ML20212H364

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Semiannual Radioactive Effluent Release Rept,Surry Power Station,(Jul-Dec 1986)
ML20212H364
Person / Time
Site: Surry  Dominion icon.png
Issue date: 12/31/1986
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
87-058, 87-58, NUDOCS 8703060083
Download: ML20212H364 (19)
v • d • e


Text

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POW 24 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION Uuly 1,1986 Through December 31,1986) l i

PRUpRED BY j KPPROVED llY l

l 0703060003 041231 PDif H

ADOCK 05000200 gt PDit k

l

PORWARD This report is submitted as required by Appendix A to Operating License No.'s DPR-32 and DPR-37, Technical Specifications for Surry Power Station, Units I and 2, Virginia Electric and Power Company, Docket No.'s 50-280, 50-281, Section 6.6.B.3.

RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION (July 1,1986 Through December 31,1986)

Index Section No. Subject Page 1 Purposo and Scopo 1 2 Discussion I&2 3 Supplomontal Information 2 Attachment 1 Effluent Roloaso Data Attachment 2 Annual and Quarterly Dosos Attachment 3 Revisions to Offsite Doso Calculation Manual (ODCM)

Attachment 4 Revisions to Process Control Program (PCP)

Attachment 5 Major Changes to Radioactivo Liquid, Gasoous and Solid Wasto Treatment Systems Attachment 6 Inoperability of Radioactivo Liquid and Gasoous Effluent Instrumentation Attachment 7 Unplanned Releases i

Pags I of 2

1.0 Purpose and Scope

The Radioactivo Effluent Release Report includos a summ7ry of the quantities of radioactivo liquid and gaseous offluents and solid wasto as outlined in Regulato-ry Guido 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Rc1casos of Radioactive Materials in Ligsid and Gaseous Effluents from Light-Wator-Coolod Nuclear Power Plants", Roiston 1, June 1974, with data summarized on a quarterly basis following the f ormat of Tables 1, 2 and 3 of Appondix B thereof. The report submitted within 60 days after January I of each year includos an assessment of radiation doses to the maximum exposed member of the pubile due to radioactivo liquid and gaseous offluents released from tho sito during the previous calendar year. The report also includes a list of unplanned releases during the reporting portod.

As required by Technical Specification 6.8B, changes to the ODCM for the timo i period covered by this report are included. Information is provided to support the changos along with a packago of those pagos of the ODCM changed.

This report includos changes to the PCP with information and documentation necessary to support the rationalo for the changos as required by Tochnical Specification 6.8A.

Major changos to the radioactivo liquid, gaseous and solid wasto treatment systems are reported as required by Technical Specification 6.9. Information to support the reason for the chango and a summary of the 10CFR50.59 ovaluation are included. In llou of reporting major changos in this report, major changos to the radioactive wasto treatment systems may be submitted as part of the annual TS AR updato.

As required by Technical Spectitcation 3.7E.2, a list and explanation for the inoperability of radioactivo 11guld and/or gaseous offluent monitors are provided in this report.

2.0 Discussion The basis for the calculation of the percent of technical specification for the critical organ in Tablo I A of Attachment 1, is Technical Spocification 3.llD.l.a (11). Technical Specification 3.llD.I.a (11) requires that tho doso rato for lodino

- 131, for tritium, and for all radionuclidos in particulato form with half-livos greator than 8 days shall be loss than or equal to 1500 mRomlyr to the critical organ at or beyond the sito boundary. The critical organ is the child's thyrold, inhalation pathway.

The basis for the calculation of porcont of technical spocification for the total body and skin in Tablo I A of Attachmont 1, is Technical Specification 3.llD.I.a (1). This Technical Specification requiros that the doso rato for noblo casos to areas at or beyond sito boundary shall bo loss than or equal to 500 mRom/yr to tho total body and loss than or equal to 3000 mRomlyr to the skin.

Tho basis for the calculation of the porcent of tehnical specification in Tablo 2 A of Attachment 1, is Technical Specification 3.11 A.I.a. Technical Specification 3.ll A.I.a states that the concontration of radioactivo matorial rolonsed in liquid offluonts to unrestricted areas shall be limited to the concontrations speciflod in 10CTR20, Appendix D, Tablo !!, Column 2 for radionuclidos other than dissolved or entrained noblo gasos. Por dissolved or entrained noblo gasos, the concontration shall bo limited to 2 X 10-4 microcurios/ml.

Pega 2 of 2 4

Percent of technical specification calculations are based on the total gaseous or 11guld offluents released for that respectivo quarter.

The annual and quarterly dosos, as reported in Attachment 2, woro calculated according to the methodology presented in the ODCM. The bota and gamma air dosos duo to noble gases released from the sito were calculated at site bounda-ry. The maximum exposed member of the public from the roloaso of airborno lodino - 131, tritium and all radionuclidos in particulate form with half lives greater than 8 days, is defined as an infant, exposed through the grass-cow-milk pathway, with the critical organ being the thyroid. The maximum exposed memb-or of the public from radioactivo materials in liquid offluents in unrestricted areas is defined as an adult, exposed by olther tho invortobrato or fish pathway, with the critical organ being olther the thyroid or GI-LLI. The total body doso was also dotormined for this individual.

Unplanned rolossos presented in Attachmont 7 aro defined in Technical Specification 6.6.B.3 as thoso gaseous releases excooding Technical Specification 3.11.B.l.a and those liquid releases excooding Technical Specification 3.11. A.I.a.

3.0 Supplomontal Information Technical Specification 3.ll.D.I.d requires the identification of the causo for the unavailability of milk or loafy vogotation samplos, required by Technical Specification, Tablo 4.9-3, and identification for obtaining replacement samplos.

All milk and loafy vogotation samplos required by Teolo 4.9-3 woro availablo for collection during the portod of July 1,1986 through Docombor 31,1986.

Tochnical Specification 3.11.D.2.b requiros tho identification of now samplo locations datormined with the Land Uso Consus as ytolding a calculated doso or doso commitment greator than the values being calculated in Tochnical Spocif-ication 4.9.C. No now samplo location (s) that may ytold a greater doso or doso commitmont that are currently used in Technical Specification 4.9.C, woro identiflod in the Land Uso Consus.

Dry Cask Indopondent Spont Fuel Storago Installation Technical Specification Appendix C, 1.4.1 requires reporting the quantity of each of the principal radionuclidos roloased from the installation to the environment in liquid and gaseous offluents during the previous 12 months of operations. Thoro was no liquid or gaseous offluent rolonsos from the Dry Cask Indopondent Spont ruol Storago Installation during the period of January 1,1986 through Docombor 31,1986.

Att: chm:nt 1 i

EPPLUENT RELEASE DATA (July 1,1986 Through December 31,1986)

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P:g) I of 6 ,

KrFLUMNT AND WASTR DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/86 TO 12/31/86 GASKOUS KrfLUENT-SUMMATION Of ALL RKLKASES SU:RY POWER STATION UNITS 1&2 UNIT THIRD QTR. FOURTH QTH.

  • KS T. KRROR A. PISS 10N & ACTIVATION GASSS
1. TOTAL RELKASK CI 9.94K 00 3.66K 01 2.50K 01
2. A VG RMLMASK RA TE FOR PERIOD UCI/SKC 1.25K 00 4.611 00 B. 10DINK
1. TOTAL 1-131 CI 1.3HK-04 4,67K-04 2.50K 01
2. A VG RKLMASK NATM TON PERIOD UCI/SKC 1.74K-05 6.881-06 C. PARTICULA TK
1. HALT-LIVES >H DA YS Cl 7.40K-04 6.89K-04 2.50K 01
2. A VG RKLKASK NA TE FOR PERIOD UC1/SKC 9.31K-05 7.41K-06
3. GROSS ALPNA RADICA0TIVITY C1 4.99K-07 6.93K-07 D. TRifl0M
1. TOTAL RKLKASK Cl 6.67K 00 1.06K 01 2.60K 01 l a
2. A VG RMLMASK NATK TON PERIOD UCI/SKC 8.28K-01 1.33M 00 >

i PKRCKNTAGK OF T.S. LIMITS CRITICAL ORGAN DOSK NATK  % 4.43K-03 8.69K-03 TOTA L BOD Y DOSK NA TM  % 2.46K-02 3.641-02 SKIN DOSK NA TE

  • 8.02K-03 1.32K-02 l

b 1

TABLE 18 Attachmont 1

. Pega 2 of 6 EFFLURNT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/8G TO 12/31/86 GASKOUS EFFLUENTS-MIXRD-MODE RELEASES CONTINUOUS MODE DA TCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUAR 7RR QUARTER QUAR 7RR

1. TISSION & ACTIVA TION GASES KR-85 CI 0.00E-01 0.00E-01 1.82N-01 0.00E-01 KR-85M CI 0.00E-01 0.00R-01 1.36K-04 0.00K-01 KH-87 CI 0.00H-01 0.00E-01 0.00E-01 0.00K-01 KR-88 CI 0.00R-01 0.00E-01 0.00K-01 0.00K-01 XN-233 CI S.32H-01 4.46E-01 2.9]E-01 2. 57E 00 XE-135 CI 9.24N-02 1.578-01 5.368-03 1.98E-02 XH-135M CI 0.00K-01 0.00E-01 0.00H-01 0.00K-01 XK-130 CI 0.00E-01 0.00N-01 0.00E-01 0.00R-01 XE-13]M CI 0.00H-01 1.45H-03 2.39N-02 1.75N-02 AR-41 CI 0.00E-01 0.00K-01 2.975-03 0.00N-01 XE-133M CI 0,00N-01 6.SGN-03 L'. 23N-03 2.19H-02 TOTAL FOR PNRIOD CI 9.25N 01 6.12N-01 5.00R-01 2.62E 00
2. 10DINNS I-131 CI 9.76N-08 H.SlE-OH 6,7HH-06 1.29N-05 l-133 CI 1.47N-07 1.H35-08 6.77N-OH 3.02N-06 1-135 CI 0.00N-01 0.00N-01 0.00N-01 1.H2E-07 l-132 CI 0.00K-01 0.00K-01 0.00N-Of 4.03N-08 TOTAL FOR PKH10D C1 2.45N-07 1.03N-07 6.H5K-06 1.62N-05
3. PARTICUL A THS SR-H9 CI 0.00N-01 0.00N-01 0.00N-01 0.00N-01 SR-90 CI 0.00K-01 0.00K-01 0.005-01 0.00K-01 CS-134 CI 3.66N-OH 1.62H-OH 0.00N-01 0.00H-01 CS-137 CI 2.42H-07 1.24H-07 2.46N-OH 9.67K-09 BA-140 Cf H.02N-09 0.00N-01 0.00H-01 0.00N-01 LA-140 Cl 0.00N-01 0.00N-01 0.00K-01 0.00K-01 CH-51 Cl 0.00N-01 0.00N-01 0.00K-01 0.00H-01 CO-57 CI 1.17N-0!t 0.00H-01 0.00N-01 0.00N-01 CO-58 C1 3.32N-0J 0.00N-01 1.4HH-06 0.00H-01 CO-60 CI 9.44N-07 5.3HH-07 1.20N-07 0.00H-01 SH-75 Cl 1.77N-OH 0.00N-01 0.00N-01 0.00N-01 RB-HH CT 0.00K-01 0.00N-01 4.97N-05 9.H9N-06 SR-92 Cl 0.00H-01 0.00H-01 6.69N-OH 0.00N-01 TM-132 CI 0.00H-01 0.00H-01 0.00H-01 0.00H-01 CS-13H Cl 0.00N-01 0.00N-01 0.00N-01 0.00N-01 MN-54 Cl 0.00N-01 0.00N-01 0.00K-01 0.00N-01 CH-139 Cl 0.00N-01 0.00N-01 0.00M-01 0.00H-01 ND-147 Cl 0.00N-Of 0.00N-01 0.00N-01 0.00N-01 CH-141 Cl 0.00N-01 0.00H-01 0.00N-01 0.00R-01

TABLR 2C Attachm:nt 1

' P g) 3 of 6 NFFLUMNT AND WASTN DISPOSAL SEMIANNUAL RNPORT PERIOD: 7/ 1/86 TO 12/31/86 GASROUS KffLUNNTS-GROUND LEYFL RRLNASKS CONTINUOUS MODN BA TCll MODN SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTRH QUARTER QUARTER

1. FISSION & ACTIVA TION OASNS KR-H6 CI 0.00R-01 0.00N-01 0.00N-01 0.005-01 KR-85M CI 0.00N-01 0.00N-01 S.92H-03 0.00R-01 RR-87 CI 0.00R-01 0.00N-01 4.01H-03 0.00N-01 KR-88 CI 0.00N-01 0.00H-01 1.02H-02 0.00K-01 XK-133 CI 0.00H-01 1.USN 01 2.23N 00 6.915 00 XK-135 CI S.69K 00 U.69H 00 8.41N-02 2.35H-01 XK-135M Cl 0.00N-01 0.00N-01 0.00N-01 0.00R-01 XH-138 CI 0.00H-01 0.00R-01 0.00K-01 0.00R-01 XN-131M CI 0.00R-01 0.00R-01 1.03H-02 0.005-01 AR-41 Cl 0.00R-01 0.00H-01 S 78N-01 0.00H-01 XN-133M CI 0.00N-01 0.00N-01 2. 2 7N-04 0.00N-01 TOTAL FOR PRRIOD CI 6.698 00 2. 72H 01 2.92H 00 6.18N 00
2. 10DINKS I-131 CI P.42K-05 4.02K-04 4.73N-05 5.22N-05 I-133 CI 1.77N-04 1.60K-03 1.66H-05 3.49N-05 I-136 CI 0.00N-Of 4.96N-04 0.00N-01 0.00N-01 1-132 CI 0.00H-01 2.52H-04 4.608-07 1.74H-05 TOTAL FOR PERIOD CI 2. 61N-Osl 2.68H-03 6.43N-05 1.04K-04
3. PARTICULA THS SR-il9 CI 0.00N-01 0.00N-01 0.00N-01 0.00N-01 SR-90 Cl 0.00H-01 0.00N-01 0.00N-01 0.00H-01 CS-134 Cl 7.6HH-05 4.40K-05 3. 0 7N- 0 7 4.60H-06 CS-137 C1 4.10N-04 2.31H-04 l.09H-05 3.00K-05 BA-140 CI 0.00H-01 0.00N-01 0.00H-01 0.00N-01 LA-140 CI 0.00K-01 0.00N-01 0.00N-01 0.00N-01 CH-61 Cl 0.00N-01 0.00N-01 4.2HH-07 0.00N-01 CO-57 Cl 0.005-01 0.00H-01 1. 66N-Oli 0.00H-01 CO-6H CI 3. 3HK-Oli <l.27N-05 6.73H-06 9.HJH-06 CO-60 Cl 2.17N-04 I.H7K-04 4. 4HH-Oli 2.76N-05 SN- 75 Cl 0.00N-0! 0.00N-01 0.00N-01 0.00N-01 RB-HH Cl 0.00N-01 0.00N-Ol 9.lilN-03 0.00N-01 SR-92 Cl 0.00H-01 0.00N-01 0.00N-01 0.00N-01 TM-132 Cl 0.00N-Of 0.00N-01 2. 0HH-Oli 0.00N-01 CS-ISH Cl 0.00H-01 0.00N-01 1.64N-03 0.00H-01 MN-54 Cl 1. 95N-Oti 0.00N-01 1.0lN-07 0.00N-01 CH-139 Cl 0.00N-01 7.UON-07 0.00N-01 3.58H-07 NO-147 Cl 0.00H-01 0.00N-01 0.00K-01 1.H2N-OH CH-141 Cl 0.00N-01 0.00N-01 0.00N-01 7.92N-07

htt: chm *nt 1 TABLK 2A P g) 4 of 6 FFFLUMNT AND WASTR DISPOSAL SKMIANNUAL RKPORT PKRIOD: 7/1/86 TO 12/31/86 LIQUID KrFLUMNTS-SUMMATION Of ALL RKLKASKS SU:RY POWKR STA TION UNITS 162 UNIT TNIRD QTR. YOURTH QTR.

  • MS T. KRROM A. FISSION AND ACTIVATION PRODUCTS
1. TOTAL MULKASK (NOT INCLUDING THITIUM, GASKS, ALPHA) CI 2.65K 00 1.72K 00 2.60K 01
2. AVO DIL. CONC. DURING PERIOD UCI/ML 3.83K-09 4.09K-09
3. PRMCNNT Of APPLICARLK LIMIT  % 1.24K-02 2.92K-02 I

D. THITIUM

1. TOTAL HKLKASK CI 1.56K 02 1.21K 02 2.50K 01
2. A VG DIL. CONC. DUNING PKRIOD UCI/ML 2.34K-07 2.90K-07
3. PERCKNT Of APPLICABLK LIMIT  % 7.79K-03 9.65K-03 C. DISSOLYKD AND KNTRAINKD GASKS
1. TOTAL NKLKASK CI 7.67K-02 H.60K-02 2.50K 01

, 2. A VG DIL. CONC. DURING PMMIOD UCI/ML 1.16K-10 2.06K-10 3 PKMCKNT OF APPLICARLM LIMIT 8.76K-05

  • 1.03K-04 D. GROSS ALPHA HADI0 ACTIVITY
1. TOTAL HKLKASK CI H.2HK-05 5.54K-06 2.50K 01 i

K. YOLUNK Of WASTM HKLMASKD (PRION TO DILUT10N) LITKHS 6.79K 07 3. 7HK 07 3.60K 00 P, VOLUNK Of DILUTION WA TKH USKD DURING PKN10D LITERS 6.66K ll 4.19K 11 3.60K 00 ,

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TABIN 2B Att: chm:nt 1 Paga 5 of 6 NFFLUNNT AND WASTN DISPOSAL SEMIANNUAL RNPORT b PRR1001 7/ 1/86 TO 12/31/06

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LIQUID KFFLUENTS CONTINUOUS MODN BA TCH MODN SURRY POWNH STA TION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUANTKH QUARTHH QUARTNH QUARTHR SR-89 CI 0.00N-01 0.00K-01 0.00H-01 0.00H-01 SH-90 CI 0.00N-01 0.00H-01 1.5HK-04 0.00K-01 CS-134 CI H.95H-05 3.32H-03 1.32K-01 1.94H-01 CS-137 CI 3.11H-03 2.14N-02 4.64N-01 6. 4 7N-01 1-131 Cl 0.00H-01 0.00K-01 1.40K-03 1.2HH-02 C0-5H C1 4.22K-05 4.00N-05 7.49N-01 2.3GN-01 CO-60 CI 0.00H-01 3. ink-03 6.HHR-OL 2.97N-01 FN-59 Cl 0.00K-01 0.00K-01 3.0lN-03 1.64K-03 ZN-65 CI 0.00N-01 0.00H-01 3.97N-04 4.35H-05 MN-54 C1 0.00H-01 0.00K-01 2.07K-02 7.91H-03 CH-51 CT 0.00N-01 0.00N-01 2.01H-01 5.50N-02 ZR-95 CI 0.00E-01 0.00N-01 1.96N-02 4. 67K-03 NB-95 Cl 0.00N-01 0.00N-01 3.37H-02 0.62K-03 MO-99 CI 0.00N-01 0.00N-01 5.56K-05 1.52H-04 TC-99H CI 0.00K-01 0.00H-01 9.22K-06 5 HIN-04 BA-140 Cl 0.00N-01 0.00N-01 2.4GN-05 7.34N-03 LA-140 Cl 0.00K-01 0.00H-01 0.00K-01 2.33N-04 CH-141 Cl 0.00N-01 0.00K-01 3.76N-04 0.005-01 CO-57 Cl 0.00K-01 0.00R-01 1.H9H-03 5.06H-04 SD-125 Cl 0.00N-01 0.00N-01 1.72K-01 H.60H-02 AG-110M Cl 0.00N-01 0.00K-01 5.50K-03 2.57N-03 SH-92 Cl 0.00N-01 0.00N-01 2.44K-03 H.53N-04 HU-103 Cl 0.00N-01 0.00N-Of 7.52N-03 5.32K-04 CH-144 Cl 0.00N-01 0.00K-01 H.74N-03 1.3]N-03 NO-147 Cl 0.00H-01 0.00N-01 4.62N-05 7.H7K-06 SB-124 CJ 0.00N-01 0.00N-01 1.44N-02 1.43N-02 NA-24 CI 0.00N-01 0.00K-01 1.93H-02 9.37N-04 1-133 C1 0.00K-01 0.00N-01 2.57N-03 9.02H-03 1-135 Cl 0.00H-01 0.00N-01 3 H4N-04 1.02K-03 TN-132 Cl 0.00N-01 0.00N-01 4.69N-05 6.94N-06 T-132 Cl 0.00N-01 0.005-01 0.00N-01 2.41H-04 W-1H7 Cl 0.00K-01 0.00N-01 0.00N-01 5.95H-04 NA -22 Cl 0.00N-Of 0.00N-01 0.00N-OL 2.9HK-06 FN-SS C1 0.00H-01 0.00N-01 0.00N-0l 9.64N-02 TOTAL l'OR PNH100 Cl 3.24N-03 2.79K-02 2.00N 00 1.69N 00 XN-133 Cl 0.00N-01 0.00H-01 5.17N-02 4.13N-02 XH-130 Cl 0.00N-01 0.00N-01 2.44N-02 4.3tN-02 AH-41 CI 0.00N-01 0.00N-01 6.56N-05 U.15H-05 NH-H7 Cl 0.00N-01 0.00N-01 3.19H-06 0.00N-01 XN-130M CI 0.00N-01 0.00N-01 2.22N-04 1.52N-03 NH-HSM Cl 0.00N-01 0.00N-Of 3.05N-05 0.00N-01 ,

NH-HH Cl 0.00N-01 0.00N-01 6.13N-05 2.99N-05 XN-133M CI 0.00H-Of 0.00K-01 1.0$N-04 1.H4H-05

Attachment I Page 6 of 6 TABLE 3 l EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT

! SOLIO WASTE AND IRRA0!ATED FUEL SHIPMENTS ,

l PER!00 07/01/86-12/31/86 SURRY POWER STATION A. SOLIO WASTE SHIPPED OFFSITE FOR BURIAL OR O!$POSAL(Not irradiated fuel) t

, 1. Type of waste Unit 6-month Est. Total

! Period Error,%  ;

a. Spent resins, filter sludges, evaporator m8 2.58t+01 5.00E+00 '

bottoms,etc. Ci 6.40E+02 3.00E+01

b. Dry compressible waste, contaminated m3 3.02E402 6.00E+00 j equip., etc. C1 1.00E401 3.00E+01 ,

l c. Irradiated components, control m2 0.00E+00 0.00U00  !

l rods,etc. Ci 0.00D00 0.00E+00  !

d. Organic waste (i.e. oil and scintillation m3 0.00E+00 0.00E+00 i fluid) Ci 0.00E+00 0.00E+00 }

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2. Estimate of major nuclide composition (by type of waste) i i
a. Cs-137  % b 05E+01 l

Co 60  % 2.20E+01 i

l Cs-134  % 1.47E+01 j Ni-63  % 7.10E+00 [

Fe-55  % 2.40E400 t

b. Cs-137  % 3.03E+01 Co 60  % 2.24E+01 ,

i Fe 55  % 1.55E+01 t Cs-134  % 1.31E+01 C0 58  % 1.19E+01 NI 63  % 4.70D00 i Co 144  % 1.10E+00  !

Nb 95  % 1.10L+00  :

, c.  % 0.00E+00 l

d.  % 0.00E+00 l l I 3. Solid Waste Otsposition ,

Number of Shipments Modo of Transportation Destination 17 7Fu3 ifalnwe11,5C [

i B. IRRA0!ATEDFUEL$HIPMENT(Ofsposition)

Number of Shipments Modo of_ Transportation Destination U ,

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Attachm:nt 2 P go 1of1 ANNUAL AND QUARTERI,Y DOSI:S

!.! QUID G ASEOUS Total llody Thyroid GI-LLI Gamma Ilota Thyroid (mRom) (mRom) (mRom) (mrad) (mrad) (mRom)

Ist Qu rter 1.02 E-2 1.53 E-2 2.61 E-2 6.79 E-l 1.91 C+0 2.40 E-2 2nd Qu:rtor 1.41 E-2 2.11 E-2 7.07 E-2 4.32 E-1 1.28 E+0 9.64 E-3 3rd Qu:rter 6.90 E-3 1.67 E-4 6.56 E-2 3.27 E-2 3.49 E-2 4.46 E-4 4th Quarter 1.17 E-2 1.78 E-3 3.37 E-2 4.90 E-2 9.08 E-2 1.19 E-3 Annual 4.29 E-2 3.03 E-2 1.96 E-l 1.19 C+0 3.32 C+0 3.53 E-2 l

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- Att: chm:nt 3 P:qa 1 of I Hl: VISIONS TO OITSITI: DOSI: CAI.CUI.ATION M ANtJ AI, (ODCM)

Thoro woro no changos to the Offstto Doso Calculation Manual during the portod of July 1,1986 through December 31,1986, i

- Att: chm:nt 4 P g] l of 1 REVISIONS TO TIIE PROCPSS CONTROL PROGR AM (PCP) l Thoro woro no changes to the Process Control Program during the portod of July,1986 through l December 31,1986, 1

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. Attecl$ent 5 ' '

P ge 1of1.-

MAJOR CHANGES TO R ADIOACTIVE LIQUID, GASEOUS AND ,

50 LID WAorr. TREATRssa a 3reTsnN  :

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There were no major changes to Surry's Radioactive Liquid, Gaseous or Solid Waste Tre,itment -

Systems during the period of July 1,1986 through December 31,1986.

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Att:chment 6 ,

  • 3 Page 1of1 i INOPER ABILITY OF R ADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONff0 RING INSTRUMENTATION Technical Specification 3.7.t.t2 roouires the Semi-Annual Report to includo an explanation why monitors required by Techn1N1 Specification Tablos 3.7-5(a) and 3.7-5(b) which wero determined inoperablo, woro not returned to operablo status within 30 days.

Two monitors requiro explanation under this critoria for the porlod of July 1,1986 through December 31.,1986. They are the Component Cooling Servico Water Monitor and the Wasto .

Gas lloldtip System Cxplosivo Goa Oxygon Monitor.  !

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> 1. Tho Coraponont Co)11ay Sorvico Water Monitor (RM-SW-107) continuos to bo inoperablo as describod in d o pec /lous Somi-Annual Report. A report from Engincoring and Constructior. (NP 1237), suggesting attornato solutions to the problom,was recotved by station engincoring at th9 ond of Docombor,1986. The report is currontly boing ovaluated by station enginocring, eporatfons and health physics.

Grab sampling, roN! rod by Tcbhr 3.7-5(a) when the monitor is out of servico, has boon poriormod sinco th9 monitor bacamo inoporablo. Tho grab sampling will continuo until '

this mottor la resolvoi, 4 L Ho,5facomont of the Wasto 0,se lloldup System Oxygon Monitors and modification of the samplo linos woro comploted in August of 1986. Ilowevor, normal oporation of tho Tystem causnd alarm ahnunications in the control room. Station engineering has provided plans for inodification of the annunicator to provont alarm. The modification should tio completed in oarly 1987, 1

Grab sampling as requirod by Technical Spocification Tablo 3.7-5(b) when the monitor is out of steviro, has boon porformod since the monitor became inoporable. Grab sampling will continuo to satisfy the monitorina requirements until the modification has boon complotod.

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' ' ol UNPLANNED RELEASES l .

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- ,There . has been no Unplanned Liquid or Gaseous Releases that exceeded Technical

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1 ' Specific' a tion 3.ll.A.I.a or 3.ll.B.I.a during the perled of July 1,1986 through December

'31, 1986.

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g k VINOINIA ELECTRIC AND Powna COMPANY Ricitwoxn,VIHOINIA 20261 February 27, 1987 Vaca Punessant Nect. man DrumArrone U. S. Nuclear Regulatory Commission Serial No.87-058 Attn: Document Control Desk N0/PML:vlh Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlement VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the Surry Power Station Semi-Annual Radioactive Effluent Release Report for July 1, 1986 through December 31, 1986. The- report, submitted pursuant to Surry Power Station Technical Specification 6.6.B.3, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the previous six months, as outlined in Regulatory Guide 1.21, Revision 1, June 1974.

Very truly yours, W. L. Stewart Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, CA 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station 7E46

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