ML17055E250

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Semiannual Radioactive Effluent Release Rept, Jan-June 1988
ML17055E250
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/30/1988
From:
NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17055E248 List:
References
NUDOCS 8810210131
Download: ML17055E250 (70)
v • d • e


Text

NINE MILE POINT NUCLEAR STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1988 DOCKET NO.:

50-220 LICENSE NO.:

DPR-63 NIAGARA MOHAMK POWER CORPORATION j

8810210131 880830'DR ADQCK 05000220 R

PNU l

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NINE MILE POINT NUCLEAR STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1988 SUPPLEMENTAL INFORMATION Facility:

Nine Mile Point Unit

$P1 Licensee:

Niagara Mohawk Power Corporation 1.

Technical Specification Limits:

A)

Fission and activation gases:

The dose rate limit of noble gases from the site to areas at and beyond the site boundary shall be less than or equal to 500 mrems/year to the total body and less than or equal to 3000 mrems/year to the skin.

2.

The air dose due to noble gases released in gaseous effluents from the Nine Mile Point 1 Station to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10 mrads for beta radiation

and, during any calendar year to less than or equal to 10 milliroentgen for gamma radiation and less than or equal to 20 mrads for beta radiation.

BSC) Tritium, Iodines and Particulates, half lives ) 8 days:

The dose rate limit of Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight

days, released to the environs as part of the gaseous wastes from the
site, shall be less than or equal to 1500 mrems/year to any organ.

2.

The dose to a

member of the public from Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half lives greater than 8 days as part of gaseous effluents xeleased from the Nine Mile Point 1 Station to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrems to any organ

and, dux'ing any calendar year to less than or equal to 15 mrems to any organ.

D)

Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B,

Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble

gas, the concentration shall be limited to 2E-04 microcuries/ml total activity.

r

D.

Liquid Effluents (Cont'd) 2.

The dose or dose commitment to a

member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 1 unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5

mrems to any

organ, and during any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

2.

Maximum Permissible Concentrations A)

Fission and activation gases:

None specified BEC) Iodines and particulates, half lives

> 8 days:

None specified D)

Liquid Effluents:

10CFR 20, Appendix B, Table II, Column 2.

Avg MPC

( Jan March

)

=

no discharges Avg HPC

( April June

)

=

no discharges 3.

Average Energy (Fission and Activation gases Mev)

Jan.

Harch: ~

= 0.082; Ep = 0.168 Apr. June No discharges 4.

Measurements and Approximations of Total Radioactivity Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.

A)

Fission and Activation Gases:

Noble gas effluent activity is determined by on-line gamma spectroscopic monitoring

<intrinsic germanium crystal) or gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Harinelli sample) of an isokinetic stack sample stream.

B)

Iodines:

Iodine effluent activity is determined by gamma spectroscopic analysis

<at least weekly) of charcoal cartridges manually or automatically sampled from an isokinetic stack sample stream.

IC H

N t"

J t

II

4.

(Cont'd)

C)

Particulates:

Activity released from main stack is determined by gamma spectroscopic analysis (at least weekly) of particulate filters manually or automatically sampled Erom an isokinetic sample stream.

For emergency condenser vent batch

releases, efEluent curie quantities are estimated by subtracting activity remaining in the shell side of the emergency condenser after batch release from activity delivered to the shell from Make-Up sources.

Actual isotopic concentrations are found via gamma spectroscopy.

Batch release activities of Sr-89, Sr-90 and Fe-55 are estimated by applying scaling factors to activity concentrations of gamma emitters.

The activity of tritium released during normal operation or during batch releases is conservatively estimated by multiplying recent condensate storage tank H-3 activity by assumed steaming rates out the vents.

D)

Tritium:

Tritium effluent activity is estimated by liquid scintillation or gas proportional counting oE monthly samples taken with an air sparging/water trap apparatus, E)

Liquid Effluents:

Isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.

F)

Solid Effluents:

Isotopic contents of waste shipments are determined by gamma spectroscopy, gross alpha and water content analyses of a

representative sample of each batch.

Scaling factors established from primary composite sample analyses conducted off-site are

applied, where appropriate, to find estimated concentration of non-gamma emitters.

For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.

5.

Batch Releases The following information relates to batch releases of radioactive materials in liquid and gaseous effluents.

A)

Liquid l.

Number of batch releases:

0 2.

Total time period for batch releases:

3.

Maximum time period for a batch release:

4.

Average time period for a batch release:

5.

Minimum time period for a batch release:

6.

Average stream flow during period of release of effluent into a flowing stream:

7.

Total volume oE water used to dilute the liquid effluent during release periods 8.

Total volume of water available to dilute the liquid effluent during reporting period hours 0

hours 0

hours 0

hours 0

Not Applicable No Discharges 2.85E+01 GL min.

min.

min.

min,

W Wi,<< '

<<4 H

=

H

  • HW H

'H

~

~

W " )'.ll I

~ I

<<H

~

~

W

~

H HI H<<1 g,

5. (Cont.)

B)

Gaseous (Emergency Condenser Vents) 1.

Number of batch releases:

0 2.

Total time period for batch releases:

0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min.

3.

Maximum time period for a batch release:

0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min.

4.

Average time period for a batch release:

0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min.

5.

Minimum time period for a batch release:

0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min.

6.

Abnormal Releases A.

Liquids none B.

Gaseous none

TABLE lA SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION 81 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL JANUARY JUNE 1988 UNIT 1st QUARTER 2nd EST.TOTAL QUARTER ERROR A.

Fission

&. Activation ases 1.

Total release 2.

Average release rate for period 3.

Percent of Technical Specification Limit Ci yCi/sec 1.80E+Ol O.OOE+00 1.0E+02 2.29E+00 O.OOE+00 B.

Iodines 1.

Total iodine-131 2.

Average release rate for period 3.

Percent of Technical Specification Limit Ci yCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OE+00 O.OOE+00 C.

Particulates 1.

Particulates with half-lives >8 days 2.

Average release rate for period 3.

Percent of Technical Specification Limit 4.

Gross alpha radio-activity Ci pCi/sec Ci 8.65E-04 1.10E-04 1.68E-05 3.31E-04 3.0E+01 4.21E-05 2.82E-05 2.5E+01 D. <Tritium 1.

Total release 2.

Average release rate for period 3.

Percent of Technical Specification Limit Ci pCi/sec 1.83E-01 7.28E-02 1.44E+00 5.72E-Ol 2.5E+01

~Stack

& Emergency Condensers

l

TABLE lA (Cont'd)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION f51 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL JANUARY JUNE UNIT 1st QUARTER 2nd QUARTER E.< Percent of Technical S ecification Limits (NMP-1 Elevated Release)

Fission and Activation Gases:

1.

Percent of Quarterly Gamma Air Dose Limit 2.

Percent of Quarterly Beta Air Dose Limit 3.

Percent of Annual Gamma Air Dose Limit to Date 4.

Percent of Annual Beta Air Dose Limit to Date 5.

Percent of Whole Body Dose Rate Limit 6.

Percent of Skin Dose Rate Limit 1.76E-02 1.79E-02 8.79E-03 8.95E-03 7.0SE-04 3.57E-04 O.OOE+00 O.OOE+00 8.79E-, 03 8.95E-03 O.OOE+00 O.OOE+00 Tritium Iodines and Particulates (with halE-lives reater than 8 da s):

2.

3 ~

Percent of Quarterly Dose Limit Percent of Annual Dose Limit to Date Percent of Organ Dose Rate Limit 1.43E-01 1.95E-01 5.68E-03 2.09E-03 2.83E-01 1.04E-01

r 1t lg II I

TABLE 1B SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION f11 GASEOUS EFFLUENTS-ELEVATED RELEASE JANUARY JUNE Nuclides Released Unit CONTINUOUS MODE Fission Gases Argon-41 Krypton-85m Krypton-87 Krypton-88 Xenon-127 Xenon-133 Xenon-135 Xenon-135m Xenon-137 Xenon-138 Kr-85 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 8.50E-08" 1.47E+Ol 3.31E+00 2.11E-04~

2.

Iodines Iodine-131 Iodine-133 Iodine-135 Ci Ci Ci 3.

Particulates 4.

Strontium-89 Strontium-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-58 Manganese-54 Barium-Lanthanum-140 Antimony-125 Niobium-95 Cerium-141 Cerium-144 Iron-59 Cesium-136 Chromium-51 Zinc-65 Iron-55 Molybdenum Tritium Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 1.25E-05 2.93E-06 1.54E-04 6.30E-04 1.08E-05 5.47E-05 1.44E+00 5.67E-06 1.26E-06 1.28E-05 2.52E-04 5.91E-OS 5.72E-01

~Controlled release from a gas calibration standard.

j H

F 8'

TABLE 1C SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION 81 GASEOUS EFFLUENTS-GROUND LEVEL (EMERGENCY CONDENSER VENT) RELEASES JANUARY JUNE Nuclides Released CONTINUOUS MODE BATCH MODE 1.

Fission Gases Argon-41 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-135 Xenon-135m Xenon-137 Xenon-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci No discharges No discharges Iodine-131 ladino-133 Iodine-135 2.

Iodines

~

~

Ci Ci Ci No discharges No discharges 3.

Particulates Strontium-89 Strontium-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-58 Manganese-54 Barium-Lanthanum-140 Antimony-125 Niobium-95 Cerium-141 Cerium-144 Iron-59 Cesium-136 Chromium-51 Zinc-65 Iron-55 4.

Tritium Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci No discharges No discharges No discharges No discharges

Pi gl

'lg II, NIP

TABLE 2A SEMX-ANNUAL RADXOACTXVE EFFLUENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATXON 81 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE Unit A.

Fission and activation roducts 1st 2nd Est. Total guarter guarder Error 2.

3.

Total release (not including tritium,

gases, alpha)

Average diluted con-centration during reporting period Percent of applicable limit Ci pCi/ml None None B.

Tritium l.

2.

3.

Total release Average diluted con-centration during reporting period Percent of applicable limit Ci yCi/ml None None C.

Dissolved and entrained ases l.

2.

3.

Total release Average diluted con-centration during reporting period Percent of applicable limit Ci pCi /ml None None D.

Gross al ha radioactivit 1.

Total release Ci None None E.

Volumes l.

2.

3.

Prior to dilution Volume of dilution water used during release period Volume of dilution water used during reporting period liters None None i>ters liters 2.09E+10 7.60E+09 2.0E+01

-10

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TABLE 2A (Cont'd)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION PP1.

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE Unit F." Percent of Technical S ecification Limits 1st guaetee 2nd quarter 2.

3.

4.

5.

6.

Percent of Quarterly whole Body Dose Limit Percent of Quarterly Organ Dose Limit Vo Percent of Annual Whole Body Dose Limit to Date Percent of Annual Organ Dose Limit to Date Percent of 10CFR20 Concentration Limit fo Percent of Dissolved or Entrained Noble Gas Limit fo

<There were no liquid discharges from NMP-1 through the period January June 1988.

k 4

+g) tl

TABLE 2B RADIOACTIVE EFFLUENT RELEASE SEMI-ANNUAL REPORT (1988)

NINE MILE POINT NUCLEAR STATION 81 LIQUID EFFLUENTS RELEASED JANUARY JUNE Unit BATCH MODE Nuclides Released Strontium-89 Strontium-90 Ces ium-134 Cesium-137 Iodine-131 Ci Ci Ci Ci Ci Cobalt-58 Cobalt-60 Manganese-54 Chromium-51 Zirconium-niobium-95 Barium-lanthanum-140 Ci Ci Ci Ci Ci Ci No Discharges No Discharges Tungsten-187 Arsenic-76 Iodine-133 Iron-59 Iron-55 Neptunium-239 Praseodymium-144 Iodine-135 Ci Ci Ci Ci Ci Ci Ci Ci E Dissolved or Entrained Gases Ci

-12

A J

t 1,,

p V

j ill

~ e 1

TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFl UENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION (f1 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.

Solid Waste Shi ed for Burial Not irradiated fuel 1.

Class of Waste Januar June Est.Total Error a.

Class A

Spent Resins Jll Curies Solidification Agent Container Package Principle Isotopes 4.468+01 5.158+00 None HIC Type A Co60, Csl37,

Fe55, Mn54, Ni63, Co5&, Csl34 2.58+01 Dry Compressible Waste Jll Curies Solidification Agent Containers Package Principle Isotopes 4.08+01 4.058+01 6.568+00 None Steel LSA Box and Steel liner Strong Tight Package
Csl37, Co60,
Fe55, Cs134, Mn54 Boric Acid Wastes m

Curies Solidification Agent Container Package Principle Isotopes 2.528+01 3.22E-02 Cement Steel Liner Strong Tight Package Co60, Csl37,

Fe55, Mn54 Ni63, Co58, Csl34 3.08+01 b.

Class B

Filter Media Jll Curies Solidification Agent Container Package Principle Isotopes 5.108+00 1.808+01 Cement Steel Liner Type A Co60, Csl37,

Fe55, Mn54, Ni63, Co58, Csl34 2.58+01 c.

Class C

None

-13

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w 1

4

TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION ftl SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued) 2.

Estimate of Ma'or Nuclide Com osition b

T e of Waste a.

Boric Acid Wastes Resins Filter Sludges Cobalt-60 Cesium-137 Iron-55 Manganese-54

'ickel-63 Cobalt-58 Cesium-134 Other 4.98E+Ol 3.76E+01 4.45E+00 2.27E+00 1.46E+00 1.09E+00 7.40E-01 2.59E+00 b.

Dry Compressible Waste Cesium-137 Cobalt-60 Iron-55 Ces ium-134 Manganese-54 Other 6.54E+01 2.28E+01 8.40E+00 1.78E+00 8.40E-01 7.80E-01 3.

Solid Waste Dis osition Number of Shi ments Mode Destination 15 Truck Chem-Nuclear Systems Barnwell, South Carolina B.

Irradiated Fuel Shi ments (Disposition)

Number of Shi ments Mode Destination None

TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION 1P1

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY JUNE In accordance with Section 6.9.l.e of the Nine Mile Point 1

Technical Specifications, this Table (a) describes and provides justification for recent changes to the Off-Site Dose Calculation Manual (Revisions 5

and 6) and (b) explains why these changes will not adversely affect the accuracy or reliability of off-site dose calculations or monitor alarm setpoint determinations.

Attachment 2 to this document provides copies of Revisions 4 and 6 to the Off-Site Dose Calculation Manual.

The Revision 6 copy also shows changes made in Revision 5.

All revisions to the Off-Site Dose Calculation Manual were reviewed and accepted by authorized station personnel in accordance with applicable Administrative Procedures and Section 6.5.2 of the Technical Specifications.

Review and approval documentation is affixed to the front side of Attachment 2.

Most of the changes made to the ODCM were in response to an independent SRAB audit conducted on the Unit 1 ODCM by KLM Engineering in 1987.

-15

TABLE 4 (Cont'd)

SEMI-ANNUAL RADIOACTIVE EFFLUENT REf EASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION Pal

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY JUNE ODCM, REV.

4 SECTION CHANGED DESCRIPTION OF CHANGE JUSTIFICATION AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/ALARMSETPOINT DETERMINATIONS 2.1.2, pages 3 and 4

Typographical corrections were made in the Alarm setpoint calculation formula and in the Required Dilution Factor definition.

None 2.1.4.3, page 7

Independent audit conducted by KLM Engineering for NMPC discovered that references made to a sparger spray ring assembly were in error.

The section was therefore deleted.

Actual arrange-ment involves two eductors and one pump providing a total recirculation flow of 300 gpm.

There is no affect since adequate recirculation of the tank volume prior to sampling is provided using the eductors.

2.1.4.5, page 10 The general approach used to estimate H-3, Sr-89, Sr-90 and Fe-55 concen-trations in the event the service water system is contaminated was specified.

Supervisory discretion was applied since, depending on the source of contami-nation, projected concen-trations may vary.

Accuracy/reliability of dose calculations and alarm setpoint determina-tions is improved since the most accurate pro-jected concentrations of non-gamma emitters are applied to the calculations.

2.3.1, page 14 Parentheses were added to units designation typo-graphical correction.

None

-16

TABLE 4 (Cont'd)

SEMI-ANNUAL RADIOACTXVE EFFLUENT RELEASE REPORT (1988)

NXNE

.MXLE POINT NUCf EAR STATXON KP1

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY JUNE

ODCM, REV.

4 SECTION CHANGED DESCRIPTION OF CHANGE JUSTIFICATION AFFECT ON ACCURACY/

REf IABILITYOF DOSE CALCULATIONS/ALARMSETPOXNT DETERMINATIONS 3.1.1, page 19 Revision 4 did not specify which monitor alarm set-points would remain fixed during outage periods.

In Revision 5, stack and offgas monitors were specified.

This change was a clarifica-tion only, therefore, dose calculations and alarm set-point methodologies were unaffected.

3.1.2, page 20 Highest land sector, site boundary X/Q value in Revision 4 was incorrect and inconsistent with the X/Q value provided in Table 3.1.

Therefore, the section was changed to simply reference Table 3.1.

The change had no bearing, on dose calculations or alarm setpoints since proper X/Q values were used in calculations.

3.1.3, page 22 3.1.3, page 23 "R.KR" was typographi-cally corrected to

"(R)(KR)"

Per NRC recommendation of R. Struckmeyer (NRC Inspection 87-06) the relationship between the offgas monitor setpoint determination and the consequent offsite dose needed explanation.

A statement describing the relationship between these two terms was therefore added (and is consistent with NMP-1 Technical Specification Bases).

None This statement provided serves to clarify the relationship between offgas monitor setpoints and off-site doses only.

There is no affect on accuracy or reliability of either alarm setpoints or offsite doses.

-17

TABLE 4 (Cont'd)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

NXNE MILE POINT NUCLEAR STATXON 81

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATXON MANUAL JANUARY JUNE ODCM, REV.

4 SECTION CHANGED DESCRIPTION OF CHANGE (JUSTIFICATION)

AFFECT ON ACCURACY/

RELXABILITYOF DOSE CALCULATIONS/ALARMSETPOXNT DETERMINATIONS 3.1.5.3, page 26 3.1.5.5, page 27 3.2.11, page 32 Sentence structure improvement A statement was added to specify that redetermi-nation of I-135/I-131 and I-133/I-131 ratios should be performed after plant status or fuel integrity changes.

Typographical corrections were made to include proper dose rate units and summation signs.

None Accuracy of dose calcula-tions/alarm setpoints is improved by this change since iodine data used in the calculation should be more accurate.

None 3.2.12, pages 33 and 34 The target particulate and iodine release rate value used to trigger dose rate calculations was r'aised from 1E-02 to 3E-01 yCi/sec since the previous value was overly conservative.

Dose/alarm setpoint calcula-tions remain unchanged.

Reliability of dose rate calculations should not be affected since the new target release rate value will still trigger dose calculations prior to exceeding Technical Spec-ification limits.

3.2.1.2, page 35 Typographical correction

'IIDII to

~ID tt None

-18

II lalt

TABLE 4 (Cont'd)

SEMI-ANNUAL RADIOACTIVE EFFIUENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION tt1

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY JUNE

ODCM, REV.

4 SECTION CHANGED DESCRIPTION OF CHANGE JUSTIFICATION)

AFFECT ON ACCURACY/

RELIABIIITY OF DOSE CALCULATIONS/ALARMSETPOINT DETERMINATIONS page 45 6 46 4.1, pages 45 and 46 Revise reference in dose calculation to note that dose is to teenager or adult.

Adult reference was added for consistency with other sections of 4.1.

For shoreline

sediment, the dose to a teenager or an adult is the same.

No change to the dose equation or the calculated result.

More accurately describes the dose.

4.4, page 50 Added reference to note that boating is not permitted at the Energy Information Center Facility.

No change to the dose equation.

More accurately describes the basis of the dose equation.

4.4, page 51 Added reference to note that X/g value based on a stack (elevated) value corresponding to 0.5 miles is 'conservative because of the close proximity of the stack and receptor location.

Reference was a clarifi-cation.

No effect on dose or dose equation.

4.4, page 51 Revised reference to Regulatory Guide.

E-7 is correct reference previous reference was incorrect.

Reference is a clarification No effect on dose.

Table S.l, page 83 Reference to TLD ft26 as environmental program number 92 was a typo-graphic correction.

Previous reference was incorrect.

Change is a typographical correction.

No effect on dose.

Table 5.1, page 8S Added Produce Location ttl2 (map location tt59)

Addition more accurately reflects location of the closest garden locations.

-19

TABLE 4 (Cont'd)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION tl

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY JUNE CHG.

NO.

ODCM, REV.

4 SECTION CHANGED DESCRIPTION OF CHANGE JUSTIFICATION AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/ALARMSETPOINT DETERMINATIONS 20 Table 5.1, page 85 Added reference to define the letters CR.

CR means control result (location).

Reference is clarification.

No effect on dose.

21 Figure 5.1-2 (Off-Site map)

Added Food Product location Pt59 to be consistent with the new sampling location noted on Table 5.1.

The addition increases the accuracY of the environ-mental sampling program.

-20

TABLE 5 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION St1

SUMMARY

OF CHANGES TO THE METEOROLOGICAL MONITORING SYSTEM JANUARY JUNE The Nine Mile Point Nuclear Station (including the James A. FitzPatrick Nuclear Power Plant) has improved its processing of wind direction data this reporting period.

This was accomplished by the replacement of 360 degree wind direction processors with 540 degree wind direction processors.

The 540 degree processing of wind direction is state of the art and affords improved readability of north winds on analog wind direction recorders.

All other aspects of the system remain the same.

-21

TABLE 6 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION fP1

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY JUNE The Nine Mile Point

/Pl Process Control Program (PCP) for waste solidification, as described in Administrative Procedure 3.7, Revision 2,

was not revised during the January-June reporting period.

-22

ATTACHMENT 1 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

PROBLEMS WITH THE NMPl STACK EPPLUENT MONITORXNG SYSTEM:

CAUSES AND CORRECTIVE ACTIONS JANUARY JUNE The causes and corrective actions for several design deficiencies existing in NMPl's high range stack monitoring

system, RAGEMS, were identiFied and outlined in the July-December 1987 Semi-Annual Report.

Although progress has been made in correcting these design deficiencies, additional modiFications are still necessary to upgrade the system to a

more reliable condition oF operation.

It should be

noted, however, that the stack monitoring requirements, as defined in Section 3.6.14.b of the Radiological Environmental Technical Specifications (RETS),

were met using the Old General Electric Stack Monitoring System (OGESMS).

Furthermore, RAGEMS was available for meeting TMI IX.F.l.l monitoring requirements from January through May in the 1988 reporting period.

Subsequent to May 1988, the system was rendered inoperable to perform modifications during the outage.

Current plans are to continue with these modifications through 1988 and 1989.

Although (a)

OGESMS, (b) an interim high range stack telector monitor, and (c) environmental sample survey team data are available to supplement monitoring when RAGEMS is inoperable, the OGESMS does not have a sufficient range to satisFy TMI IX.F.l.l monitoring requirements during post-LOCA drywell venting.

Therefore, it is our intent to maintain RAGEMS availability during most periods of commercial operation to meet monitoring requirements.

STACK MONITORING SYSTEM ModiFication U date The following is an update of recent modifications and design changes made to date on

RAGEMS, and a

summary of modiFications needed to complete the entire system upgrade:

1.

Developed a

new PSID to convey more detailed information on a

complex system to enhance system operation.

2.

Completely revised the system's radiation alarming logic to include both the Radiological Gas Effluent Monitoring System (RAGEMS) and the OGESMS to Facilitate operator response.

This design package is complete and awaiting site approval for installation.

Installation is expected by the end of 1988.

-23

ATTACHMENT 1 (Cont'd)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

PROBLEMS WITH THE NMPl STACK EFFLUENT MONITORING SYSTEM:

CAUSES AND CORRECTIVE ACTIONS JANUARY JUNE 3.

Designed flow alarming capabilities from the RAGEMS unit to the plant's main Control Room.

Installation is expected prior to plant restart.

4.

Replacement of RAGEMS'ennelec Count Rate Meter to eliminate the periodic spiking signals.

Installation of a new count rate meter is expected prior to plant restart.

5.

Improved operator interface with the system's parameters by increasing the ability to chart/record the system's operation.

This design package will be issued for construction by the end of 1988 and includes:

A.

Placing the existing OGESMS radiation signals (counts per second) on new recorders.

6.

B.

Addition of new parameters to be recorded (e.g.,

the RAGEMS radiation release

rate, OGESMS system flow, RAGEMS system flow and total stack flow).

Installation of a

permanent power supply for the air conditioner in cabinet t4 of RAGEMS.

This design package was issued for construction in late February 1988 and is awaiting installation by the Site Electrical Department in September 1988.

7.

Installation of cables for future expansion of the system.

This design package was issued for construction in late June 1988 and should be installed in September 1988.

8.

Installation of remote manual switches to the RAGFMS dilution system to manually override the RAGEMS process computer.

The design of this work is currently being worked on with a projected completion date by the end of 1988.

Installation is expected in 1989.

9 Provide RAGEMS with the capability to isolate the plant's containment vent and purge valves.

OGESMS currently has this isolation capability.

The design of this modification is in progress with a

projected completion date in 1988.

Installation is expected in 1989.

10.

Replacement of the flow control valves with RAGEMS.

The design of this work is in progress with an anticipated completion date by the end of 1988.

Installation is expected prior to restart.

ATTACHMENT 1 (Cont'd)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

PROBLEMS WITH THE NMP1 STACK EFFLUENT MONITORING

,SYSTEM:

CAUSES ANb CORRECTIVE ACTIONS JANUARY JUNE ll. Replacement of the flow control valve and associated controller on OGESMS.

The design of this work is in progress with a

projected completion date by the end of 1988.

Installation is expected in 1989.

12. Installation of calibration
valves, leak test valves and gauges on both RAGEMS and OGESMS.

This design package has been issued for construction and currently is being installed.

13.

Redesigned the particulate and iodine filtration portion of OGESMS to provide filtration redundancy.

This design package has been issued for construction.

Installation is expected in September 1988.

14. Installation of additional shielding designed to eliminate periodic spikes in the background radiation levels on the OGESMS monitors.

This design is in progress and expected to be issued for construction by the end of 1988.

15. Resolution of computer software and hardware problems.

This work includes the upgrade of the computer's modem capability.

Presently, this work is in progress and anticipated to be completed in 1989.

16. Modify RAGEMS/OGESMS computer input and output signals to provide additional essential input to the Safety Parameter Display System (SPDS).

This work should be completed in 1989.

17. Revision of the plant's process computer's descriptions and setpoints as they apply to the Stack Gas Monitoring System (OGESMS and RAGEMS).

Completion is projected for 1989.

-25

ATTACHMENT 2 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)

NINE MILE POINT NUCLEAR STATION ttl OFF-SITE DOSE CALCULATION MANUAL REVISIONS JANUARY JUNE Attached are copies of, Revisions 4

and 6 of the NMP-1 Off-Site Dose Calculation Manual.

Changes made in Revision 5

are indicated in Revision 6

(see revision bars located on the right hand side of individual pages).

Also provided are copies of review and approval documentation associated with Revisions 5

and 6.

Description of changes made to the Off-Site Dose Calculation Manual are provided in Table 4 of this report.

-26

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