance program for the counting room
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cross-check p.,
s with a vendor whose quality assuranc program was trace.oie to the National Bureau of Standards.
As part of the NRC's confirmatory measurements program, he licensce analyzed
~ samples for selected beta-emi ing radionuclides.
The results were in agreement for itium, strontium-90 and iron-55.
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The maximum environmental radiation doses attrib ed to plant
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l re16ase were a small fraction of 10 CFR 20 an 10 CFR 50, i
Appendix I limits and criteria. Maximum total ody dose to a I
hypothetical individual from liquid ef fluents, as calculated to be 0.0156 mrem per unit, which was 0.524 per ent of the annual limit.
Maximum gamma air dose and bet air dose to a i
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hypothetical individual frcm gaseous rete es were less than 0.2 percent of the annual limit.
t Ouring 1987, the volume of solid rad onctive waste shipped by the licui.Lc? totalled 4,300 cubi feet (ft ) containing
903 curies of activity. This volu of waste shipped offsite is one of the lowest of any facili in Regiom II.
During 1987, the licensee initiated the use a vendor to super compact the waste prior to shipment for b rial.
Increased decontamination efforts for equipment and m erial leaving the RCA, as well as control of material being rought into the 2CA, resulted in a significant reduction in adioactive waste volume relative to 1986, when approximatel 11,420 ft3 were shipped containing approximately 89 curie.
Three violations wer identified:
j a.
Severity le 1 IV violation for failure to follow radiation work permi (RWP) requirements (87-36).
b.
Severit Level IV violation for failure to properly comp 1 ' e a manifest for a radioactive waste shipment (b/-
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erity Letel IV violation (four examples) for f ailure to olf
' ave adequate procedures (87-48).
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Co clus19<
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3 Board Recor endaticos Licensee management should give continued ateention to:
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addressing the continuing higher than average annual collective occupational doses and ) ef forts to reduce plant and personnel y
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d contaminations.
In a ;.. ton, licensee managemerit should assure
%+<y that there is an acequate level of resources and support
provided to effectively deal with these issues.
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was adequate.
The licensee participated in a quarterly cross-check program with a vendor whose quality assurance program was traceable to the National Bureau of Standards.
As part of the NRC's confirmatory measurements program, the
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I licensee analyzed samples for selected beta-emitting radiorJClides.
The results werk in agreement for tritium,
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strontium-90 and iron-55.
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The maximum environmental radiation doses attributed to plant
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release were a small fraction of 10 CFR 20 and 10 CFR 50,
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Appendix 1 limits and criteria.
Maximum total body dose to a hypothetical individual from liquid effluents was calculated to be 0.0156 mrem per unit, which was 0.524 percent of the annual limit.
Maximum gamma air dose and beta air dose to e hypothetical individual from gaseous releases were less than 0.2 percent of the annual limit.
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During 1987, the volume of solid radioactive waste shipped by (
the licensee totalled 10,800 cubic feet (ft) containing
903 curies of activity. This volume of waste shipped offsit-is
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below the average for PWRs in Region II.
During 1987, the licensre initiated he use of a vendor to super compact the waste prior to shipment for burial.
Increased decontaniination efforts for equipment and material leaving the RCA, as well as control of material being brought into the RCA, resulted in a
reduction in radioactive waste volume relative to 1986, when
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approwimately 11,420 ft were shipped containing approximately
89 curies.
I Three violations were identified:
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a.
Severity Level IV violation for failure to follow radiation
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work permit (RWp) requirements (87-36).
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b.
Severity Leul IV violation for fsilure to oroperly
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complete a manifest for a radioactive waste shipment (87-36).
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Severity Level IV violation (four examples) for failure to follow and have adequate 7rocederet. (87-48).
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t;onclusion
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Category:
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Board Reccmmet.dations i
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.icensee management should give continued attention to:
(1)
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addressing the continuing higher than average annuti collective
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occupational d 4 es and (2) efforts to reduce plant And personnel contaminations. In addition, licensee management sheuld assure i
that there is an adequate level of resources and scport
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provided to effectively deal with these issues.
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c.
October 12, 1987, the unit was shut down as a precautionar measure for a hurricane warning.
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d.
February 7,1988, the unit was shut down fro.,100*4 po r due to exceeding the Technical Specification action ate-ment for inoperable battery chargers, e.
April 6, 1988, the unit was shut down to investi ate and repair a leak in the turbine control oil syste,
f.
April 28, 1988 the urJt was shut down due t increased RCS leakage (3.2 gpm) esused by a pressurizer pray valve bellows rupture.
K.
Radioactive Effluent Releases (Ci/YR)
Activity Released (Curies)
1985 1986 1987
1.
Gaseous Effluents Fission and Activation
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Gases 3.1 4.65 1.70 Sodiums and Particulates 0.
0.023 0.025 Tritium
593 820 i
2.
Liquid Effluents Fission and Activation
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Products 0.9 0.506 0.75 Tritium 869 727 540 3.
Personnel Contaminations
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a.
Turkey Pot 437
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b.
Region !!
R Average 306
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Contaminate Area (fts)
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a.
Tur ey Point 23,821 L
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R ion 11 16,023 L
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Cel etive i
Do (Man-rem)
l Turkey Point 645
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b.
Region !! PWR Average
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390
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Solid Rad Waste (ft )
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Turkey Point 4,300
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Region !! PWR Average 14,497
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c.
October 12, 1987, the unit was shut down as a precautionary measure for a hur.*icane warning.
d.
February 7,1988, the unit was shut down from 100% power due to exc2eding the Technical Specification action state-ment for inoperable battery chargers, e.
April 6, 1988, the unit was shut down to investigate and repair a leak in the turbine control oil system, f.
April 28, 1988 the unit was shut down due to increased RCS leakage (3.2 gpm) caused by a pressuri:er spray valve bellows rupture.
K.
Radioactive Effluent Releases (Ci/YR)
Activity Released (Curies)
1985 1986 1987 1.
Gaseous Effluents Fission and Activation Gases 3.12 4.65 1.70 Sodiums and Particulates 1.015 0.023 0.025 Tritium 320 593 820 2.
Liquid Effitents Fission and Activation Products 0.9 0.506 0.75 Tritium 869 727 540 3.
Personnel Contaminations 252 a.
Turke/ Point
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306 b.
Region II PWR Average
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4.
Contaminated Area (ft)
23,821 a.
Turkey Point
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16,023 b.
Region II
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Collective Dose (Man-rem)
645 a.
Turkey Point
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390 b.
Region II PWR Average
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6.
Solid Rad Waste (ft)
10,800 a.
Turkey Point
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14,500 b.
Region II PWR Average
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