ML20107B491
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JUN 23197i c
J. F. O'Reilly, Chief, Reester Testing and 4
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operatians Branch, Diviesa of Compliameg, EQ 4
JERSET CENIRAL POWER AW LEggt amam (Ot8TER CERE) i 900tEr 30. 50-119 t
The attashed report of inspostians esadmeted at the subject Sesility on April 6 - 8, 12 and 13, 1971 is forwarded for action.
1 These inspections included an in-depth soview of the licensee's
=mang===t of radseste, similar to those recently performed at Ginna, Nine Mile Point and Dresden. As you are mare, similar results unre obtained and added up to several safety / - pliance items servesting formal enforcannot action. You have our proposed enforcement letter 1
l which was forwarded in advance of this report.
F The findings portaining to radueste management were a disappointment j
to us especia11y' in light of the positive signs received daring our i
recent audit of management systems. All the.more reason to go the formal enforcement route. With regard to the specific deficiencies noted, 9 g telecons with the site indicate that proper cor-rective action has been or is being implementad. An inspection is j
currently underway (June 22 - 15, 1971) and will include followup in these areas.
I McDermott's inspection included follouup on several of the deficiencies i
identified in our====g====e systems audit. More will be covered l
during the current inspection including a visit to Parsippany, l
tentatively set for the week of Jane 18 One of the areas rovfeued during the April taspostimes was the surveillamse testing program.
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Although JC is still est enspletely on top of this, they ase in a
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mach better positian them he5ere, esposta11y with a full time
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soordinater of surveillance testing activities.
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This ropest desuments early (menemmetam en the eers sprey system
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unter hammer problem. Kappler/Nolan have been kept infeemed of subsequent developments. The sismificasse of the problem (possible j
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Form AEC-$le (Rev 9-53) AECM 0240 9 v. s. so va n=wan t enmtme o rsic s, s ae, o-3 o.e n?
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2 everstressing of system piping) makes this a reportable (10 day) event for whimb they are enestem. Caummatestians with NoCluskey in this regard have bees unfruitful. This was Aspressed upon Fiafrock ta a sail to him en this matter by una===att on Juss 22. It is now our understanding that a report will be submitted in the very usar i
future.
h turbias stop valve closure screms (Mos. 14 and 15) highlight the I
possibility of an event.widah may" border en a situattaa 1the "curbine trip without bypass valve opantma. h mode of turbino stop valve q
closure, i.e., momentary less of oil pnessure, was._,M to have resulted in some delay of bypass velve openias. McDermott has dis-aussed the delay aspects of thi.s event with Bill Farmer, Technical support tranch, who indimmead that he intended to pursue this with GE during a meeting scheduled for May 19, 1971, our zweise of the transianen for the two scrase in question did not discloes any con-earns.
The station staff has been augmented further. Although not all are destined for 0 ster Creek (sans to go to Forked River 1) this facility f
should benefit durius the interim.
f JC has experienced a inseber (13 at time of in8P88tiOR) Of LI8M failures. Nine Mile Point has a similar problem. The cause, moisture via connectors outside vessel but inside drywell, apparently is the same in each case.
l You will note that CE's metallurgical analysis of the previously reported failure of a push-pull rod in the turbias bypass valve control system shoued that the material was not in accordance with l.
l design specifications. JC has been unsuccessful thus far in gettin8 j
more details from GE. All four affected rods at OC-1 have been j
replaced.
The Sollowing matters are also spoken to in the mtport:
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Scram history data (your memoranden dated 2/8/71).
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Aircraft everfliatts (your memorandma dated 2/1/71).
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14ak detection equipumat and procedures (you memoranden dated j
q 3/2/71).
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It should be noted that Mr. G. Fredrickson, GAO, accompanied the inspectors an all dates as part of their audit of Region I.
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I R. T. Carlson Sr. Raastor Inspector l
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Co Repon No. 219/71.-1 a
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S. ATOMIC ENERGY COMMISSION DIVISION OF COMPLIANCE
^RCCIC:: I Field Notes for:
CO Inspectiop Report No.
50-219/71-02
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Subject:
Jersey Central Power & Light Co.
Oyster Creek 1 License No. DPR-16
. Location:
Forked River, N. J.
Priority Category C
. Type of Licensee:
BWR Type of Inspection:
Routine, Announced Dates of Inspection:
June 22-25 & July'2, 1971 Datos of Previous inspection:
April 6-8, 12, 13, 1971
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Principal Inspector:
R. J. McDermott 8/2/71 Date Accompanying Inspectors: L. B. iligginbotham; F. S. Cantrell Date T. Young; R. T. Carlson Date Other Accompanying Personnel:
None Date.
Reviewed By:
R. T. Carlson 8/23/71 Date Proprietary Information:
None b
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2' 0YSTER CREK - 1 Inspection cI 0, A }, 2 Y ll Higginbotham e
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SECTION I Enf*orcement Action None Liconsee Action on Previousiv Identified Fnforcement Matters
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l A.- Due to a procedural error in coBting and analysis of liquid waste.
effluent it appeared that total radioactivety released had been underestimated for the year 1970. Corrective action to preclude recurrence of this. error was verified during the inspection. 00-1 plans to report corrected values for total activity released in their next semiannual report to the AEC.
B.
The procedural error in counting and analysis of wastes also caused 0C-1 to exceed the technical specification limit for total activity in outside waste storage tanks.
Corrective action to prevent recurrence was verified during the inspection.
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Status of Previousiv Renorted 11nvesolved Itama A.
A review of records and discussions with plant personnel during the last inspection disclosed / that 00-1 had apparently not utilized the waste treatment system in a manner to limit or maintain the release of radioactive liquid effluent,s as low as practicable during a major pertion of 1970. 1.xamination of records disclosed that effective use of the waste treatment system had begun /M in November 1970 and the volumes and total activity had decreased since tnat time.
This inspection disclosed an apparent further reduction in volumes and total activity.
OC-1 had instituted a program to control and further limit releases of waste to the environment.
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SECTION II Additionni Sub'ects innoection. Not Identified in Section I. Where No Deficiencies Or ifnvesolved Items Were Fotmei 1.
Radiation Protection s.
Personnel monitoring records January 1970 to March 1971.
b.
Survey records January to April 1971.
2.
Radicaletive Warte Systems a.
Logs and records January 1970 to ).iay 1971.
b.
Procedures for counting and analysis.
- 3. - Environment 1 M ni terine-a.
Records for January 1970 to December 1970.
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OYSTER CREEK - 1 Field N:tes i
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e-O pu eres Details or subjects Discussed in Section I (ak d in Id 5 ' * *
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' Liould Waste System Descriotion (Figure 1)(.cliscussta O r-N '4
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Iow conductivity Wastes.
Low conductf.vity (high purity) liquid waste from piping and equipment drains are collected in: (a) the drywell equipment drain sump, (b) the rebetor. building equipment drain tank, and (c) the turbine building equipment drain sumps.
Such wastes from piping and equipment drains are transferred to the waste collector tank in the radwaste build'ing.
This tank will also collect wastes from the fuel pool, reactor cleanup system, absorp-tion chamber, spent resin and filter sludge dewatering, ani low conductivity condensate demineralizer backwash water.
Low conductivity wastes collected in the waste collector tank and waste surge tank are processed through a pressure precoat filter (waste filter) and a mixed bed demineralizer (waste demineralizer) and then collected as a batch in one of two waste sample tanks.
Af ter these wastes are sampled and analyzed, they are normally trans-ferred to the condensate storage tank.
Processed water may be 4
returned to the waste collector tank for recycle through the system.
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Mich Onnductivity Wastes. High conductivity (low purity). liquid
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waste (primarily from floor drains) is collected in: (a) the radwaste building floor drain sumps; (b) the reactor building floor drain sumps; (c) the turbine building floor drain sumps; and (d) the drywell floor drain sump. Such high conductivity waste is transferred to the floor drain collector tank in the radwaste building.
1 High conductivity wastes are processed through a pressure precoat filter (floor drain filter) and thdn collected as a batch in one i
of two floor drain sample tanks. After these wastes are sampled and analyzed, they are normally discharged to the circulating water discharge canal'.
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Chemical waste. High conductivity chemical wastes such as lab-oratory drains and condensate demineralizer regeneration solutions are collected and pumped to the waste neutralizer tank in the radwaste building.
Chemical wastes collected in the neutralizer tank are sampled and neutralized as required. Those batches having sufficiently low concentrations of radioactive material for off-asite discharge will be filtered and received in the floor drain sample tank.
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Af ter sampling and analysis, this waste will be discharged to the circulating water discharge canal. Those batches which are too high in concentration for off-site discharge are concentrated in the waste concentrator and the condensate liquid is sent to the -
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waste collector tank.
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uiscellaneous Liould waste.
Primary system water resulting from J
refueling and startup operation is discharged through the fuel pool filter and demineralizer and reactor cleanup system to the condenser hotwell and returned to condensate storage.
Liquid waste from laundry operation and waste from shipping cask decontamination are collected in fAc laundry drain tank.
After sampling and anaiysis these wastes are discharged to.the circulating water discharge canal.
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Waste i
Sample Tank Equipment Waste Waste Waste
"*l Drains Collector Filter Demin-
- Condensate i
Reactor Tank (WCT) d d
eralizer Waste
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Discharge Radwaste 30,000 gal 3
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Tank g
30,000 gal i
Waste Surge
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Tank Laundry-
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100,000 gal Drain Tank 2,000 gal Flow control-.
- measure, j
Floor Drain radiation _..
HIGH SOLIDS 10g000 gal-Floor Drain Floor Floor Drains Collector Drain Turbine b1dg Discharge Tank Filter Floor Drain Canal l
Reactor b1dg 10,000 gal Radwaste b1dg Sample Tank 10,000 gal HICH ACTIVITY T
Waste L
t Regenerants Neutralizer Condensate Tank
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deminer ~-
12,000 gal
'. ' Waste Collector Tank l
alizers Waste.
Neutralizer Waste Concentrated Concen-Waste Tank Shiph nt Tank j
12,000 gal trator 5,00D gal Drtes Storage s.
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5 System Performpnce(00 rpt 7141, attachment 1, par E) j The last inspection disclosed that the 1Mensee had been j
" unsuccessful in determining what the (design) objectives (of thewastesystem)are". Substantial variances were observed in actual use of the radwaste system as compared with statements the majority of liquid wastes in in the FSAR: (a)/ waste collection drains were intended to be reused as condensate; however, during 1970 less than 10) were processed for reuse with the remainder discharged to the environment, (b) chemical wastes were to be sampled and concentrated with the distillate processed to the waste collection u
system. During1970essentiallyallsuchwastewasdigcharged se:
->n to the environment through the floor drain system,[(c) $0, %ked N
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concentrations of radioactivity in the floor drain system ranged
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from 20 to 100 times the expected. value of 0 5 x 10 Ci/ml i
and,(d) actualisotopicconcentrationsand/$8hkNionof liquid wastes were found to vary substantially from expected j
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values listed in the FSARL t The licensee reported (Pelrine, Stoudnour, Ross) that shortly after the last inspection the concentrator had been employed about 16 to 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> per day, primarily for floor drain liquids.
Figure 3 shows the major flow paths for liquida processed in the system at the present-time.
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Waste-LOW SOLIDS
+ WcWM ank Equipment Waste Waste Waste 30,000 gal Drains Collector vile.r nomin.
+ Condensate iI U
eralizer Reactor Tank (WCT) n
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Mscharge Radwaste 30,000 gal Tank 30,000 gal g
t Waste Tank Laundry O
Surge 100,000 gal +
Drain Tank 2,000 gal pig,e,'ntrol-I
- measure, i
Floor Drain radiation SamP e Tank monitor l
HIGH SOLIDS 10;000 gal-Floor Drain Floor Floor Drains Collector Drain O<-
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Turbine b1dg
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Tank Filter Floor Drain Canal Reactor b1dg 10,000 gal Sample Tank j
Radwaste b1dg 10,006 gal
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t Waste Regenerants Neutralizer Condensate Tank t
deminer--
12,000 gal vaste Collector Tank alizers Waste Neutraliz Wasta Concentrated j
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Concen" Waste Tank Tank r
p 12,000 gal trttor
.5,000 gal Druns Shipmen'-
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waste i
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+- Recycle-WCT Equipment Waste Waste Waste 30*000 al l
Drains Collector Fi1 Par Da=i".
o ensate Reactor Tank (WCT) d eralizer Waste im Discharge t
Radwaste 30,000 gal Sample Tank 30,000 gal Iwaste Tank Laundry O
Surge
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100,000 gs1 Drain 1
Tank 2,000 gal Flow control-
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Floor Drain radiation HICH SCLIDS S8mple Tank monitor
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10,000 gal-Floor Drain Floor Floor Drains U
Discha y
^5 Turbine bide Tank Filter Floor Drain
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Reactor b1dg 10,000 gal Sample Tank Radwaste b1dg
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7' HICH ACTIVITY
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p Regenerants Neutralizer Condensate Tank i
deminer --
12,000 gal 7
Waste Collector Tank
.,s alizers Waste
,s Neutralizer Waste Concentrated Tank Concen-Waste Tank i
'12,000 gal trator 5,000 gal DItuns Shipment r
Storage
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Table 1 shows the volumes of liquid waste processed through l
the system and a breakdown of volumes discharged to the environ-ment and volume recycled for use within plant pystems.
Table' 2 shows a breakdown of waste discharges by volumes from the waste sample tanks and floor drain sample tanks.
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Waste Releases (C0 rpt 71-01, attachment 1, par B)
Table 3 shows total activity discharged from the plant in two t
columns; one value is that reported by the licensee in semi-annual reports and based on their gross beta analysis, the other value is
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the " corrected" total activity which the licensee intends to report as a result of the last inspection. The corrected totals do not include dissolved gaseous activity, i.e., Xenons, which have been identified in samples of processed waste collection system water.
The basis for the correction factor of wacte releasec for_ the year 2
1970 (multiplying reported values by h.1) was explained by Ross (the data was also presented to ACRS by Ross):
a.
Comparison of an 00-1 gamma spectrum analysis for 1970 to a gross Beta count used for a release gave a factor of 6.2; total gamma activity / gross beta = 6.2.
b.
Comparison of results of isotopic analysis between 00-1 and three other laboratories (Radiation Management Ccrp, Isotopes, Inc, General' Electric) indicated that 00-1 f
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Table - 1 4
Oyster Creek - 1 Waste Helease Data 3
Gallons x 10 1920.
Released Returned Total Processed Cn = 1stive Jan 1309 2 1309 2 1309 2 Feb 1014.0 1014.0 2323.2-j.
Mar 1174.6 167 1 1341 7 3664.9
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Apr 1047 2 1047 2 4712.1 May 977 3 977 3 5689,4 Jun 1100 3 1100.3 6789 7 Jul 1153 2 1153 2 7942 9 Aug
-1492.4 1492.4 4435.3 Sep 1289.8 1289.8 10725 1 Cet 1230.1 1230.1 11955 2 Nov 1161.0 93 0 1254.0 13209 2 Dec 673 643 3 1316.3 14525 5 1921 Jan 590.0 8Q5 6 1395.6 15921.1 Feb 748.8 440.6 118).4 17110 5 Abr 977 2 3L9 1 1326.3 18436.8 Apr 7L6 302 7 1050 7 19h67 5 796 1313 0 20808 5 Ma;.
517 Jun 2LL
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1000 1244 22052 5 Stoudnour hired to supervise waste system Leak developed in a makeup line from demin water tank to condencate storage tank; inleakage to condensate storaEe tank which prevented reuse of some water processed in waste system therefore it had to be released.
May 10 the leak (**) was repaired.
Total also includes about 8000 gallons from laundry tank, Total includes about 8000 gallons from laundry tank.
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Table 2 I/
Ovster Creek - 1 Waste Release Data 3
Gallons x 10 4
Source of Liould Releases from Waste System 197]l Waste Samnle Tank Floor Drain Tank M
4 ki Jan 597 8 711.42 1309.2 Feb 477 8 536.2 1014.0 var 518 3 656.3 1174.6 Apr 533 1 514.1 1047 2 May 367.6 598.7 977 3 Jun 645.6 454 7 1100 3 Jul 675 478.2 1153.2 Aug 926.2 566.2 1492.4 Sep 819.8 470.0 1289 oct 736.9 493 2 1230.1 l
Nov 726.4 434.6 1161.0 Dec 190 9 482.1 673 4
Jan 14h.2 445 8 590.0 Feb 508.4 240.4 748.0 var 683.6 293.6 977 2 l
Apr 606.0 142 784 May 460 49 509 Jun 219 7
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Table 3 Ovster Creek - 1 Liauld Waste Releases Curles Unidentified 19,7.Q,,
Tritium Renorted Correc ted l
Jan 2.62 0.283 1.16 Feb 1 38 0.424 1 74 l
mr 2.18 0.196 0.804 Apr 1.88 0.185 0 759' my 0.87 0.060 0.246 Jun 1.42 0.613 2 51 Jul 1.89 0 721 2 96 Aug 2 55 0.461 1.89 Sep 1 99 0 353 1.45 Oct 1 72 0 392 1.61
. k Nov 1 93 0.495 2.03 Dec 1.41 0.320 1.31 Totals Xenens from pg 19.21 Jan 1.67 0,35h 1.45 Feb 2.3 0 518 1,73 Mar 2.14 0 952 2.86 Apr 1.84 0 918 0 96 May 1.31 0.884 0.884 Jun Not available 0.44 0.44 While 00-1 still reports activity other than tritium as" unidentified" the total curies are based on results of isotopic analysis of each batch release. Ilowever, even though identification is made the
~I release is controlled on the basis of 1 x 10 Ci/ml.
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results were high in all cases. A total of four samples were used in the evaluation, one laboratory analyzing two samples.
Results showed 00-1 to be high by factors of 1 96, 1.20, 1.49, g
07, 0.8.
00-1 then used another correction factor from this data of 1 5 which was applied to the 6.2 factor from paragraph a above:
6.2 /15 = 4.1, and 1970 values of total activity are to be multiplied by this value. 1971 values for total activity, January throtgh April, are corrected in a similar manner; however, the value varies for each month according to the amount of activity 1
that was released based on gross beta analysis. Beginning in May 1971 all releases are being made on the basis of isotopic analysis: 18 beta-gamma emitters by gama isotopic analysis, Xenon 133, 135, tritium, and strontium-90. Each batch is analyzed in this manner except that a value for strontium-90 is used based on the experience from several sampic analyses; infrequent re-sampling is perron:cd to verify the strontium-90 value used.
Ross was reluctant about reporting an estimate of noble gases or Xenons released in liquid discharges.
He said that it would be difficult, if not impossible, to reconstruct enough data upon which to base a value.
I outlined one trethod for Ross which I feel h'as as sound a basis as the one used to correct total activity. Analysis of waste sample tanks show the presence of 4
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l Xenon 133,135 in the range of 10 pCi/ce, whereas results of analysis of. floor drain system liquids do not show the presence of Xenons. The/$0EIMptof the gas in floor drain liquids can be explained by (1) it is indeed not present or, (2) the activity i
i is masked, in the gamma spectrum, by the presence of plutonium-239 and/or other activity.
It is detectable in the waste collection I
system because the ganna spectrum is fairly clean due to removal l
of the major portion of the activity in fiiters, concentrator, I
and the demineralizer. Further, one would not expect significant if any amount of the' gas in floor drain liquids because they j
have probably evolved from exposure in sumps and other portions of the system.
If an estimate, better termed a guess, must be made of dissolved i
Cases released in liquids, the method following is as good as l
any:
a.
From a review of records at 00-1 for the period of May 15, l
,>d 1971 through June 20, 1971 where the results of 77 enaly'es s
of waste samples showed the presence of Xenon-133,135 the
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average concentration of the gases was about 2 x 10 pCi/ml.
I Xenons were identified in analysis of waste sample tanks and
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never in floor drain sample tanks.
b.
The total volume of liquid waste released in 1970 was 6
6 13.6 x 10 gallons; 7 2 x 10 from waste sample tanks and n m
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6.4 x 10 gallons from floor drain sample tanks.
If the assumption is made that all liquids released contained dissolved gases then 6
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(13.6 x 10 Eallons)(2 x 10 pCi/ml) = 10 3 Curies would be the guesstimate. If the assumption is made that Xenons were present only in waste sample tank releases then i
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(7 2 x 10 gallons)(2 x 10 Ci/ml) = 5 4 Curies would be the guess.
However, a review of raseous_ releases reveals that total curies released per month increased from a low of about 3500 to a high of about 14,400 during 1970. The values reported for 1971, January through Wy, varied from j
l about 16,700 curies to the high (in May) of 35,000 curies.
Correcting these values reported for total curies to amounts of Xenon-133,135 (from averaging percent of composition by isotope in gas analyses) the average curies of Xenon-133,135 released per month in 1970 is about l;6 33; the average curies of Xenon-133,135 released for the months of April and May 1971 (June la not available as yet; May and June are the months for f
which Xenon-133,135 values are averaged for a " gas in liquid" h,
concentration) is about 4,963 If the assumption is made that Xenon-133,135 dissolved in liquids is proportional to that produced and released, then the estimated values for gas in water given above can be corrected by the factor
'1970 average /1971 period average = /GU/48U = 0.3$
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If the assumption is that all liquids released contained Xenons the gaseous activity in liquids is 10 3 Curies X 0. = 7..f Curies as a guess. j i If the assumption is that Xenons were present only in waste sample tank releases the gaseous activity in liquids is 5 4 Curies X 0.3V = l,8 Curies as a guess. 7 Isotonic ComDositien/ Distribution (C0 rpt 71-01, attachment 1) A review of the results of startup test number 1, Chemistry and Radiochemistry, disclosed that measurements of iodine carryover indicated values in the order of 1 to 2 percent; concentration of iodine in steam / concentration of iodine in reactor water. i Thic is the same range of values reported at Millstone-l. The startup test reports et both facilities state that this probably results from changes (from Dresden-1 design) in the cleanup systems and steam dryers. The values reported in both Millstone and OC-1 FSAR for isotopic composition in wastes are based on Dresden-1 experience and data. 6. Liould Waste Monitor (C0 Report 71-01, attachment 1, par D) The background radiation problems for these monitors 1 ave been reduced to about 80 to 100 cps by replacement of contaminated (carbon steel) piping with stainless steel and addition of 9 r-
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c.., - - ~ -. - . +, ,y'#- o / <a . f 6f. .ex ernal shielding.-- A majorlof high background radiation was-3 t from external sources. The-current setpoint for the alarm ' -3 corresponds to a con::entration of.about 1 x 10 perf,1, -The 3 r monitor serves an alarm function only, it does not serve to -f trip or close valves to' halt a weste discharge. The discharge pumps from waste sample tanks are ga. tad,for.300 gpm; the~ dilution l i I . or circulating water. flow is about 460,000 gpm; the dilution factor-1 ' (at maximum discharge) would be 460,000/300 or about 1500. l i 1 4 To ensure that an instantaneous concentration of 1 x 10 pCi/ml i 'i is not exceeded in the discharge. canal the monitor setpoint U would be (l'x 10 Oi/ml)(1500) *1 5 x 10.pCi/m1'as compared with the celected.value'or 1 x.10-3' ci/ml which is higher,than 4 - the calculated value by a factor of about 10. Technical specifi-cations allow a maximum daily average of 10 times the annual average. The volume of a waste. sample tank is 30,000 gallons and at the rated maximum capacity of the pump of 300 gpm the tank would be emptied in about 15 hours. A continuous daily b discharge at 300 p would amount to 432,000 gallesns/ day. L 5 t 4 ') i a 4 1 L F g
^ t s^ o 3 ~ Gaseous Effluents 9 Stack nas unnt' tors Calibration curves for the two stack gas monitors are shown in Figure The current setpoint for the "high-alarm" corresponds { to a stack release of about 0.03 Ci/second,1/10 of. the annual average release rate limit; the "high-high alarm" corresponds to the annual average release rate limit of 0 3 Ci/sec. The monitors serve an" alarm function only and have no isolation or trip functions. A st.ack monitor celibration factor is determined on a weekly basis from (1) analysis of a grab sample of off-gas and (2) holdup time from off-gas flow determination. The indicated ~ activity at the off-gas sample line is decayed for the holdup time and a calibration factor is determined in eps/ Ci/sec. The stack gas activity as indicated by the monitors is contin-or a bases uously recorded (cps) and, weekly the =dC.y calibration factor is applied to integrations of the readings of strip chart recorders. 10, crf-cas unniters I Calibration curves for the two off-gas monitors are shown in Figure f. The current setpoint for the "high-alarm" corresponds l l = _.g, s.
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.e ...-.-.a. - -. ~. ~.. s (..) ' ) f s to the 0 3 ci/soe annual average release rate limit as measured-at the off-gas monitor for air inleakage of 100 cfm; the "high-high alarm" corresponds to the 3 0 ci/sec 48-hour release rate limit of technical specifications, the 3 0 ci/see is also as measured at .s l the off-gas monitor. At present the setpoints hitve two " factors of conservatism"; present air inleakage is determined to be about 10 to T cfm and the setpoints do not take into consideration the decay through holdup time. The present average off-gas flow is about 110 cfm (atout 15 cfm inicilugt) which affords a holdup timo of about 60 minutes; with '100 cfm inleakaCe the holdup time would be, of course, about 30 minutes. l 11. IsotcM e Annivsis. S 6 vs E 22 Geses in Effluents OC-1 is presently converting activity measurements of E 6 fission i gases at the air ejector to predicted JG 22 fission gases at the stack. i ^ '">7
./. =.u - w O D l ~ By definition: (2 BWR's) Eauilibrium component or mixtu'+ of fission gar!es exist when conditions are such at a long delay time (relative to half-lives of composition) is present between production of the a 5 I gas and its release. The activity (A) in an equilibrium-mixture = a derived constant (K,) X the fission yield (Y): A = K, Y and when data is normalized K Krypton = K, Xenon 3l" K, Iodine ( d X 10). g An equilibrium mixture of gases is indicative of very small holes or fuel defects. There is no consistent correlation of releases with power levela low release rates; some j l spiking on changes in reactor power. Recoil component or mixture of fission gases exist when there is essentially no delay time between production and release. The activit, (A) in a recoil mixture = a derived constant (K ) X the fission yield (Y) X the deca) constant (k): r A=K Yh r and when data is normalized K I dine = K Xenon = K Krypton... r r r An equilibrium mixture of gases is indicative of'large holes-or fuel. defects, fuel in the coolant or fuel in contact 1 l with the coolant.. Activity release rates follows power and j no spiking on power changes.
-d O 3 4 J Diffusion component or mixture of fission gases is the intermediate condition between the two previous conditions, i.e., there is intermediate delay time between production and release of the gas. Theactivity(A)inadiffusion \\j mixture = a derived constant (K ) X Me Masion yield (Y) X d the square root of the decay constant h): ~ A=K d and when normalized K I di"* " Xenon =.... d d A diffusion mixture is indicative of small fuel defects. The release rates follow an exponential increase with power 1 level, spikes occur on porter changes. Assuming the activity release is due to. one of the three " pure" components described above, the following summarizes the decrease (by decay) of total activity according to holdup time; $ 6 gases measured, g 22 gases calculated.. Equilibrium O minutes ar 6 A A = 1.2 30 minutes st 22 60 minutes 2 22 A A = 1.4 Diffusion 0 minutes e 6 A A = 1.8 30 minutes 8 22 60 minutes 6 22 A A = 2.8 Recoil 0 minutes
- 6 AA=25 30 minutes e 22 60 minutes # 22 A A = 5.8-6
.=- 7.- - e :. a n.-s, O -'r Figure 6 is a graph of the ratio of 2 6 to 2 22 in off-gas mixtures for various holdup times and gives an indication of relative error if the' measured activity of. the26 gases is not corrected -for the presence of the 22. T From the measurement of: the 6. gases it is fairly simple l to
- calculate the release' of 22 gases, for a given holdup time, if the mixture 6cnsists of a " pure" component, i.e., recoil, diffusion, or equilibrium.
If there is contribution from two or three of the components to the activity mixture the calculation becomes somewhat more involved. Example: recoil = K YA A r A K Y = equil e j i A E Y diff d ls To normalize gaseous (and iodine) activity where two cf the compcnents are present in the mixture: t i J i L W e -e-p = r y e .= rw -er- -w--~ r--
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A. "+4.a, -w ,4 k.e 6-.me e s ,e .e O 3 v, '11brium + Recci_1 "~ A A Atotal = recoil + equil \\ 8 A c "K Yh + K, Y Y f equelshhu m g i. Ag K + K h = r e Y If the data from the measurement of the 6 gases is nornalized and plotted on a graph such as the one above and the plot followed a horizontal line tendence, the mixture is an equilibrium mixture; if the data plott&d to a slope or 45 angle the contribution is from recoil. An intermediate slope is indicative of contribution from a diffusion component. Diffusion + Recoil k*j ' b #'/ Av wt e A, + A A ' k,YA+ Kd YE A yN YA k,+ka-{R' vecesl k As indicated above if the slope of the plotted data follows the curves in this type plot, the activity contribution is from the component indicated. A:best fit curve falling between the horizontal and a 45 angle would indicate a mixture of the . i two. components. e e.
o ..s. O ) L,s. L.; Diffusion + Eaullibrium fl A4: Aa<Ae 3 Y A = kaYW 4 K 7 A ,Wl:6 pg l h, As before. Figures 7, 6, and 9 are graphs plotted from measurement of the six gases at CC-1 on May 12, 1971. i From these figures it appears that the majority of the activity is contributed by a diffusion component with small contribution of Xenon-133 from equilibrium. Note that as the mixture strays 1 from equilibrium toward recoil, more short-lived activity is added to the mixture; at pure recoil the majority of total activity is short-lived activity. Another approach to graphical analysis of the mixture is to plot j h vs h
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,. -.a. h . O. ..) i' L ej k o<j e e I; b/ f s i A T Yh yy/ 5 \\ ,e y. o (k#c h~l*v$ me,\\ Footnote: GusNisof X 0 A$3
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.i In this type of plot it is, I think, easier to see the type or component contribution to the gas mixture; the slopes. shown are the " ideal" case for pure components. The footnote i gives fact 6ra to determine,from graphed data, the total Activity for a pure mixture, e.g., from a "best fit" curve e
- W J
/ .~ a- .q' e T O O i which has. been drawn through the plotted data of measurements of the six gases a point is picked on the curve; the A/I s) for the point is multiplied by the h for the point (in the case of an equilibrium component) and the result'is multiplied by g E the value in the footnote, i.e., for equilibrium, times 7 0.263 While the values in the footnotes may,at first, seem like some " fudge factors" they are: equilibrium - #6 Y 0.263 = diffusion =56 Y E = 2 75 x 10-3 -5 recoil = ft 6' Y h 5.69 x 10 = Figure /0 is a plot of the May 12, 1971 data from 00-1 for measurements of the 6 gases from the off-gas. The slope of the plot is indicative of a diffucion mixture. H wever, there is probably some small contribution from other components but it would appear to be relatively small. The May 12, 1971 example was used as CC-1 had reviewed their data while evaluating the error in not accounting for the 2 22, i.e., comparison of E 6 vs K 22. In doing this type comparison D. Ross and E. O' Conner calculated a resultant curve for a theoretical mixture of the gaseous components, e.g., curves for 20% recoil, 60% diffusion, 30% equilibrium. The curves drawn for various mixtures are used in a template
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4_-_.-._ ?. ^ O J form to draw a "best curve" fit through plotted dsta points from an isotopic analysis (4 6) of an off-gas sample. The template ~ which fits a best curve line through the dr sa points 1 (e.g.,10% r, 60% d, 30% e template) decides the correction factors to apply to the measured activity to' determine the 5 summation of 22 gases at the stack. For their May 12 data the evaluation sheet read: 4.06 x 10 ci/see measured at the off-gas 1 51 x 10 Ci/see was recorded as the stack release rate off-gas flow indicated a 63 nanuted holdup time, used 60 minutes in evaluation. for pure components the stack release rate would have been: 6 0 6.19 x 10 j,,g,,c,o 3 kci/ m recoil 4.06 x 10 e 4.79 x 10 E e s,e a,= 6;94 x10 7 2 f 11 equil 4.06 x100, 1.6 x 10 l = 2.95 x10 11 2.2 x 10 8 diffusion 4.06 x104, 8.9h x108 " l'b7 X10 ~ 9 2 31 x 10 4 30% recoil = 0 3 X 6 94 x103= .21 x 10 ci/see 10%equil = 0.1 X 2.95 x10 30 x 10 = k 60%diff = 0.6 X 1.47 x10 .88 x lo 1 39 x 104 ci/see at stack The recorded valua for the stack release rate was 151 x 10 which is higher than the calcu*ated value by a factor of (1 51/1 39) = 1.09, or about 9fo high. If I had performed 4 ~ eeng
.. -a ; (- J. .O D r the evaluation I would have settled for a straight or pure - diffusion mixture as indicated from Figure /O. My total activity at the air ejector would have been (fcom Figure /o ) about 4'.125 x 10 pC1/sec and the stack release rate from this would be about 1.h9 x 10 pCi/sec, as compared with their b { calculated value of 1.39 x 10 Ci/sec and their recorded 4 velve of 1 51 x 10 pCi/sec'. Examination of Figure [, the ratio of 2 6 to Ji' 22 for variouc holdup times indicates that the maxirmm error that-could be experienced for a 60 minute holdup time, if only 2 6 is censidered rather than 2 22, is in the orcer or 83, of the ceveral evaluations that I examined at 0C-1, some had overestimated the release rate, as in the above example, and som had underestimated the stack release rate; that is the comparison of stack release rate calculated on the basis of 2 6 vs calculation of SE 22 considering makeup of the gas mixture. The "unders" and " overs" would about balance. out in the ones I examined. The maximum error of 8% given above is for a holdup time of about 60 minutes. e y + = gg,
~ _'c........:- t? AN O .) e t i i Figure II is a graph of holdup time vs off-gas flow for the holdup volume reported to be available. Following is some i data of off-gas flow measurements at 00-1 that was~taken [. from records. The values reported, or given below, are f: averages for the monthly periods, i 1222 cfm off-gas 1911 cfm off-gas Jan 211 Jan 105 Feb 103 Feb 104 Mar 121 2r 111 Apr 115 Apr 108 May 117 May 106 Jun 101 Jun 109 Jul
- 99 Aug 95 Sep 95 Oct 99 Nov 101 Dec 111 The average for.the 18 month period is about 112 cfm, or an average holdup time of about 63 minutes.
Figures 17 through 11 are plots of the noble gas patterns for measurements at 00-1 in June and May 1971. To the plots of noble gas patterns I have added iodine production patterns from measurements of reactor water; noble gases from isotopic analysis of off-gas grab samples, iodines from grab samples of reactor water the same date. Note that the iodine patterns parallel the noble gas patterns and are usually lower by a factor of about 10, as indicated for 'the normal case in discussion of component pattern analysis presented previously. 'F
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4 t Figures 18 through.19 -present iodine patterns for camples. of reactor water in' January 1971.. 4 Nb NM Iodine production rates were determined by:
- 6ncentration(C1/m1}(volumeofwaterin' reactor)X
[ decay constant'4 removal constant in cleanup. system + removal constant from carryover]= pCi/ cec Som further notes on the GE method of analyzing off-gas + :; mixtures. Figure 2.0 is a plot of 1/Y b vs h for the 6. fission gases; Figure 11 is a plot of 1/Y N for the 6; j and Figure
- 2. 2, is a plot of 1/Y.
i As mentioned previously when the gas mixture strays from &l an equilibrium component (relatively long delay time between production and release indicative of very small defects) j to a' recoil component (short delay time between production 1 1 1 and release indicative of relatively large defects, fuel in j the coolant or in contact with the coolant) the ratio of short-lived activity to long-lived activity will increase and in a recoil mixture the short-lived activity predem-inatea. s .k t.
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. -1 !'i., 1.] 1,-,1 - i.. 1 Iodin.o Prod.u.ction Patterns' 3.. _ ' i 3 .J January 6,,1971 l n I, f ..1, I... I w$; +r. , +.. .. +. 2 t. i ~ 1 . ;e 9 il e 6 10 - i u
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k 4 Figure 2 3 is a plot of the ratio of Xenon-138 (14 min) to roes of the measured 6. Ideal ratios are plotted, the other 6 c tyV for the three mixture components, i.e., recoil, diffusion, Wt ' ~ and equilibrium, and for each component the ratio existing at time = 0 and tine = 10 minutes is shown. For recoil conditions the ratio of Xenon-138 to Xenon-133 (5 day) is about 500 at t = 0. Figure 2Q shows a family of curves for gas mixtures comprised of percentages of contribution from all threc
- J components.
Figure 2 6 is a plot showing OC-1 data for the year 1970, i.e., ratics of the 6 isotopes to Xenon-138. Figure 2 4 is a similar plot of 1971 0C-1 data. Figure 2 7 and28 are 4ggg plots of two specific analyses of 00-1 off-gas in May 1971. A diffusion component has predominated the OC-1 gas release since early 1970. For comparison, Figures 21, 50 and 31 are " ratio plots" of Millstone-1 data for three specific analyses of off-gas in March and April 1971. The data indicates thu an equilibrium component dominated the mixture. l 6
4- ~ i l.. CountinF aM Analysin 12. Gross Beta Countinrr The calibration error that was disclosed during the last inspection g$;ty 9 j001 - has been corrected. While gross beta counting is still being performed the results are not being used to determine total activity or concentrations released; this is bcing done by isotopic analysis of each batch of liquid released. 13 Carbon - 14 .;q o Results of several samples sent out for analysis showed levels -6 in liquids of about 10 Ci/ml to 10~E; the MPC is 8 x 10 Ci/ml. Samples were of undiluted waste and/or reactor water. 1h. PI 3300 Samnies telMid Two liquid samples were obtained of waste sample tanks; 500 m1 each, shipped in glass bottles with plastic caps and sealed with paraffin; each treated with K S 0 and 10 ml conc. hcl 225 per instructions from IDO-HSL. I Two samples of off-gas collected; standard 14.1 ml glass vials used for plant sampling; one was scaled with paraffin one was not; this was to determine if gas is lost during shipment through' the rubber serum cap. The samples were sequential; five were taken with 0C-1 using the middle threc y1 and #5 shipped to IDO-HSL; Cross counting cf the five gave results within statistical error ,. 6 o
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4 t,- and the sampites shipped to IDO-HSL should be representative of the 00-1~ samples. I ' dgj .;%p Stack sampler. charcoal cartridge.and particulate filter for
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the sample period preceding the. inspection.were shipped to - IDO-HSL. 4 ~ No results have been received as of July 7,1971. 4 Curie Content in Outside Storare Tanks
- 15. As with waste releases, the curie content of storage tanks is controlled on the' basis of isotopic analysis rather than gross beta counting.- A review of records revealed no instance where technical specification limits (total of 0 7 Curies) had been 4
M exceeded since the last inspection. t 9 i a 4 e i 4 4 'i fe. I ,.w.
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