Text

Responds to 790502 & 0831 Ltr Proposing to Amend Tech Specs for Environ Monitoring & Radiological Effluent Sys.Comments & marked-up Copy of Proposed Changes Encl.Program for Solidification & Revised Amend Should Be Sent in 30 Days
	ML19309H038
Person / Time
Site:	Indian Point
Issue date:	04/04/1980
From:	Schwencer A; Office of Nuclear Reactor Regulation
To:	Berry G; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
References
	NUDOCS 8005080217
	Download: ML19309H038 (78)
	v • d • e

{{#Wiki_filter:- _ _ _ _ _ _ ILCL) 8005080 237 g.. c,,, [ o UNITED STATES 3,,f i NUCLEAR REGULATORY COMMISSION ,E WASHINGTON, D. C. 20555 / April 4,1980 Docket No. 50-286 Mr. George T. Berry, Executive Director Power Authority of the State of New York 10 Columbus Circle New York, New York 10019

Dear Mr. Berry:

By letters dated May 2, 1979 and August 31, 1979, you proposed to amend the existing Technical Specifications of Indian Point, Unit No. 3, for the radiological effluent and environmental monitoring systems, to implement the provisions of Appendix I to 10 CFR Part 50 and the provisions approved by the Regulatory Requirements Review Committee. Our review of the proposed Radiological Effluent Technical Specifications for Pressurized Water Reactors, NUREG-0472, Revision 2, July 1979. Based on our review thus far, our comments and marked-up copy of your proposed radiological effluent Technical Specifications are attached as Enclosures 1 and 2, respectively. The proposed amendment did not include the required Technical Specifications on solid radioactive waste, liquid sampling, system operability, effluent dose limitations, explosive gas mixtures, curie content in outdoor liquid holdup tanks, and admini-strative controls. You have not submitted a Process Control Program (PCP) for solidification of radioactive wastes for Indian Point, Unit No. 3. Although, as you pointed out in your August 31 letter, the burial sites do not require that waste be solidified, they do have requirements on maximum water content in the packages they accept and incoming shipments will be inspected against these requirements. Therefore, a PCP is required to assure that waste leaving the site is acceptable. (The PCP is referenced in your proposed Section 3.11.3.1, submitted by your letter dated May 2, 1979.) We are amenable to discussing your views on solidification. Therefore, provide within 30 days, revised Technical Specifications based on our comments, and a PCP. To clarify our comments on your proposed amendment, a meeting or conference call may be necessary. Sincerely,, i $(lLO W "' [ A. Schwencer, Chief l Operating Reactors Branch #1 Division of Operating Reactors

i . O o Mr. George 1. Berry Power Authority of the State of New York April 4, 1980 I

Enclosures:

1. ETSB Comments 2. Marked-up Proposed Tech Specs cc: w/ enclosures See next page I i ) I e I i l 4 l i a l i . -.. ~.

Mr. George T. Berry Power Authority of the State of New York April 4,1980 cc: White Plains Public Library Mr. J. P. Bayne, Resident Manager 100 Martine Avenue Indian Point 3 Nuclear Power Plant White Plains, New York 10601 P. O. Box 215 Buchanan, New York 10511 Mr. Charles M. Pratt Assistant General Counsel Mr. J. W. Blake, Ph.D., Director Power Authority of the Environmental Programs State of New York Power Authority of the 10 Columbus Circle State of New York Ned York, New York 10019 10 Columbus Circle New York, New York 10019 Anthony Z. Roisman Natural Resources Defense Council Theodore A. Rebelowski 917 - 15th Street, N.W. Resident Inspector Washington, D. C. 20005 Indian Point Nuclear Generating U. S. Nuclear Regulatory Commission Dr. Lawrence D. Quarles Post Office 87x 38 Apartment 51 Buchanan, New York 10511 Kendal at Longwood Kennett Square, Pennsylvania 19348 Ms. Ellyn Weiss Sheldon, Harmon and Weiss Mr. George M. Wilverding 1725 I Street, N.W. Licensing Supervisor Suite 506 Power Authority of the Washington, D. C. 20006 State of New York 10 Columbus Circle New Yr K, New York 10019 Mr. P. W. Lyon Manager - Nuclear Operations Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 i l l l

Comments on Indian Point Nuclear Plant, Unit No. 3 i Radiological Effluent Technical Specifications (RETS) 1. We have reviewed the subject radiological effluent Technical Specifications as submitted by the licensee, and have marked them up to reflect a document which, subject to resolution of these comments, is acceptable to us. We have, in a number cf cases, changed the licensee's wording, content, and table format to make them conform to the contents of NUREG-0472, Rev. 2. Specific changes made may require subsequent discussion. 2. In Section 1.0, DEFINITIONS, modify the definitions for SOLIDIFICATION and PROCESS CONTROL PROGRAM and add definitions for PURGE-PURGING, VENTING, and DOSE-EQUIVALENT I-131 as shown in markup. 3. The following specifications, as numbered in the markup, are not required in the RETS: 4.3.3.8.2, 4.3.3.9.2, 4.11.1.1.6, 4.11.1.1, 4.11.1.2, 3.11.1.1 ACTION b, 3.11.2.1 ACTION b, 4.11.2.1.3, 4.11.2.2.2, 4.11.2.3.2, 4.11.3.3. 4. In Table 3.3-11, perform the following: a. Indicate capability for monitoring or sampling the Turbine Building (Floor Drains) Sumps Effluent Line, and indicate provisions for termination of releases via this pathway in accordance with NUREG-0472. b. Indicate capability for monitoring gross radioactivity in your Service Water System and Component Cooling Water Systems Effluent Lines in act.s ance with NUREG-0472. c. Indicate capability for measuring flow rate in your Discharge Canal in accordance with NUREG-0472.

. d. Modify the Table, including the ACTION statements, as snown in markup, e. In Tables 3.3-11 and 4.3-11 you have listed Radioactivity Recorders and their corresponding requirements, with notation to the effect that these are not applicable unless used to perform an alarm / trip action. If they are not used for this function, but as process instrumentation only, then delete these items from the tables, otherwise delete the qualifying notation. 5. In Table 4.3-11, modify the table as shown in markup (including the Table Notation) and indicate surveillance requirements for the instrumentation dis-cussed in comments 4a, b, and c above, in accordance with NUREG-0472. 6. In Table 3.3-12, perform the following: a. Indicate capability for monitoring Waste Gas Holdup System effluent releases, and capability for measuring effluent flow rate, in accordance with NUREG-0472. Indicate provisions for alarm and automatic termination of release. b. Indicate capability for monitoring the Condenser Evacuation System effluent releases in accordance with NUREG-0472. c. Indicate capability for alarm and automatic termination of releases from the Containment Purge System in accordance with NUREG-0472. d. Indicate capability for monitoring Steam Generator Blowdown Vent System effluent releases in accordance with NUREG-0472. e. Modify table, including astericked notation and ACTION statements, as shown i in markup.

, 4 I 7. Modify Table 4.3-12 as shown in markup (including Table Notation) and indicate surveillance requirements for the instrumentation discussed in cannents 6a, b, i c, and d above, in accordance with NUREG-0472. 8. Figure 3.11-1 is unacceptable. Provide maps clearly defining the site boundary and restricted area boundary, and in accordance with instructions for Figures 5.1-3 and 5.1-4 of NUREG-0472. I 9. Tables 3.3-12 and 4.3-12 should be made consistent with each other in terms of the instrumentation listed. l

10. Modify Specifications 3.3.3.8 and 3.3.3.9, as shown in markup.

11. In Tables 3.3-12 and 4.3-12, indicate which instruments have alarm and/or automatic termination capability in accordance with NUREG-0472.

12. Modify Specification 3.11.1.1 and its corresponding ACTION, SURVEILLANCE REQUIREMENTS, and BASES as shown in markup.

13. Modify Table 4.11-1, including the Table Notation, as shown in markup.

14. Modify Specification 3.11.1.2 and its corresponding ACTION and BASES, as shown in markup.

I o

15. Modify Specification 3.11.1.3 and its corresponding ACTION and BASES, as shown specified time interval) in markup; and add the following: (witi:

6 SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days in accord'nce with the ODCM. 4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least minutes at least once per.92 days unless the liquid radwaste system has been uTTTized to process radioactive liquid effluents during the previous 92 days. i ( l

16. Modify Specification 3.11.2.1 and its corresponding ACTIONS, SURVEILLANCE REQUIREMENTS, and BASES as shown in markup.

17. Modify Table 4.11-2, including the Table Notation, as shown in markup. Note that the design dose objectives of Specifications 3.11.2.2 and 3.11.2.3 must be reduced if Turbine Building gaseous effluent sampling is not provided.

18. Modify Specifications 3.11.2.2, 3.11.2.3, and 3.11.2.4, and their corresponding ACTIONS, SURVEILLANCE REQUIREMENTS, and BASES as shown in markup.

19. It is the Staff's position that in hydrogen-rich waste gas holdup systems which are not designed to withstand a hydrogen explosion, continuous monitoring (with automatic control features) of both hydrogen and oxygen is desired. We have modified your Specification 3.11.2.6 and Tables 3.3-12 and 4.3-12 of the markup to reflect this position. If you do not intent to comply with this, provide justification.

. 20. Provide a specification for curie content in outdoor liquid holdup tanks contain-ing potentially radioactive fluids, i.c., Specification 3.11.1.4 of NUREG-0472.

21. Modify Specification 3.11.2.7 as shown in markup.

22. Modify Specification 3.11.3.1 as shown in markup. Note that Specification 6.14 is referenced but has not been submitted for our review.

23. Provide a specification for compliance with 40 CFR 190, i.e., Specifica-tion 3.11.4 in markup.

24. In Specification 6.5.1.6 add the following Plant Operating Review Connittee responsibilities: k. Review of every unplanned onsite release of radioactive material to ~ the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the correc-tive action to prevent recurrence to the (Su,erintendent of Power Plants) and to the Safety Review Committee. 1. Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems. 25. In Specification 6.5.2.8 add the audit requirements shown in the markup. 26. In Specification 6.8.1 add the activities shown in the markup.

27. Modify Specifications 6.9.1.6, 6.9.1.7, 6.9.1.11, 6.13, and Table 6.9-2 as shown in markup.

l

. 28. Provide specifications for the PROCESS CONTROL PROGRAM and for MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS, i.e., Specifications 6.14 and 6.15 in markup.

29. Regarding the ODCM:

a. The contents of the ODCM are not in accordance with NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," in that there is too much superfluous information such as your Environmental Technical Specifications (which will be superceded by the Radiological Effluent Technical Specifications), memoranda of understanding between Con Edison and PASNY, and plant procedures, b. Insufficient information is presented regarding your methodology and parameters for determining effluent monitor setpoints, i.e., (AP-11): 1. All effluent pathway monitors must be discussed. 2. How is MPC,"obtained"? 3. How do you assure that once a liquid effluent monitor setpoint has been calculated, predicated on a given dilution flow rate, and release is initiated, that dilution flow won't change in an unconservative manner? 4. How are your Permissable Discharge Rates for gaseous effluents established? 5. Do monitor alarms and trips occur at the same setpoints? 6. Explain the basis for the first equation on pg. 1-39.

Enclosun 2 I ATTACHMENT E ( PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO RADIOLOGICAL EFFLUENTS REGULKiORY 00CKE FLE C t POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 APRIL 30, 1979 I. { Baikd*h9of'"#' GE&Ela? e

O p-1.0 DEFINITIONS CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHA!niEL FUNCTIONAL TEST. THE CHA!niEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentationchanne1[measuringthesameparameter. CHANNEL FUNCTIONAL TEST 1.11 A CHANNEL FUNCTIONAL TEST shall be Analog channels - the injection of a simulated signal into / a. the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions. b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions. SOURCE CHECK 1.29 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. PROCESSCONTROLPROGRAM(PCP) COMA %e. 1.30A K PROCESS CONTROL PROGRAM (PCP) shall h: th: m:nt:1 :: eJ A 4per= ting preerdu::: detailing tM pregrr ef(s'ampling, analysis, andhhatle-2ti:n.;ithiEgichthesolidificationofradioactivewastes datemM

21

from liquid systems rill be assured. 3 v i i DOSE EQUIVALENT I-131 5 / 1.19 The DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / I gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power v and Test Reactor Sites." x l-1

1.0 OETI::ITIONS (Continued) i. SOLIDIFICATION 1.31 SOLIDIFICATION :: : quired by th "'

4 M irri'irrtiene snall be the conversion of radioactive wastes from liquid systems to a* 4.

k.qeuws q T immobilized solid with definite volume and shape, bounded by a stable 9 surface of distinct outline on all sides (free-standing). Lf OFFSITE DCSE CALCULATICN MANUAL (ODCM)_ T 1.32 An OFFSITE DOSE CALCULATION MANUAL (ODCM) shall be a manual containing the methodology and parameters to be used in the calculation of offsite dc,ses due to radioactive gaseous and liquid effluents and { in the calculation of gaseous and liquid effluent monitoring instrumentation s-h alarm / trip setpoints. b GASEOUS RADWASTE TREATMENT SYSTEM I 1.33 A GASEOUS RADWASTE TREATMENT SYSTEM is a system designed and 0, installed to reduce radioactive gaseous effluents by collecting primary 5 coolant system effgases from the primary system and providing for [. delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. Dj VENTILATION EXHAUST TREATMENT SYSTEM 'o j 1.34 A VENTILATICN EXHAUST TREATMENT SYSTEM is any system designed f and installed to reduce gaseous radioiodine or radioactive material in g particulate form in effluents by passing ventilation or vent exhaust gases through charcoalAahoeaneese and/or HEPA filters for the purpose of removing lodines or particulates from the gaseous exhaust stream ~ prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluent. Engineered Safety Feature (ESP) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. g-PURGE - PURGING j 1.35 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration g or other operating condition, in such a manner that replacement air or gas is } required to purify the confinement. \\ VENTING 1.36 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or / \\ other operating condition, in such a manner that replacement air or gas is not f provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. 3 1-2

il( C*3*I 1.2 FFIOUENCY 1:OTATION_ NOTATION FREQUENCY At least once per 12 hours. S At least once per 24 hours. D At least once per 7 days. W At least once per 31 days. M Q At least once per 92 days. At least once per 184 days. SA At least once per 18 months. R S/U Prior to each reactor startup. Prior to each release. P N.A. Not applicable. l-3 7

.:n: :I:~!:d:0::

I mod:Tof.id G g EADICACTIVE LIQU:5 ETT;~JENT,I!!STR'.'."E::!ATI :* ,i. is LIMITI:;0 CC::DITIc:: TC7 C FIFJ, TIC: 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-11 shall be CPE?JaLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. "Tb., ainau / trip setpoinh of *se, chmts skatt be. da.te.rned. t at.ardasu, ai+k. N. OFFst11E Dos 6 CM.cuLAhod MAdum (ooQ. APPLICABILITY: ir E M - in T2hl: 2.2 11. Ik AQ ties. ACTION: With a radioactive liquid effluent monitoring instrumentation a. channel alarm / trip setpoint less conservative than a value which will ensure that the limits of 3.11.1.1 are met, suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable. less nae. h 8*ini*uw Apinr of crT;rcAradioacpiveliquideffluentmonitoring b. With en: instrumentation channels in perchl:, take the ACTION shown NM in Table 3.3-114 c.

iLL onc cr

r W -'rtiv liquid cfflucc.; nc. Leasug inctrur: ' ticn channel: in;p rahic Leiec.d the cratinuaticn perica spc.ifi d ir th; w 12malu ACTIC;; state::nt, pr:p:re-and ruhmit tc th: Ccr. mission within "" beurr 2fter the 7.CTIC:? linit, pursuant tc Op;cificetica 5.0.2, ; Op cial

" pcrt, i. lieu cf ac.j ether report, which id:ntific: the caus:(c) for ca:::dic.g t'..c li-.it (s), 3 fic.es corrcctiv; action; tc Ec taken t: _2 tor epershility, and pr;vid:: an -asti.matcd dat: for return to C :rAOL" 5;stua af -Lu tu n .. cat tion ^cnnel(:). Offlucnt rcle c. .5 .;; thic pathucy may centinue beyond thc '.CTIO:: tir c 1. 4.. L., = m. Le she en:1ysi: and nuc.itsi ar csadition cf the e,mimhic 7.CTIC:: a4 m...m c.t, m r SURVEILLANCE REQUIREMENTS 0.2.2.0.1 The ::tpcint: ch:11 5: d.Lu....l..ud 2d reecrd:d in creerd:n : "ith prc :durcs. i 4.3.3.8.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHA '.iEL CHECK, SOURCE CHECK, CHANNEL CALIBFATION, and CHANNEL FUNCTIONAL TEST operations during th; : OOCC and at.the frequencies shown in Table 4.3-11 ~ 4af L e4 ( 4.3.3.8.8 Records - Records shall be maintained, in accordance with 43 the ODCM, of all radioactive liquid effluent monitoring instrumentation V [k available for review to ensure that the limits of Specification 3.11.1 3 alarm / trip setpoints. Setpoints and setpoint calculations shall be / (aremet. v --- D**]D *D'WRj\\,(4' 3/4 3-44 ssN wJ

E (? BASES 3/4. 3.3.8 RADICACTIVE LIOUID EFFLt'C:7 !!!5TR"ME :TATIC:: The radioactive liquid effluent instrunentation is provilad to mer.itor and control, as applicable, the releases of radioactive materials in liquid ef fluents during actual or potential releases. The alarm / trip setpcints for these instruments shall be calculated in accordance with methads in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The CPERASILITY and use of this instrumentation is consistent with the requirements General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. 9 f 3/4 3-45 l

e, TABLE 3.3-11 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMEffrATION MINIMUM CitANNELS OPERABLE _. '""'_!C."

,ITl -

ACTION INSTRUMENT 1. Gross Radioactivity Monitors Providing Automatic Termination of Release c. Liquid Radwaste Effluent Line 1 -f il-18 -( 1)- 20 b. Steam Generator Blowdown 1 Effluent Line O

TABLE 3.3-11 (Continued) RADIOACTIVE LIOUID EFFLUEt3T mot 3ITORIt3G IIISTRUMEt3TATIOt3 MINIMUM CIIAt3NELS INSTRUMENT OPERABLE -APPLICARILITY-AC"TIOll 2. Flow Rate Measurement Indicators & Recorders ** Liquid Radwaste Effluent Line 1 -fit-21 a. b. Steam Generator Blowdown Effluent 1 -(11-21 Line 3. Radioactivity Recorders *** a. Liquid Radwaste Effluent Line 1 -fif-23 a b. Steam Generator Blowdown Effluent Line 1 -( l)- 4324 u w 4 '. Tank Level Indicating Devices (for tanks outside plant buildings) a. Refueling Water Storage Tank 1 ilt-22 b. Primary Water Storage Tank 1 -(l) 22 c. Monitor Tank 31 1 -(l )- 22 d. Monitor Tank 32 1 41F 22 +^7 + curves -may-be-utilized-to-estimate-flow-or-limiting-orifice,--in-such-cases,-actimtetement-21-is rat 2cqa h co' Required only if alarm / trip set point is based on recorder-controller.

i TABLE 3.3-11 f. (Continued) TABLE NOTATION _ (l' Carin; reles:: by th pathucy_ 0"Ir: LO sh:14 b OF PACLE -d i-

ntinueur, uaiatarrupted i::i:,

, e she during cu@ rele ::: :n : ex::pt that : t ma :: p: =itted, "ithis. the La f.w ef th: :;;;ifief '.C T I O", fer--the purp::: ef sint^- - : and p;rfc= ne ef r ^uired t::ta, ch::h:, and ::liL..t.ica:- ACTION 18 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, ef fluent releases may 4e Coefia.e, recu.cd for up to 14 days, provided that prior to initiating a release: At least two independent samples are analyzed in accordance 1. with Specification 4.11.1.1. and: least two technically qualified members of the Facility 2. AtStaff independently verify the release rate calculations V and discharge valving; s I;4e. Otherwise, suspend release of radioactive effluents via this pathway. 3o ACTION 20 With the numbers of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to **. days provided -th:t t-per 20 5:urs-grab samples are collected _.a analyzed 1 ::t en : for gross radioactivity (beta or gamma) at a 4ewev-limit of detection of at least 10 uCi/;d. Microturie.s /gra% ; ~ ~b 3o ACTION 21 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to _bF days provided the flow rate is estimated at least once per 4 hours during actual f releases. Poq curve 4 q be, ee.L -to estide flaa. ACTION 22 With the numbers of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for/up to 38 days provided the tank \\o liquid level is estimated 3 -- h idl. O GaLiiho.4 % 4ke. L

2. At i m t o k n,- s b w w k e. s 4 m.t;,.q 4 M.

N Tetendag tecla# is 3 r ea.tu. -+ A o.oi I

ic<etaAet / p DOSE. E.QOtVM4T I-m,

O' I'*A CrLL Per 24 k. eses ak -Qg, syge; g;,; g Y^t5'L6

3 oola.I ;siess 4 A er

41. to 0 o a ut c<a.

C dd tt l 3rh b5E f.Quivauer r..ag, w 1X ) d g 6 M] aI.O o 3/4 3-49 a e

k i (6 ACTIO:; 23 With the nu-ler of channels CPEFASLE less tnan required by the Minimum Channels OPEFABLE requirement, effluent releases via the affected pathway may continue for up to 14 days provided the gross radicactivity level is recorded at least once per 4 7 hours during actual relt ase. MTiod 24 (ditk tka. Mer of Chels cmp 6M less h q M b3 h 1%im Chts O Kaatti reguie=44, $twe.r vs.tou vt &c. a}{tc.t<4. pang q castime. h up +o So %s provi da.d. Ee-3ross n Lt.. aex wt +3 lu L ts dei = +1a.a. ax 1 east o % pv 4 hous bl$ ac.ha.L relea.s o.

9 O

= 3/4 3-49a

cs.. % TABLE 4.3-11 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CilANNEL CIIANNEL SOllRCE CIIANNEL FUNCTIONAL INSTRUMENT CIIECK CllECK CALIBRATION TEST 1. Gross Beta or Gandha Radioactivity Monitors Providing Alarm and Auto-matic Isolation a. Liquid Radwaste Effluent Line D% PM R(3) Q(1) b. Steam Generator Blowdown D$ M R(3) Q(1) 2. Gross Beta or Gamma Radioactivity } Monitors Providing Alarm But Not Providing Automatic Isolation-fdf a. Service *, dater System Effluent Line D4 M R(3) Q(2) J

TABLE 4.3-11 (Continued) RADIOACTIVE LIQUID EPFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CIIANNEL C11ANNEL SOURCE C11ANNEL FUNCTIONAL INSTRUMENT CilECK CllECK CALIBRATION TEST foleuZiJit YS 37Astivity Recorders.gJi> a. Liquid Radwaste Effluent g g Line DU N.A. -Nvh 4A b. Steam Generator Blowdown g,, Q Effluent Line DD N.A. -W M 4h k 4. Tank Level Indicating Devices (for tanks outside the building) 19)- a. Refueling Water Msnk D** N.A. R Q y U> b. Primary Water Storage Tank D** N.A. R Q c. Monitor Tar,k 31 D** N.A. R Q d. Monitor Tank 32 D** N.A. R Q 5. Flow Rate Monitors / Recorders ,4 D( N.A. M -N b Liquid Radwaste Effluent Line a. m s. a.. c~.r.-a m up.aum e E Q

i. -

) TABLE 4.3-11 (Continued) TABLE NOTATION

P "4^0 relear:: ?! thi: p:their j
- During liquid additions to the tank.

(1) The CHAlmEL FUNCTIONAL TEST shall tiso demonstrate that automatic isolation of this pathway and control room alarm.gnnunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm / trip setpoint. 2. Circuit failure. 3. Instrument indicates a downscale failure. 4. Instrument controls not set in operate mode. (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alann/* esp setpoint. 2. Circuit failure. 3. Instrument indicates a downscale failure. 4. Instrument controls not set in operate mode. (3) Th.--initi:1 C"2":: L CALICI'ATIOP for radhW7 C ;;2Z"'CLt--i"- M :n :ntation 05:11 M parfeumd a5 receas.4 dad in U931000:7 Eadi;109 031 M0 nit ^r*"? 1 c:ide 4.15-nm. a vu 1, "Quali-ty-Assurance fue we9:- (::crsal c;+raticus; -E Ilmen Otscana aud iW Z ~ ~ -~n;"- 4h.-occ:-: descritta the established-prcatice far eenitor errific:ti;n. ~. j a6 The initial CHANNEL CALIBRATION shall be performed using one or more of ) the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NB5. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the intial calibration shall be used. (Operating plants may substitute previously established calibration procedures for this requirement.) x- / 3/4 3-52

\\i TABLE 4.3-11 (Continued) 4d}

M=-reeuire mt ir applic el; eni-j t: y:ter: "M re th : rcie:

=:te--eyster ir dischirred te in e f f4uent--steeam,- 47 (8) CHANNEL CHECK shall consist of verifying indication of flow during perio6s of release. CHA!mEL CHECK shall be made at least once Jennsf pc.f 2.+ hem on esmy day 2 on which continuous, periodic, or batch releases are made. 59 ($) This requirement is applicable only to systems where an alarm / trip action is performed by recorder-controller instrumentation. +7+--This-sequi r e e n t i: n:t applicable te t -hich h c; dih:: :: :: -tentier rade c:pabl f p

nting runeff in th c: nt of trnt

.ccu 1 nd h:c: prenne fer crpling 2011;;ted licuid? '"d .rcuting-th: t: ; lip id ::du :t: t:::tz:nt cyrtr. t r O 3/4 3-53

I! STEU!'I! TATICN PADICACTIVE GASEOUS EFTLUE!:7 MONITORING I!!STRU!'.E!: *ATION LIMITING CONDITION FOR OPEPATIO!! 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. h 4. law /Ljo sotpoin,t2.} %se, huta sL.,4. foe.cla & w.t/ ar. act. val

u. WLh. h. OD%.

APPLICABILITY: As shown in Table 3.3-12. (-+- ( %d. log ne a.bom SpecLfi &, tmme L'% hst wA %e. rd ' ^ A 4 ACTION: ug; y, y,,,,,,44g,,,1,,,,; g,,3,,g %,,44y,1,4 g,,,. (with a radioactive gaseous effluent monitoring instrumentation a. channel alarm / trip setpoint less conservative thaQe-*elee. whi@ "ill :n ure tbt,th: limit: e f 3.11-r2.1 ::: et, cdeclare the channel inoperable. less A N.

io

%=b s. et. Withgene os-esee radioactive gaseous effluent monitoring b. instrumentation channels snoperable, take the ACTION shown in Table 3.3-12. .o, With ena-or-ecre radic::ti;; g :::u; affluent -Onitering-4ftstewnentatien-channel; incier ble--bsie..d th: Ont in'* % -peri ^A rp::ified-in the appli &ble-AGIGH siotc;;nt, prep re M.d submit te the Cc--1 :i : rithin 2' hour after the-ACTICN limit, purrunnt t: Specific:tien 0.^.2, e S p iel Repor%--in lieu Of any other coporb hich ads..Lifica ihe caur e !:) ft: ;.ccading-th: *1-its, defines w. ctive acti:n: te be tAe.. te a stor spa-A llti, a.2 pre" N en - ' ' ' - estunated date fe. retur.- te CPE??2LC at tu: ef th inst r chec...al' Effluent rele:::: ei thir rathr:y -;y centine d bey nO th: ACTICM ti..e limit : hj:;; te th; n:1 :i: 7 monitcring ::nditien: :f th: 2ppli:21: 'CTION ;; tc.unt. SURVEILLANCE REQUIREMENTS 4.0.3.0.1 The u tpeint: ;h:11 h: ?.;termin:d :nd r:: erd:d in ace::d nce-uith-p:::: La u s. 4.3.3.9.fi Each radioactive gaseous effluent monitoring instrumentation ( channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations duzid; th: "005' nd at the frequencies shown in Table 4.3-l 12. -~ v s m / 4.3.3.9.J2. Records shall be maintained of the calculations made, in t~

,a tw etar l

3 accordance with procedures in the oCDM, of all radioactive effluent I

( monitoring instrumentation alarm / trip setpoints. Setpoints and setpoint. calculations shall be available for review to ensure that the limits ,/ I 7 }ofSpecification3.11.2.1aremet. g D** 3 ci'l 3/4 3-54 cc c d 4

EASES 3/4.3.3.9 EADICACTIVE CASECUS EFFLUE!;T I! STRUME;;TATIC:: The radioactive gaseous ef fluent instrumentation is provided to monitor and cont.rol, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the vaste gas holdup system. The OPERASILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. i e 3/4 3-55 L-

/' 0 9 / L,1T' TABLE 3.3-12 56 I - RADIOACTIVE GASEOUS EFFIEENT MONITORING INSTRUMD4TATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY -PARAM9PSR-ACTION 1. Waste Gas lloldup System Explosive Gas Monitoring System 4 Ori ;ca 30 a. Oxygen Monitor

- 45 6.

dstacow MaLW y 7 g 2. Plant Vend *** -Radionetivity-Rate 27 a. Noble Gas Activity Monitor 1 -Meaeur----t- -Verify presen:: ef 31 b. Iodine Sampler Cartridge 1 eartri @ w 8 Verify-praeane= Of - fi-Iter-31 E, c. Particulate Sampler Filter 1 -Gystem-Flcw Rote 26 d. Effluent System Flow Rate 1 -Mea su rement-Measuring Device -~ ~ ~~~ - - Q -Sampler-Flow-pate-26 Sarr.pler Flow Rate Measuring 1 4 e. g Measuremenh-F Device 3. Containment Monitor System -Radiometivity."ce=uu ~..i 27 a. Noble Gas Monitor (R 12) 1 -RadieeebiViti "Ceau;Z2t-27 b. Particulate Monitor (R 11) 1

TABLE 3.3-12 (Centinued) TABLE NOTATIC11

At 0.lt towe.s.

C mc.aci: chill L: C"r?J.3LE :nd in ;;;vic: en : c atinuous, uni-teum,t.J

2th: :y, c ce[4-th:t cut ;;; c.e Faz-itted, be-in-during ::1 :::: "in thi a

-whMn-tha ti e -f ra;. sf--the opmwifica ACTION Im ihm purpc: ef '- at :n:n;c-r.d-perfer ance of required t::t:, chech :nd ::litratisn:.

- During waste gas holdup system operation (treatment for primary system of fgases).

^^^Thi; will aims.~.dter ::1::::: fr;-- th; cent herf::, "~'liari huildin; vente, 'v:1 ;; crag; t;ilding ccc. : rd th: redu;;t: tre: centr- '"h--- -cendeneer :: ;uction cyctc;- i. ;..it : d ;;ntinucuc1; Only 2: !" "' # - iter 2 _ 30 ACTIO!! 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE rec,uirement,peffluent releases via this pathway may continue for up to $5 days provided the flow rate is estimated at least ence per 1F hours. 4/ So ACTION 27 With the number of channels OPEFABLE less than required by the minimum Channels OPEPABLE requirement, ef fluent releases via this pathway may continue for up to 29-days pro-ided grab samples are taken at least once per 8 hours and these samples are analyzed for gross activity within 24 hours. ACTIO!1 28 (Deleted) ACTION 30 With the number of channels OPERABLE one less than required by the Minimum Channels CPERABLE requirement, operation of this system may continue for up to 14 days.-) -Mru:1 se._;1:: =:tch u!11--Lz ;;;;p* Te "bec the p::;;;s 'E== c,==== p : __.1.- -a... ~ _ _. _ __,._._._.4_._ 2 _ m., u_ _. o imL h chas epetu, be. 6 o.e teo.st aer sr es, Wi h b kours. 1 l e O e

TABLE 3.3-12 (Continued) TABLE NOTATIO!! 10 ACTION 31 With the number of channels OPERABLE less than required by the Minimum Channels CPEPABLE requirement, effluent releases via this pathway may continue for up to 98 days, provided samples are continuously collected with auxiliary sampling equipment !:: p::!r'- er & r ::.. '7: i-ia...: .;L;;;' :!:hin 40 Lvw ; cf th: :n cf e - r1 - :rilretier os rgMuL in TAbte 4.11-2., e 3/4 3-SS s

TABLE 4.3-12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SilRVEILLANCE RFJ)UIREMENTS CIIAt3NCL NPD 84 W AKA SOEJE W CI CilANNEL SOURCE CIIANNEL FUNCTIONAL E4GoaLLD INSTRUMENT CilECK CllECK CALIBRATION. _ TEST 1. Plant Vent M a. Noble Gas Activity Monitor D R(3) O(1) 4 b. Io' dine Sampler Cartridge & W N.A. -R-N.A. K N*O* Particulate Filter g p 5 W c. . Particulate Activity Monitor W D R(3) Q(1) .g d. System Effluent Flow Rate -# D N.A. R O 4 Measuring Device 6 Yg '2. Waste Gas lloldup System Explosive Gas Monitoring System V Q A 4* - WA. N.A. 89( 4 ) um. a. Oxygen Monitor M hl. A. Q(5) A

TABLE 4.3-12 (Continued) RADIOACTIVE GASEOUS EFFIAJENT MOllITORING INSTRUMENTATION SURVEILLANCE RCnUIREMENTS CllANNEL meOO 861 *Id*L4 CllANNEL SOURCE CllANNEL FUNCTIONAL CO R J Cat.ca.a ct i CllECK CilECK CALIBRATION TEST SEtiroitt0 INSTRUME:aT 1 3. Containment Purge Vent System p a. Noble Gas Activity Monitor D* .D*~ R(3) Q(1) P I y R(3) Q(1) b. Particulate Activity Monitor D 1 8

O TABLI 4.3-12 (Continued) TABLE NOTATION & 4t an. times ^ Channel chall he CT:nAOL :nd in :::vi;; en : Ocntinuous, uninterimpted -basis--during ral a= ce: ric this path.::y, except-that-outage ar; pe_mitted, within the time-frame of ihm specificd *.CTICM for -thc purposa of ;; inter ="r^- +nd performanse-of guiled testo, whuwk and 0:libration:-

- During waste gas holdup system operation (treatment for primary system offgases).

Thi will clas seitor relca;c. f vu LL vent hc:dcr, cuxilie y huilding .:;cn t e, fnai s+0ra W iny vu.is and the r:& ::te are: -cats. Th: condent:r Overu*tierray5tua i5 RenitOr:d can;inasu5ly only : in thi -itee Os. (1) The CRANNEL TUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm / trip setpoint. 2. Circuit failure. 3. Instrument indicates a downscale failure. 4. Instrument controls not set in operate mode. (3) The initial CHANNEL CALIBRATION for radioactivity measurement in-strumentationshallbeperformed[2: recc-nded-in n;gulatory ["Guid; .15 ncvicier 1, "guality *.::urene: f r nadi:1cgie:1 :Snitsiing-Freg r -- "'emal-Operatienr } - Effluent.Otrc;.; and th 2nvir:nac.t". Che-CDC4-deser-ibes--the =uaLiished prettice--fer.4nitor vcrific:ticr. -tExisting plant: :y ;uhaiaiat; previe"-ly ::t;Liished calibr: tion -procedure: for thi; ::quir

nt.)-

y using one or more of the reference standards certified by the National Bureau of Standards or [ using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall \\ permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have / been related to the initial calibration shall be used. (Operating plants h may substitute previously established calibration procedures for this requirement.) 3/4 3-61

TABLE 4.3-12 (Continued) (4) The CHAN::EL CALIBRATIO1 shall include the use of standard gas samples containing a nominal: 1. One volume percent oxygen, balance nitrogen; and bha. 2. Four volume percent oxygen, -284r nitrogen. 00". k d::; n. i 3 (b N CO M6L, 4 ttitane d s Q ine,LA.,,-ft.,, s e, ey stg_ J. 4 g b i.l, c. r _1_ _ : Y* fW ht~, b&m en, d

2.. R% v. 6 p g L % c,baA.m ge _

t S e 3/4 3-62"

3 /4.11 FADIOACTIVE EFF'./.'E::TS 3/4.11.1 LIQUID EFFLUE:TS CO!;0E :TRATICN_ LIMITING CC: DITICN FOR OPERATICN 3.11.1.1 The concentration of radioactive liquid effluent released from the site to unrestricted areas (see Figure 3.11-1) 2: calcui:tcd und:: 20.1052, shall be limited to the concentrations specified in 10 CFR Part 20, APPedis B, Table. E, Column 2. jer rod.tomac.L:Aes atur h dasalvd.or ch nobte.$ases. or Ossolved or edrained, webla, $a.ses, +k.a. meeJA4 4 sM bo (l.4ted, to 2.x m-4 w eroturie5 kl total &c.t iVMs. APPLICA3I ITY. At all times. ACTICN: With the concentration of radioactive material released from e,# a. the site to unrestrictg areas exceeding the above limits, imaudiateL3 6 g6 take action to restore cencentration within the above limits. x hL (b. -ans provide prompt notification to the Commission pu.suant to Specification 6.9.1.4210. C SURVEILIR;cE REQUIREME :TS p# f s mw [4.11.1.1.1 The concentration of radioactive caterial at any time in ( ) liquid effluents released frem the site shall be continuously monitored p d # of.M -in accordance with Table 3.3-11. ( l 4.11.1.1.2 The liquid effluent continuous monitors having provisions ? 3.3-for automatic termination of liquid releases, as listed in T /S 11, shall be used to limit the ccncentration of radioactive w terial released at any time frem the site to unrestricted areas to the values j j iven in Specification 3.11.1.1. ~ ~ i v 4.11.1.1.3 The radioactivity centent of each batch of radioactive liquid waste to be discharged from the site shall be determined prior to release by sampling and analysis in accordance with Table 4.11-1. The results of pro-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is#1i-itef *^ W '21;;; i.- Specification 3.11.1.1. l > m itaa ad. t4 E 4ke. C it' 'Y it d 4.11.1.1.4 Post-release analyses of samplesg rom batch releases shall f be performed in accordance with Table 4.11-1. The results of the previcos post-release analyses shall be used with the calculational methods in the ODCM +o assure that the concentrations at the point of release were -init0d te th: =lu s in Specification 3.11.1.1. MALA % tsk QHC ika C la,of b h Cal d M C Spetl.fi (Ah 3.11.1.1 M/w & ACTiodO ra tAEtaedu Ca+4 12o sak;s}ie.L becou.a. 4 c m A... x ucen.j. %3c. aga<,ne,t i w. ecma a_, h e % 5 m-et-a.- e %t as w a;s_s % a c,a w ^"*1 N N bE A sy ma. acts sLA ta.et be A gg g W 1 3/4 11-1 3.11.1 4 Is utt. 'IM,4, provist*N S!us.ll wet prevd assqc. L b ed44. r M b% f MHk. ALTied A..

SU R'.*EILLA';CE F.E O'JIRE'iE!;TS (Contir.ued) 4.11.1.1.5 The radioactivity concentration cf li:::ds dis:harged fr::- continuous release points shall be determined by ::lle:: ion and anal / sis of samples in accordance with Table 4.11-1. The results of the analyses shall be used with the calculational methods in the CDO: to assure that the concentrations at the point of release areb i-l =' ~ + % bhintalnut w.tGh G:h ej. '- Specification 3.11.1.1. ~- M gW 4.11.1.1.6 Reports. The semiannual Radioactive Effluent Release a3V Report shall include the information specified in Specification 6.9.1.E 6, w _- 3/4.11 RADIOACTIVE EFFLUE!;TS BASES 3/4.11.1 LIQUID EFFLUENTS 4 B, TA= I, (** 2' ' 3/4.11.1.1 CONCENTRATIC:3 This specification is providedito ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20,A This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will aet result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population. Tkt. ConceedEA.Cee k hr-dissolvaA or EM nabe. gets is bc.s eck upoN h<.- Assumptiew 42.f )G.-In is YLa. ceJActhq radioisotope, M Ms MPC. l~ Ah. (subutrsiox) Was cewerted. +o a uvalr4 Caur4.fLL tk waL ut., % u.eAccts ctescribed [~ L%4~ L Ca w ass;e ~ w k m

c.1 Pmtic.t ~

uan uu w. i 3/4 11-2 1

l l TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SM*PLING AND A! ALYSIS PROGFAM Lover Limit Sampling Minimum Type of Activity of Detection Liquid Release Type Frequency Analysis Analysis (LLD) (uCi/ml)a Frequency 5x10~7[ P P A. Batch Waste Re-Each Batch Each Batch Principal Gamma Emitters 7' b lease Tankse Comhsite 1 x 10-6 b bMO Each Batch I-131 TaA) P M one Batch /M Dissolved and 1 x 10-5 Entrained Gases (6a m. Eu ttud 1 x 10-5 I* P M H-3 C Each Batch Composite Gross alpha 1 x 10~7 1 x 10-6 P-32 P Q Sr-89, Sr-90 5 x 10-8 c Each Batch Composite -6 Fe-55 1 x 10 W d d B. Plant Continuous Continous Composite Principal Gamma Releasesf Emitters 9 5 x 10-7 (S A 6% d 1 x 10~6 I-131 hh~) M M Grab Sample Dissolved and 1 x 10-5 Entrained Gases (Sama. E%;+tud l M d d 1 x 10-5 Continous Composite H-3 Gross alpha 1 x 10~7 i 1 x 10-6 P-32 Q d d 5 x 10-8 Continuous Composite Sr-89, Sr-90 Fe-55d' 1 x 10-6 3/4 11-3

4 TABLE t.. 1-1 (Centinued) TABLE NOTATION 4d d daa+ai:L

Thes; 2nalyses-will-bewfowed-for-a--cn y:-

par e r-en -e ad; by the-Lic---ee

t -the ne:d te centinue-thca :n:1y;;; b :-;d-

.on. ievicu 3:tciled in the " -i :n-"-1-Radicactiv: Effluent Fele se-2epert; The LLD is the smallest concentration of radioactive material in a a. sample that will be detected with 95% probability with 51 probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radio-chemical separation) : LLD = 4.66sb E V 2.22 Y exp(-Aat) o g, priod' b where

lb

/ PS LLDisthe[lowerlimitofdetectionasdefinedabove (as -pet per unit mass or volume): sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) : E is the counting efficiency (as counts per transformation); V is the sample size (in units of mass or volume); x i0' microcari u 2.221s the number of transformations per minute pergpice-m le; 4 Y is the fractional radiochemical yield (when applicable): A is the radioactive decay constant for the particular radionuclide; at is the elapsed time between sample collection and time of counting. The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background countina rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In :21:ul :in3 th: LLD fu..- radienuclid:- detarained by ;- r -::y p :treret y, the b :kgr und shall inchde the typical centributi:n: cf other radienuclid : norm:11y prc:-e.t ir the r-pier. Fer i;:tzpic :::urem;nt:-using ya; rpertr::::py, -th; i:rkgrcund count rate-i; ::1culated fr:n-th; backgr ;nd -counte-that :: detc.:.ined to t: uithin. c... full,.id.;..t h:1f-

-axir"

ncrgy b--o ^~

th: :n rgy :: U.

3.....y p :L aa d- -for th: 71--titativ: :n:1ysi: for th t radienu.1 d. Typical valuesof(L,V,Y,andateheeld e used in the calculation. u, mu. It rh Cid L. mwOgni::d th t th: LLO i; d fined 20 g priori (befer th fac*i 'i-it'::pr:::nting th: cap sility :f : meesweement cyct : ;-d n:t

n 3 perterieri '* ** ^--th; fact) - liait f r particul-r ~= =r"r: ;nt.

3/4 11-4

f cld : 1;u :n:rgi::. Or f r i b. T;r cm.'.olu r dirn'@ ider. tith 1:1 ;;=: certain. di..mclid; mixture, ii.., me; bc pe;;itic te m:::ur: radie..w lido, in cen catr;ti:n: n;;r the LLO. L'.a. th::; :ir _.. Lan u.u 4h LLE ...uy bu luciaaoud AuvwA=wly y syw is 4 ally Lv Lhu .ua y as a k ud w Of th: grc: yield 'i.e., ';. 1 GM/I, es t a I As ihm pheien bund:nce e*pr;;;;d : : d::i=:1 fracti...). A composite sample is one in which the quantity of liquid sampled is c. proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is repre-sentative of the liquids released. d. To be representative of the quantities and concentrations of radio-active materials in liquid effluents, samples shall be collected cow %uousl3 in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representat-tive of the effluent release. Composite samplers must be engineered and backfit and will not be operational until September 1,1981. e. A batch release is the discharge of liquid wastes of a discrete volume. Pn'er to sap,% fe % ses, c a.. borrA sLoa de. isetut, a~t h hou3ya. 63 A. utud. dueribe. %,, CDcM., to Astwa rep ast+2*It<t. sa.y liq. f. A continuous release is the discharge of liquid wastes of a non-discrete volumes e.g., from a volume of system that has an input flow during the continuous release. (i.:. :t:= gen:: ter during :- _pri,;ry t: :erend mj lech!-- of*' g. The principal gamma emitterr for which the LLD specification.sezhk applu s 2;;17 r e exclusively 3the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which er; bale.: th LLO for the cual;.. shcul? '" 1:v:1. " hen unu ual r.o; L, rapsrt:d 2: bein: pre:ent :t th: -eheumeeence. umult in 11"' higher-thin requir:d, th; rc::en: +helt-be documented in th;.caiannuel n:dic::ti2: Cffinmut Rel ::: -Report. N " hen op er=*ienal er other li-itatiene preclud; specific gr ::dinedina. 2nalyci: in batch reles ::, the previ icas af new1.;m.j Ouid: 1.21 (n ticien 1) .'.,r, :ndix A C: tien 3.1, i he felle : d. -'efer te n.O. 1.21- -Oc;tien C. 4 and.'.pp:ndix '., C::tien 0, I l i l 3/4 ll-4a

-* )$6Q[.f]W'. 7';). 4 &.?'" g ~n 2 ' ; ,st-: ut st ff.'./*'(Ip,f j' ub?'f'kIavis / 9 3,/ i 12 w$ff,oGWc0,[s**' y

l v

q ~3,,,,, s i l &,/.//, - e. ,. =.. / w;c 2, ~- dharles ,,.<.7 /9 b.;,;/Pt'/ l g' $p?? 2 es l ,/. *Ce,*h%lHad_ y,y 23 ,.9 f l l< - f.OW POPUI.ATION ZONE PERIMETpB' f o ff '7

\\ lg b' M~

n :;my:f 1 / f n.enF

{f:.. :,

U. Q '; \\ \\ v j y, ;n; / cy i.- .1,g~c //..j ff 6 j sof [ y," h., s / Y' / INDIAN POINT I Q.j,3

Sm

.x soy uuts u a g //,- -iggw.a yy \\ / / ?ynWW ,\\,.= /.4% - w.. .$W \\).:- W..t-v A ,cjYf*,M .~...c / v...mau y i ",,25*~y@fM h

g j

zu-N,OIm ^ h l '- ,. p AnanQ ;: ji ~f / o /.5 ......a . y _ ' !.,,. )*.:.a. cr.c k.' ,, f 5,* -l t y/ .r .~ - c, e n m

i,
I' s

('J al} h..-.: 4<:@: ' :+:s' f l' . '?.iMf A' s , ~Clf$ ~ *} *.4..g& ,e. s ,..L-i. ~y = / \\ f ..h/. 4 .)$

j f Y h(......?-l h,

A 1Ck / Ca solen.., s rsO hD.I. " f%i J s 4 ****.**.*'/ . k+/.* / / 7s'd CON EDISON RESTRICTED ., p g* ' ' 'P fP rrO l r. A AREA (IP-lf.2)

M d

Jh POWER AUTHORITY RESTRICTED f d

==rm iv= u u

FJu")ICACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATICN f& 3.11.1.2 The dose or dose commitment to an individual from radioactive

site, materialsinliquideffluentsreleased,fromeach{ unit,teunrectricted:::::po%%e.g (see Figure 3.11-1) shall be limited:

During any calendar quarter to 4 1.5 mrem to the total body and a. to J 5 mrem to any organ, M b. Oar s 6 3 w*m. h h tom bok M $6 b IO *** Yo APPLICABILITY:q % cake <laA. 34ar. -to At all times. eq m. AC"*'I ON. e w a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a 1 Special Report which identifies the cause(s) for exceeding the [ limit (s) and defines the corrective actions to be taken to reduce N the releases of radioactive materials in liquid effluents during the 3 I remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment ' i to an individual from such releases during these four calendar / quarters is within 3 mrem to the total body and 10 mrem E any _ organ. - .: pcc;&T depci Ushsil7130 -;nclude (1) the c; ult; of N ical analyses Of the drinleing-water S0urce-and (2) the- -radiological impact _cn finishcd drinking water supplies with regard u. . u.s __a._......._ .s ,.-~.a m,u_ m 2 _,. u, u w_ 1,m, _ _ _ o v n., o m om o, n v.. j ,w ~.. t. The previ:icnc of specification; 3.Or3-and 3.0.4 &ce act applimoule.-- 1:v:1 ::t forth 2: ~~rri::1 guidas for d :ign chjectiv:: irr Oc;;i:n II, 10C""30, A m.. din I. -At th; cre ti ;, th; licen;;; i: ;c rittcd -.dc

10sTO, App:ndix !,-th: fl u.hility Of ep:riti^*

p tible with : ncider:ti:n -ef hcalth = d f ty, ts casmr; th;t th: public is pr:vided :- 2:p:n d 91: ::ur;; ef poucr ;c;n under =u ;al ;; r; ting cenditirn:-

hieb ry t:r.;;r;rily sc; ult in ::le:::: higher th;n wh umic:L

.guid:: for ac-i; chj::tiv:: het :till witbo ic c 1: that =rrur - that th;

r:gc p pul: tie.. cap;;ur; i; e a;seleni tv

. 11-s fractica; cf dere: fr:: natural-bechgreed r: diction. It ir r;::ted thet-in using thi; Operati;nal-flexibility undcr unusual cpcrating conditicas, th; liccascc--will cnart-hie hest effv.te to-N::p level: ef radicactiv: rat: rial in affluent: within the- -rmmer4c 1 guid:: fer design Obj::tiv :. SURVEILLANCE REQUIREMENTS 4.11.1.2.1 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once per 31 days. 3/4 11-6

3/4.11.1.2 D05E c+ K.4, This specification is provided to i=plement the requirements of L SectionslIII. A and IV. A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section 11.9 j 1Memb of Appendix I. The ACTION statements provide the required operating i flexibility and at the same time implement the guides set forth in i Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably ) achievable". The dose calculations in the ODCM implement the requirements { in Section III.A of Appendix I that conformance with the guides of i Appendix I ve-6e be shown by calculational procedures based on models and data,such that the actual exposure of an individual through appropriate i pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents vill h Aso } consistent with the methodology provided in Regulatory Guide 1.109, i " Calculation of Annual Doses ~to Man from Routine Releases of Reactor ) Ef fluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.113, 1 " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. N'J2:0 0122 p::fid:: m:th d: f:: d :: ::1:;l: tier: -- -irt::t -aith 2:gul:tery Cuid s 1.100 oud 1.113. RADIOACTIVE EFFLUENTS BASES This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system. i

~

l 2 3/4 11 7

RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION oppropriate, portions of h. 3.11.1.3 The liquid radwaste treatment system -ee-eee shall be OPEPABLE. TheAsystem shall be used to reduce the radioactive materials in licuid _ wastes pr,ior to their discharge when the projected dose # due toiliquid ' effluent-rel::::: h arestrict:d Orc:: (0:0 Figur 3 11-1) wili t is en ::d the li-it; in 3 11.1 2- % rew tkt. site. (sen. R we 3.4-0 MW "Med A. %s, wcnJA cren,J 0.C(o wrem ts %. tot:a.L fooy or 0.2. mrtw fo aq eqa. APPLICABILITY: At all times.during 2ny q: rt:r in hi:P dis-..- r-unrectricted crear cf liquid Offlurate cont:ining pl:nt rel:::d Offi s ts-centaining pl:nt relet:d r:di:::tive m teri:10 cc ur :: i; :n;::t;d. roAcute. M d1' # L-81 ** #f

ACTION:

A kg.id. Wasts a. With :dic;;ti:: liqui weete being discharged-t; the un.ustch L J -ar-ea. without treatment and in excess of the above limits, k lh of M ~) prepare and submit to the Commission within 30 days, pursuant { to Specification 6.9.2, a Special Report in li:u cf :ny ay a ^ er repert which includes the following information: ~2 $ V +ke. two parato Ic Ap ~~ 1. Identification of equipment or subsystems.;t Cr:=LE 3 and the reason for inoperability. 3 2. Action (s) taken to restore the inoperable equipment to sb2 OPERABLE status. ?l, D 3. Summary description of action (s) taken to prevent a 8 recurrence. BASES 3/4.11.1.3 LIQUID WASTE TREATMENT The OPERABILITY of the liquid radwaste treatment system cr :n:ni, j Op::ified in LLo OOCS ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part .36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and sign objectikar rne3 ection II.D of Appendix Ento 10 CFR S Part 50. Thespecifiedlimitsgoverningtheuseofapgropriateportions of the liquid radwaste treatment system were specified in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents. GS0.Sdelol.hac. tic >- af t l % dese, dn*p objtttive! Set hik. 3/4 11-8

RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose in the unrestricted areas (see Figure 3.11-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values: The dose limit for noble gases shall be 4 500 mrem /yr to the a. total body and 4 3300 urem/yr to the skin, and b. The dose limit for all radiciodines and for all radioactive materialsinparticulateform,[withhalflivesgreaterthan P 8 days, shall be 4 1500 mrem /yr to any organ. F APPLICA3ILITY: At all times. 5 ACTION: g-Y imedish% Q p With the dose exceeding the above limits,g ecrease the release g d a) 3 rate to comply with the limit (s) give in Specification 3.11.2.1. ') M grovide prompt notification to the Commission pursuant to { ,u o p - C-) ) Specification 6.9.1.12. s SURVEILLANCE REQUIREMENTS I j A.11.2_1.1 The W = ;=e affluent-centinusus w eiter: having-prevwiene 3 l Joe-the-eutematic-tennination of gasesus releess, :: listed in Table ( sr M 27-shall be used te limit-offsite-dese. ithin the values cstabli:hed e 1 .in-Specif4 cation 3.11.2.1. whe_- r-itor ::tpcint :1u : ::c cxc::d:d. O E O +r h arl.2 The relesse rat: cf o l we a va material:, ethc; then- .nchie ;?ser,-insecu; cfflucats shall be detm.a.in 2 by cbtaining- -aepsasantative--r plee-and performing._ elycer i- =~rdance eith the . sampling-and--onelysis program, :pecifi;d in -Table 4.11-2. 1 P b. % e. esed &f Spudiv.tte.- 3. ll 2-I M/V ACT'64 d-Ms ht k, I gat!1fitA be hse., o tw tu.t.it e j- -fio s e. addsessed, k Acfm! A, h , cw u Aste t J M sktt 6 plu.ut G. a.t teut-ket-sLtdu~ witG~ 6 Les um ceM. l A s ktd u,_ g; g 30 gy,,g 4g M* S ecf ht % a. u. 2..t is a. %;s po<ist. m, g t % " O h (ou-f 3 al A Acrt.4 &, "* 5 t 3/4 11-9

4. L l.2.1.1 Ne, dost., M clw Yo gefale. go.ses i.-gaseous QLeZG gW k

be.,(Anh. M to (og., Alt G YL.a. ahe/4 ( 'r.its s'~ Accavh A -hka, ne.%ds a4 yo cadyu, 4 4t, opc.g, SUPJJEILLAZE RE9UIEIMr'Ib 1 4.11.2.1.9 The dose in unrestricted areas, due to radioactive materi-als other than noble gases released in gaseous effluents, shall be determined to be within the required limitsihy ~ig the result: Of- ) the sampling and analysis program [specified in Table 4.11-2. -iw @p in unr;;tricted cres:- %p GE6. Co*# prfering th; ;;1;alati;ns of d::: g "7 p gh o.3 4.11.2.1.( Reports The semiannual Radioactive Ef, fluent Release 4D IEg Report shall include the information specified inD.C. _ _1.21 "c. 1 h L o p fEhG'.t.A b A 1. (., {If BASES 9-c.5 E. I I 2 3/4.11.2 GASEOUS EFFLUEiTS $ 2# 3/4.11.2.1 DOSE h

site, T h{

This specification is provided to ensure that the dose at the xclucica $f g +eee boundary from gaseous effluents from all units on the site will $ ft be within the annual dose limits of 10 CFR Part 20 for unrestricted a The annual dose limits are the doses associated with thej-* fa61 areas. concentrations of 10 CFR Part 20, Appendix B, Table IIf These limits {3 f(s provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the exclud e-2:e dte, 3 boundary, to annual average concentrations exceeding the limits s-ecified p in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106 (b b q Forindividualswhomayattimesbewithinthe[*'clusien:::: boundary, J ]p y, the occupancy of the individual will be sufficiently low to compensate for.any increase in the atmospheric diffusion factor above that for the$$s4*sien-+c+aboundary. The specified release rate limits restrict,alaLL % 4, thecorrespondingammaandbetadose7aYovebackgroundtoanindividual at or beyond the enclucier 'r:r boundary to 4 (500) mrem / year to the g total body or to < (3000) mrem / year to the skin. These release rate _ limits also restrictXthe corresponding thyroid dose above background *,A% a % es, to an infant via the cow-milk-infant pathway to 4 1500 mrem / year for the nearest cow to the plant. This specification applies to the release of gaseous effluents from all reactors at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system. e 1 l 3/4 11-ID l 1 1 l

TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Type of Detection (I.LD) Gaceous Release Type Frequency Frequency Activity Analysis (uCi/ml)# P P f 1 x 10-4 A. Waste Gas Storage Each Release Each ".cleare Principal Garaa Emitters Tank Grab 'l a. k_, Sample -H-3*- x-IN P P D. Containment Purge Each Purge Each Purge 9 Principal Gamma Emittersf 1 x 10-4 O Containment Pressure Grab 1 x 10-6 Reliefs 4g % Sample II-3 f 1 x 10-4 C. Plant vent MB A, A go S Principal Gamma Emitters 5 (wde ter Air Ejectu Grab H-3 1 x 10-6 [ Stem Gewst.,- Etwas R.4L Sample e Ta A -- M I-131 1 x 10-12 e E Continuous O' bN Charcoal kh Gu SteyAsje, Ta.k. Sample I-133 1 x 10-10 6,e.trJ - o. c P - ge. g e Continuous (cdabau.t' Prenure, kaks f Particulate Principal Gamma Emitters -Il ' 9 '. W.i Sample (I-88, Otkes ) 1 x 10 b*l h a r.tk*,,3 2 3 1 x 10-11 continuouse M Gross alpha Corde.sa A*x E ectge d Composite Stcaw (made bdow fwk Particulate Th *L., Sample Continuouse Q Sr-89, Sr-90 1 x 10-11 Composite Particulate Sample Gatauous" Rolde, Gal Asble. Gases l -6 I x to b c. tor 6,.ss kr., 4 Ga-9

hf'S 3d k ed. At least met pes 7 o%s M s es E M 6.a. CeylaTaA. "A +8 W Aft- % Dr c-ft-e b. +). s% a t TAS*.I 4.11-2 (Continued) J f TABLE NOTATICM I See footnote a. on Table 4.11-1. a. _ith 1.. ;,.; 7 :12 er 1:u : :rgi;3, or 1 t._ -r;; em,.*,4-r e 4 .o_, c3 y m e fer certair ::dimnuclid; =ixturer, it ;,ay not b; p;;sible te ~^:;ur;- { 2 dica"clid : in ::n=entrati:n n;.r th; LLO. Und:: th::: circ" - ++="ce% -th: LLO r.y be loc. m ca lu m eely p oporti:n:lly tr 'h-r:gn'_+"#- cf the y - y.la (i.w., 1a 10-4/I, 4 ci. I as the ph:t:n

k"n':

exprr. ;;d es : d::i..;l f;o

.eu). tLt leasT d. /nal'yses shall also be performed at least once per 24 hours forg7 days 3 } following eachkr-fe;1ing er ciriler crer tic..a ww wi..nce c ^A#"? i "hich -^"'d-le d te si nific:.. incrc:::: er d:::::s : in :di

g rel:::::. When samples collected for 24 hours are analyzed, the f

corresponding LLD's may be increased by a factor of 10. }E RR F The ratio of the sample flow rate to the sampled stream flow rate <1 J e. shall be known for the time period covered by each dose or dose 4h rate calculation made in accordance with Specifications 3.11.2.1, k.{4 3.11.2.2 and 3.11.2.3. m~ v S f. The principal gamma emitters for which the LLD specification *s-H applies y . apply'a're'Qxclusivelyj he following radionuclides: Kr-87, Kr-88, jR y ~ t Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions and Mn-54, 7p Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 y7 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are ? "{ n measurable and identifiable, together with the above nuclides, shall yg also be identified and reported. "u:lider hi:P ::: belet th: LLO-2 -fer th: an:1ysc: theuld net b: r,mrt=A being pr ;;nt ou L:iw LLB-4 level for tb=* - ur' 4 Aa '^ ea "ausu ' 4-~--

.3 Mgher -than requir-A -
ka * ::.n; abo 11 Lw Jewmmut=a in uha ocai=

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e "lere than".ainmo shell n t be u::d fR

. u.. _-._ s _. _t _. _s,2-- ., ~,, + < _.. g Q m. g. The couie;ceent.:ble ;;;...e.. iter 'T !?' c.y b: ured t.alcul:t: the J ral==e^ r:te.

h -lieu of gr-b

- pl::, une of.'"T." =thed D3442 " Test-fcr-Triti= Cenicnt-of-Mr" c= a he unca.

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e. na. Q - IS fute X of %. FATED T % G PwGt A1 L a on kew p:ea..

h Mb jrtLb Saatpas skad lot h, gy (gagt g y Q3 gy % ~ap. .'- * *- $d s y lu 441L h.t b artwr m pec7 gs b_ % h' 3,.

M*" *ST h -h.a. syd hd. pod auto., j dm 5ted h a pool..

3/4 11-12

b. M]

calc dar g en, Ye 610 urod. h p-raddQ g i & u m & ut raias.. FA'H CACTI'.*E ETTLUE::TS

g' DOSE, !:03LE GASES a+-

LIMITI!:G CONDITICH FOR OPERATION [ow / h 3.11.2.2 The air dose in unrestricted areas (see Figure 3.11-1) due to noble gases released in gaseous effluents shall be limi:ed to the following: g During any calendar quarter, to 4 5 mrad for gamma radiation and a. ( 10 mrad for beta radiation; APPLICABILITY: At all times. ~' ACTION: ~ ' N' With the calculated air dose from radioactive noble gases in gaseous s a. / effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the ( 'f Commission within 30 days, pursuant to Specification 6.9.2, a Special 3 Report which identifies the cause(s) for exceeding the limit (s) and N defines the corrective actions to be taken to recuce the releases of / radioactive noble gases in gaseous effluents during the remainder of k the current calendar quarter and during the subsequent three calendar \\ quarters, so that the cumulative dose during these four calendar quarters is within (10) mrad for gamma radiation and (20) mrad for t beta radiation. D rep ^rt, repor ing th::: ucticns. ,/ is specteitS=t the-armeerl 1 lc :e of redioactive ::terial-tre It efflucat frer the -=it- :an gencr:1-ly be maintained ithin LL. -levels set-4 orth :: nu ericalmidos for d::igr chj::tives--ard Sect-icn II,-lOETR50, App;ndin Ir '. t the := tin:, the liccas:c 1. p....Itt-a = der-40CTR50, Appcndix -I, the flexibility of opcr: tier cc :tihl: uith concider: tion ef herith :-d safety, to ::;ure that the p 211w is pie.ided ; dep:ndable source of peu:: :ccn under =ucusi operating cc~*itien: j wh*c-h-c;y terr:rcrily ::: ult in rel::::: highcr th e -"ch n =:ri :1 l guidcs for accigr chj::tivc3 but still within le"als that 1;sure-that-th: crer:g: p-p la-ti:n :nperura ir quivslent te s.. ell-I fr:: tion: ef ac;cs frca natur:1 backgrc= d radictien. It i:- l e*pected that... uaing thic sper tional finibility under =usu:1 cperatiny w..diticas, the licensec -ill :nert his best efforte te keep icvcis of radic::tivc material in effluents within

k=

,=:rijel guides fer do iv. chjc;tiver-carrei calck gar **f Od C"'*C Cok& I SURVEILLANCE REQUIREMENTS 4.1), 0. 2.1 Dose Calculations Cumulative dose contributions for tktetel-4 ire prica shall be determined in accordance with the Offsite cose Calculation Manual (ODCM) b #Il**'I*"*~P'# 1I N" ' ^^ N_-

v O* g [4.11.2.2.2 e_

Reports The semiannual Radioactive Effluent Release Report i shall include the information specified in Specification 6.9.1.We. / 3 ~ 3/4 11-13

4 BASES 3/4.11.2.2 DOSE,1C2LE GASES 2t. 5 This specification is provided to implement the requirements of SectionsAIII. A and IV. A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in b SectioT y of Appendix I. The ACTICN statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix I assure that the releases of radio-active material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements inDh** SecticaIII.AofAppendixIthatesaseam{withtheguidesofAppendixI h be snown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate path-ways is unlikely to be substantially underestimated. The dose calcula-tions escablished in the CDCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents ill ir an., consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Iffluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatorf Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July The ODCM equations p ovided for determining the air doses at the 1977. sMe unr : trim::d :::: boundary uill b; based upon the historical average atmos-q pheric conditions.

Mre, e*

3/4 11-14

RADIOACTIVE EFTLUZ::TS DOSE, RADICIODINES A!!D RADIOACTIVE MATERIAL IN PARTICULATE TcRM, A4D E/@o duct.tocs Cr%f TM4 Mck.E, GMET gg LIMITING CONDITION FOR OPERATION _ pes) l 3.11.2.3 The dose to an individual)from radioiodines -aewir, radioactive materialsinparticulateform,kwithhalf-livesgreaterthan8 days,in gaseouseffluentsreleasedIt: unrcetrict.f arcas (see Figure 3.11-1) shall be limited to the following: %, free. cu.L. rs=Le-U, $rou. he. sih. During any calendar quarter to 4 7.5 mrem to any organM, a. Io. hr% M cdMa^ tj tM. 4o 615 m.rt.e. ib og evga. APPLICABILITY: At all times. / ACTION N With the calculat'ed dose from the release of radioiodines, radioactive , a. materials in particulate form, or radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents ( exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radio-i iodines and radioactive materials in particulate form, and radio- \\ nuclides (other than nobles gases) with half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, ) so that the cumulative dose or dose commitment to an individual from such releases during these four calendar quarters is within (15) mrem ( to any organ. -luvmis 2 t w ;h as.. eriee h idas for a::ign OL;ac:ive; in-- \\Q:" ~ II, IcCTRf0, 7.ppcadix I. s- _y J.t th: cr t i. ~, J._ licensee i; permitted under 100-~'"O, Arfundix-h -the flexibility of Operation, cc.patib1: uith considerations-of h;:lth rd : fety, t: :: ure that th: public is p.cridad ; depend:ble :: ::: sf power ev:n undcr unuc a1 oper:ti..3 m.dition;- whien ny temper rily rcault in r:1 :::: high:_ than such.e.~ mcel guide; for d::ign obj::tivcs but till within 1 v:1; that as;;r: that th: 2 :r ge p pul; tion :npesur is egmavaient t: :::11 freetient of d:;cs In natural 5: dground radicti:n. It is hemdud that in u:ing this eper' tion:1 ficnibth ey undcr unu;uci operating--ccaditiens, the liccare:.till ca... hu tc;t cfforts to keep icvel: ef ra44+aet4ve-eate 1=1 1.. efflum as ithin the nu crie:1 guide: fer dc;ivu OLj e ctive.a ( SURVEILLANCE REQUIREMENTS curve 4 cale+ala^. va E Gaml C curre4 c-M-4a^_ DoseCalculationsCumulativedosecentributionsforthhotet 4.11.2.3.1 ) 4ia s.d shall be determined in accordance with the ODCM at least once every 31 days. jt ( 4.11.2.3.2 Reports The semiannual Radioactive Effluent Release Report - e3 shall include the informatien specified in Specification 6.9.1 W. M. ~_ e M NM

BASES 3/4.11.2.3 DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NCBLE GASES G. C" This specification is provided to implement the requirements of Sections K.c., III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for The Operation are the guides set forth in Section 4VrA of Appendix I. 3 ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix.I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways in unlikely to be substantially underestimated. The ODCM calculational methods ;pp_rc: ty = for calculating the doses due to the actual release rates of the subject materials are :g in d t: ': consistent with the methodology provided in Regulatory Guide 1.109, " Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for r.he Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmosphoric conditions. The release rate specifications for radiciodines,and radioactive material in particulate formAare dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent e s sumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. , M mLowdMa o%ar b x f.te gases p 3/4 11-16

i U DI0 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RA0 WASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 5.1-3), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 4;*4) when averaged over 31 days would exceed 0.3 mrem to any organ. ,g_, 3 APPLICABILITY: At all times. ACTION: a. With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days or with gasecus waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specifica-tion 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information: 1. Identification of the inoperable equipment or subsystems and the reason for inoperability, 2. Action (s) taken to restore the inoperable equipment to CPERABLE status, and 3. Summary description of action (s) taken to prevent a rect.rrence. 5. The provithn ef Speci'ic:tien: 3.0.3 and 3.0.? are not ;pplic;ble SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the 00CM. 4.11.2.4.2 The GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days. -2% a i s i 3/411-317 (

i l BASES 3/4.11.2.4 GASEOUS IfASTE TREATtENT_ The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTIIA-TION EXHAUST TREATMENT SYSTEMS ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design criterion 60 of Appendix A to 10 CR part 50, and design objective Section iip of Appendix I to 10&R Part 50. The specified limits governing the use of appropriate portions of the doso % y Ch*cN* 2 systems were specified as a suitable fraction of the[ A set forth in Sections II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents. e O 3/4 11-18

O RADICACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE 'Hydrc;cr -icr :) t: : ret ~=c4; ::.: ' a ;a..a r hyd-c; r :xpl;;i:n) LIMITING CONDITION FOR OPERATION 6 3.11.2.54 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volume whenever the hydrogen concentra-tion exceeds 4% by volume. APPLICABILITY: At all times. ACTION: a. With the concentration of oxygen in the waste gas holdup system greater than 2% by volume but less than or equal 4% by volume, reduce the oxygen concentration to the above limits within 48 hours, b. With the concentration of oxygen in the waste gas holdup system greater than 4% by volume and the hydrogen concentration greater than 2% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% by volume within one hour, c. The provi;i;n;-of Spcificatica; 3. 0.2 56a 3.0.4 are not applicre+e. SURVEILLANCE REQUIREMENTS 6 4.11.2.68 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the hydrogen 9 and oxygen monitors required OPERABLE by Table 3.3-E3 of Specification 3.3.3.ht. 12 Enscs 3/4.11.2.44 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. (Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration below the flammability limits.) Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Fart 50. 3/4 11-172o ,~ n-573-t-

} RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LI!4ITING CONDITION FOR OPERATION _ 3.11.2.7 The quantity of radioactivity contained in each gas storage tank shall be limited to < 6000 curies noble gases (considered as Xe-133). APPLICABILITY: At all times ACTION: With the quantity of radioactive material in any gas storage tank a. exceeding the above limit, suspend all additions of radioactive material to the tank and within 48 hours zitM r reduce the tank contents to within the limit.c,: pr^"iA-prr rt n:tifi;; tion t:r the cc ric;ien pursue.L Lv.;fowifisoim. '.^.1.11. se wilii a fell:=p :: pert ch:11 inclua.. Omow.lytiv.. vi activiLio, yl ...cd 2nd/or t 9 :n t: ::du:; th, L.a,0.im..;; te within ;h 1~;;

14. 4 +. -

SURVEILLANCE REQUIRE!!ENTS 4.11.2.7 The quantity of radioactive material contained in each i;;istcd gas storage tank shall be determined to be within the above limit at least once per 24 hours when radioactive materials are being added to the tank. BASES 3/4.11.2.7 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure." ~,. 3/4 IJ-21

RADICAC*IVE EFFLUENTS 3/4.11.3 SOLID RADIOACTIVE WASTE, Q g g ggggp LIMITING CONDITION FOR OPERATION The solid radwaste system as described in the PROCESS CONTRCL 3.11.3.1 p PROGRAM shall be OPERABLE and used t: pr: tide for the SOLIDIFICATION and g packaging of radioactive wastes to ensure meeting the requirements of 10CFR Part 20 and of 10CFR Part 71 prior to shipment of radioactive waste from the site. APPLICABILITY: At all times. 10 cFL PcuT lb L/er l CFA-Pat m ACTION: NN With the4 requirements of 6 F.c^CCCC CO:TEOL 20^" = ef w ifica;.ien 3 a. 4,44-not satisfied, suspend defectively packaged shipments of solid radioactive wastes from the site. SURVEILLANCE REQUIREMENTS 4.11.3.1 4 The solid radwaste system shall be demonstrated CPERABLE at least once per 92 days, :: th:re be 9e "re!lig for CC'_"TrIC' !C!: d .~~w.. _m<.,,, m.,. n. ,,.e

um c e;,;i. 4,- 3312..

63: ~ q With the solid radwaste system inoperable for more than 31 days, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days pursuant to Specification / 6.9.2 a Special Report which includes the following information: 1. Identification of the inoperable equipment or subsystems and the reason for inoperability, 2. Action (s) taken to restore the inoperable equipment to ( / OPERABLE status, I / 3. A description of the alternative used for SOLIDIFCATION and j packaging of radioactive wastes, and 1 4. Summary description of action (s) taken to prevent a recurrence. s l / ~m l 1 ( 3/4 1-1-22 l I

U i' SURVEILLANCE REQUIRE!!ENTS (Continued) By performance of functional tests of the equipment and com-a. ponents of the solid radwaste system. b. By operating the solid radwaste system at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM. Verification of the existence of a valid contract for SOLIDIFI-c. CATION to be performed in accordance with a PROCESS CONTROL PROGRAM. tow %. 4.11.34.2 The PROCESS CONTRO PROGPRI ;f O : ifi. -. 0.l? shall be used to verify the SOLIDIFICATION of at least one representative test specimen from at least everyXhu dredth batch of each type of wet radioactive (e.g., filter sludges, spent resins, evaporator bottoms, boric acid waste solutions, sodium sulfate solutions, and filter media). The test specimens shall be processed in the radiochemical or waste processing laboratory in accordance with procedures of the PROCESS CONTROL PROGRAM. If any test specimen fails to verify SOLIDIFICATION, the SOLI-a. DIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, al-ternative SOLIDIFICATION parameters can be determined in ~ accordance with the PROCESS CO:: TROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM. b. If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall pro-vide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until 3 consecutive initial teru specimens demon-strate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.14, to assure SOLIDIFICATION of subsequent batches of waste. 4.ll.3d$.3 Reports - The semiannual Radioactive Effluent Release Report shall include the following information for each type of solid waste shipped offsite during the report period: 66E a. container ~. volume, g A5 b. total curie quantity (determined by measurement or estimate), l 3/4 11-23 1

SUFVIILLA!;CE REQUIFI.!'I!;TS(Continued) principal radionuclides c. estimate), (determined by measurement o g(( r d. ,,6 type of waste df evaporator bottoms),(e.g., spent resin, compacted d ry waste

b e.

type of container (e.g., LSA Quantity), , Type A, Type B, Large and f. solidification agent (e.g., cement, Bl.ES_ urea formaldehyde). 3f4.11.3 SOLID RADIOACTIVE WASTE will be available for use wheneverThe OPERABI e system ensures that the system packaging prior to being shipped offsit the requirements of 10 CFR Part 50 3 solid radwastes require proc e. 6a and General Design criteria 60This s Appendix A to 10 CFR Part 50 ing the PROCESS CO!; TROL PROGRA!! may i The process parameters used in est bli of type, waste pH, waste / liquid /s lidification agent / catalyst ratinclude, but are a sh-oil content, waste principal chemical o times. constituents, mixing and curing os, waste 6 P 3/4 11-24

RADICACT:VE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months. APPLICABILITY: At all times. ACTION: a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-tion 3.ll.l.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.ll.2.3.a, or 3.ll.2.3.b, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4. This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report. If the estimated dose (s) exceeds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a v_riance in accordance with the provisions of 40 CFR 190 and including the specified information of 5 190.11(b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification. b. The provi;icn of Specification: 3.0.3 and 3.0.? ar: "et applie'"lec SURVEILLANCE REQUIREMENTS 4.11.4 Dose Calculations Cumulative dose contributions from liquid and l gaseous effluents snall be determined in accordance with Specifications 4.11.1.2, i 4.11.2.2, and 4.11.2.3, and in accordance with the ODCM. l SL2 ;!; ; 3/4 11-25

245ES 3/4.11.4 TOTAL DOSE This specification is provided to meet the dose Ifmitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the calcylated doses from plant radioactive effluents exceed twice the design objective doses of Appendix 1. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commit-ment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site,or within a radius of 5 miles must be con-sidered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. An individual is not considered a member of the public during any period in which he/she is engaged in carring out any operation which is part of the nuclear fuel cycle. l l l

REVIEW _ 6.5.2.7 The SRC shall review The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments ccepleted under the50.59 a. provision of Sectiondid not w nstitute an unreviewed safety question. n Proposed changes to procedures, equipment or syste b. 50.59,10 CFR. Proposed tests or experiements which involve an unreviewed 50.59,10 CFR. safety question as defined in Section c. i Proposed changes to Technical Specifications of this Operat ng d. License. Violations of codes, regulations, orders, Technical Specifi-cations, license requirements, or of internal procedures or e. instructions having nuclear safety significance. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect f. nuclear safety. Events requiring 24 hour written notification ce the Commiwien. g. in All recognized indications of an unanticipatea deficiency some aspect of design or grasration of safety " slated structures, h. systems, or components. Reports and meetings Rinutes of the Plant Opetrating Review 1. Committee. l l 5-10 Amendment No. dB e

AUDITS y T 4 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the SRC. These audits shall encompass: o t l a. The conformance of facility operation to provisions contained 4.: ( within the Technical Specifications and applicable license conditions at least once per 12 months. .] b. The performance, training and qualifications of the entire da facility staff at least once per 12 months. g4 i "h c. The results of actions taken to correct deficiencies occurring j q in facility equipment, structures, systems or method of operation g .[ that affect nuclear safety at least once per 6' months. 5 Y y c-(j $ ( d. The performance of, activities required by the operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, .[ f, g at least once per 24 months. i f + [3 e. The Facility Dnergency Plan and implementing procedures at least ~ .3 " A once per 24 months. t, .s w 4 f. The Facility Security Plan and implementing procedures at least j g U, once per 24 months. a3 .! 1 g. Any other area of facility operation considered appropriate by the SRC or the Executive Director. l h *3.? n 3l ~ h. The Facility Fire Protection Program and implementing procedures at least once per two years. o g hJ 1. A fire protection and loss prevention inspection and audit shall }j Tj be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm. g j .? b% 9 gty5% j. An inspection and audit of the fire protection and loss prevention 3 a. O d program shall be performed by an outside qualified fire consultant m }3ag at intervals no greater than 3 years. k. The radiological environmental monitoring program and the results l ' y thereof at least once per 12 months. ,g t 1. The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months. I { AUTHORITY 6.5.2.9 The SRC shall report to and advise the Executive Director on g those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8. i Amendment No. 6-11

PICCRDS_ 18.7-1972. The Records will be maintained in accordance with ANSI d balows following shall be prepared, approved and distributed as indicate 6.5.2.10 d Minutes of each SRC meeting shall be prepared, app a. date of the meeting. h ll Reports of reviews encompassed by Section 6.5.2.7 above, s a I be prepared, approved and forwarded to the Executive Director b. within 14 days following completion of the review. ll be I Audit reports encompassed by Section 6.5.2.8 above c. fter tions responsible for the areas audited within 30 days a completion of the audit. CHARTER _ pproved Conduct of the cc::mittee will be in accordance with a charter, a tion of the l by the Executive Director, setting forth the mechanism for implementa 6.5.2.11 coc=tittee's responsibilities and authority. REPORTABLE OCCURRENCE ACTION _ 6.6 S he following actions shall be taken for REPORTABLE OCCURRENCE 6.6.1 The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9. a. Each REPORTABLE OCCURRENCE requiring 24 hour notification to b the Commission shall be reviewed by the PORC and a report su - b. PC and mitted by the Resident Manager to the Chaism of the S Manager-Nuclear Operations. SAFETY LIMIT VIOLATION _ 6.7 i it is The following actions shall be taken in the event a Safety L m

6.7.1 violated

l The reactor shall be shut down and reactor operation shall on y ( ) (1) (i). be resumed in accordance with the provisions of 10 CFR 50.36 c I a. The Safety Limit violation shall be reported immediate b. Conmission. will be notified within 24 hours. h PORC. A Safety Limit Violation Report shall be prepared by t e ding This report shall describe (1) applicable circ'.:mstances c. ka ponents, systems or structures, and (3) corrective action ta e the occurrence, to prevent recurrence. 6-12 Amendment No. - - - ~ ~ - - -

I .6 The Saf ety Limit violation P.eporr shall be sul-itted to the 5 Cc:: mission, the Chai:=an of the SRC and the !!:e.ager-Nuclear 3 d. Operations by the Resident Manager. d L, .f..$ 6.8 Written procedures shall be established, implemented and maintaine PROCEDURES d s h 6.8.1 covering the activities referenced below: 7g The applicable procedures recc= mended in Appendix"A" of Regulatory e d a. }$ Guide 1.33, November, 1972. I g - Ph b. The radiological environmental monitoring program. 4 T dd a 4 -p

o Refueling operations.

t } c. Surveillance and test activities of safety related equipment. d d. 03 V Security Plan implementation. e. O U:m.1 - n ,{ Ol-f. Emergency Plan implementation. g '~< # g. Fire Protection Program implementation. a. I f.m Offsite Dose calculation Manual implementation. \\ h. Tecporary changes to procedures above may be made provided: 6.8.2 The intent of the original procedures is not altered. a. The change is approved by two members of the plant staff, at lcast one of whom holds a Senior Reactor Operator's license b. on the unit affected. The change is docu=ented, reviewed by the PORC and approved by the Resident Manager within 14 days of implementation. c. d Each procedure of 6.8.1 above, and changes thereto, shall be reviewe d by the PORC and approved by the Resident Manager prior to implementa 6.8.3 reviewed periodically as set forth in mAm%istrative procedures. 6.9 REPORTING REQUIRDd.ENTS_ ROUTINE REPORTS AND REPORTABLE OCCURRENCES 10, Code In addition to the applicable reporting requirements of Title d to the Director of Federal Regulations, the following reports shall be sul 6.9.1 i td 6-13 Amendment No. l

START-UP REPCRT 6.9.1.1 A summary report of appropriate plant testing shall be submitted following (1) an amendment to the license invelving a planned increase in power level, (2) installation of fuel that has a different design and (3) modifications that may have significantly altered the nuclear, thermal, or hydraulic performances of the plant. The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the testing and a comparison of these values with acceptance criteria. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report. 6.9.1.2 Start-up reports shall be submitted within (1) 90 days following completion of the start-up test program, (2) '90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Start-up Report does not cover all three events (i.e., initial criticality, completion of start-up program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed. A WJAL RADIATICN EXPOSURE REPORTS 6.9.1.3 A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associsted man rem exposures according to work and job functions, 1/ e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance, waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions. A WJAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.4 Routine radiological environmental operating reports covering the l cperation of the unit during the previous calendar' year shall be cubmitted prior to May 1 of each year. 6.9.1.5 The annual radiological environmental operating reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological. environmental surveillance activities for the report period, includ-ing a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the milk animal census required by Specification 3.12.2. If harm-ful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem. 1/ This tabulation supplements the requirements of 20.407 of 10 CFR Part 20. Amendment No. 6-14

4 The annual radiological environmental operating reports shall include [ summarized and tabulated results in the format of Table 6.9-1 of all radiological environmental saeples taken during the report period. In the event that some results are not available for inclusien with the report, the report shall be j submioted noting and explaining the reasons for the missing results. The missing i data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description i of the radiological environmental monitoring program including sample methods for each sample type, size and physical characteristics of each sample type, sarple preparation methods, analytical methods, and, measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from the plants the result of milk animal census required by the specification 3.12.2 and the results of licensee particpation in the Interlaboratory Comparison Program required by Specification 3.12.3. SEMIAlmUAL RADIOACTIVE EFELUENT RELEASE REPORT 6&J.;4 Reutine ::di L m cfflu..;.mlec.;c n g &L m oulu3 ic wc M ir cf -th e uuiL a ir.g ;lm prevume-0 wi.th: ;f spu otic.. :hril b " -itiel iU41u % -OysafterJanuaryIandJuly1ofeachyear. l t t 's j J a. The radioactive effluent release reports shall include f summary j of'the quantities of radioactive liquid and gaseous effluents t i and solid waste released from the unit as outlined'in Regulatory f . ) Guide 1.21, " Measuring Evaluating, and Reporting' Radioactivity { in Solid Wastes and Releases of Radioactive, Materials in Liquid i C i and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants",1witti data summarized on a quarterly basis following d g j the format of Appendix B thereof. I I y-x 7 'tb. The radioactive effibent release' reports shall include a summary + V i of the meteorological conditiens concurrent with the release of gaseous effluents during'each quarter as outlined in Regulatory i' Guide 1.21, with data surxtarized on a quarterly basis following the format of Appendix,B thereof. i \\d / \\ W c. The radioactive effluent release r'eports shall include the i \\/3 j following information for all unplanned releases to unrestricted ! areas of radioactive materials in gaseous and liquid effluents: i 1. A description of the event and equipment involved. l i N i 2. Cause (s) for the unplanned release, s, I s 3. Actions taken to prevent recurrence. N j [4. Consequences of the unplanned release. Amendment No.- 6-15

(,.4.14 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. d.. The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Apoendix 8 thereof, b. The radioactive effluent release report to be submitted 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaeous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and m caseous effluents to members of the public due to their activities inside the /Le b)g site boMry (FigureMM _ Eu 5.H) during the report period. All assump-tions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for deter-mining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). C. The radioactive effluent release report to be submitted 60 days af ter January 1 of each year shall also include an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operatin. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1. d. The radioactive effluents release shall include the following information for each type of solid waste shipped offsite during the report period: Container volume, J. Total curie quantity (specifiy whether determineu by measurement or estimate), 2-Principal radionuclides (specify whether determined by measurement or estimate), 3. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms), d. Type of container (e.g., LSA, Type A, Type 8, Large Quantity), and f. Solidification agent (e.g., cement, urea formaldehyde).

(2.9.l.A ad.) c. The radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis. f. The radioactive affluent release reports shnl include any changes to the PROCESS CONTROL PROGRAM (PCP) made during t<is reporting period. I 1

TABLE 6.9-1 G [NVIRONMENTAL RADIOLOGICAL M)NITORING PROGRAM SUP94ARY l p Docket No. Name of Facility l Reporting Period Location of Facility -(County 5 tate) 1 ta P Location with Highest Annual Mean Control Locations Nder of Type and Lower Limit 1 nean () b REPORIABL[ Medium or Patlway Total Nder of All Indicator tocations Mean(b)b OCCURRENC[5 Sampled of Analyses Detectiona Mean (1)b Name Range Range (Unit of Measurement) Perforted (LLD) Rangeb Distance and Direction I i i I I. e 96 %3 't t a. a g 0 l-

Noelnal Lower Llett of Deteckton (LLD) as defined in table notation a. of Table 4.11-3 of Specification 4.11.A.

Fraction of detectable measurements at specified locations is indicated in based upon detectable measurements only. bMean and ra parentheses ). [ kte: The example data are provided for 111ustrative purposes only. l

~ 6 w.- ) Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made r effective. In addition, a report of any major changes to the radioactive I waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the -{4httt kiu Cmd. P%r Opuu1;n Vuw Ces. \\ V rsm ___ -~- 1 l The rad oactive effluent release reports shall include any 1 e. c)anges to the Offsite Dose Calculation Manual (Coci) made / during the reporting period. j L MONTHLY OPERATIMO REPORT, i I 6.9.1.7 Routine reports of operating statistics, operating and shutdown experience and safety-related maintenance shall be rutnitted on a monthly basis to the Director, Office of Management Infer d :r and Program C:nte:1,- % s% "1 9 40 ::.ria to the Offi m uf R.:pectie.. r.J C.f a r.:nt, U. S. Nuclear Regulatory Co= mission, Washington, D. C. 20555,fno later than tBEsuyo follow-V 7 [1. ing the calendar month covered by the report. 8%et M uon* P. I 7 6.9.1.8 Each monthly operating report shall include P A tabulation of plant ope zating data and statistics. C C a. 1 b. A narrative su=sary of operating experience during the report period relating to safe operation of.the facility, including l k p-safety-related maintenance not covered in 6.9.1.8.c.5. below.2/ r For each outage or forced reduction in power M of over twenty percent of RATED PCWER where the reduction extends for greater [ c. than four hours: 3-1. The proximate cause and the system and major component involved (if the outage or forced reduction in power involved equipment malfunction) 5 2. A brief discussion of (or reference to reports of) any .+ reportable occurrences pertaining te the outage or power H reductions ?.'2 2j Any safety-related maintenance information not available for inclusion in the 7 monthly operating report for a report period shall be included in a subsequent J monthly operating report not later than 6 months following completion of such. l maintenance. y The term " forced reduction in power" is defined as the occurrence of a com-ponent failure or other condition which requires that the load on the unit be reduced for corrective action immediately or up to and including the very next ' Note that routine preventive maintenance, surveillance and calibra-weekend. tion activities requiring' power reductions are not covered by this section. s Amend =ent No. 6-17

Cerrective action taken to reduce the prehability of recurrence, 3. if c.ppropriates Operating time inst as a result of the outage or power re-4. duction (for scheduled or forced outages, 4/ use the generator for forced reductions in power, use the off-line hours approximate duration of operation at reduced power); A description of major safety-related corrective maintenance 5. performed during the outage or power reduction, including the system and component involved and identification of the critical path activity dictating the length of the outage or power reduction; and ' 6. A report of any single release of radioactivity or radiation axposure specifically associated with the outage which accounts for more than 10% of the allowable annual values. REPORTABLE OCCURRENCES 1 The REPORTABLE OCCURRENCES of Specifications 6.9.1.10 and 6.9.1.11 6.9.1.9 below, including corrective actions and measures to prevent recurrence, shall Supplemental reports may be required to fully describe be reported to the NRC. In case of corrected or supplemental reports, final resolution of occurrence. a licensee event report shall be completed and reference shall be made to the original report date. PROMPT NOTIFICATION WITH WRITTEN FOLIC 4-UP_ I The types of events listed below shall be reported within 24 hours by 6.9.1.10 telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate no later than the first working - The day following the event, with a written follow-up report within two weeks. a completed copy of a written follow-up report shall include, as a =4n4= =, Information provided on the licensee event report licensee event report form. form shall be supplemented, as needed, by additional narrative material to pro-vide complete explanation of the circumstances surrounding the event. Failure of the reactor protection system or other systems a. subject to limiting safety system settings to initiate the required protective function by the tire a monitored parameter reaches the setpoint specified as the limiting safety sys tam setting in the technical specifications or f311ure to complete i the required prctective function. 4/ The term " forced outage" is defined as the occurrence of a component failure or other condition which requires that the unit be removed frcun service for corrective action immediately or up to and including the very next weekend. l 6-18 Amendment No. w e me - -c

Operation of the unit or affected system when any parameter b. or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications. Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.}/ c. Reactivity anomalies involving disagreement with the pre-d. dicted value of reactivity balance under steady conditions during power operation greater than or equal to 1% ik/k; a calculated reactivity balance indicating a SHU2DOWN MARGIN less conservative than specified in the technical specifi-cations; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if suberitical, an unplanned reactivity insertion of more than 0.5% ik/ks or occurrence of any unplanned criticality. Failure or malfunction of one ormore components which pre-vents or could prevent, by itself, the fulfillment of the e. functional requirements of system (s) used to cope with acci-dents analyzed in the SAR. Personnel error or procedural inadequacy which prevents or f. could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the SAR. Conditions arising from natural or man-made events that, as g. a direct result of the event require plant shutdown, opera-tion of safety systems, or other protective measures required by technical specifications., Errors discovered in the transient or accident analyses or h. in the methods used for such analyses as described in the safety analysis report or in the bases for the tec%ical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses. Performance of structures, systems, or components that re-i. quires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of con-ditions not specifically considered in the safety analysis Leakage of packing, gaskets, mechanical joints and seal welds within the limits for identified leakage set' forth in technical specifications need 5/ Steam generator tube degradation need not be reported under this item. not be reported under this item except where leakage exceeds the limits of specification 3.1.F. I 6-19 Amendment No. ...ee. 6 me +

l jt. hTa reIsa m f (Adioc4t*wo A).TMs i% AdAym % e.m.a. % t_ u et qu4 a._ a.a.,.i 2.n.1. i. report or technical specifications that require remedial action or corrective measures to prevent the existence or develo ment See.Ca e e+f

of an unsafe condition.

[ 7 Exceeding the limits in Specification 0.' 1.2 or 3.11.2.4 for the The written storage of radioactive materials in the listed tanks. i I J, follow-up report shall include a schedule and a descript l specified limits. THIRTY DAY WRITTEN REPORTS I The types of events listed below shall be the subject of written 6.9.1.11 reports to the Director of the Regional Office within, thirty days of occu Information provided on the licensee event of the event. of a licensee event report form. report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding tha event. Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative than a. those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.6f Conditions leading to operation in a degraded mode permitted b. by a limiting condition for operation or plant shutdown re-quired by a limiting condition for operation.6f Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of c. degree of redundance provided in reactor protection systems or engineered safety feature systems. Abnormal degradation of systems other than those specified I' d. in 6.9.1.10.c above designed to contain radioactive material resulting frce the fission process.2/ An unplanned offsite release of 1) more than 1 curie of radio-active material in liquid effluents, 2) more than 150 curies e. of noble gas in gaseous effluents, or 3) more than 0.05 curies The report of an unplanned of radioiodine in gaseous effluents. offsite release of radioactive material shall include the following information: A description of the event' and equipment involved. 1. 6f Routine surveillance testing, instrument calibration, or pr except where test results themselves reveal a degraded mode as described. Leak- ]/ Sealed sources of calibration sources are not included u i for identified leakage set forth in technical specifications need not be re-ported under this item. I 6-20 Amendment No.

2. Cause (s) for the unplanned relea*s. 3. Actions taken to prevent recurrence. 4. Consequences of the unplanned release, n -__ ~ l f. Measured levels of radioactivity in an environmental sampling medium l determined to exceeo the reporting level values of Table-ht@d when 1 avera quarter sampling period._ y --are-detecta la iha sampliny maiunr,-this ers i, shall ba A

"k *

(o.9 -1.- I consentsation-il-I ,+ cunwouts % n (2) t. .-1 reporting levef7f) reporting level (2) Nhen radionuclides other than those in Table 6.9-2 are detected and are the results of plant, effluents, this report shall be, submitted if the potential annual dose to an individual is l l equal to or greater than the calendar year ihnits of Specifi-cations 3.11.1.2, 3.11.2.2/and 3.11.2.3. This report is not re ! " quired if the measured level of radioactivity was not the result of plant effluentsi however,-in such an.~ event, the /* f. j condition shall be reported and described in the An:iual P,Idioy/ / i logigalEnvironmentalgeratingReport/ l [ t SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification: a. Sealed source leakage on excess of limits (Specification 3.9) b. Inoperable seismic Monitoring Instrumentation (Specification 4.10) c. Primary coolant activity in excess of limits (Specification 3.1.D) d. Seismic event analysis (Specification 4.10) e. Inoperable fire protection and detection equipment (Specification 3.14) f. Operation of Cverpressure Protection System (Specification 3.1. A.3) g. Radioactive effluents (Specification 3/4.11) h. Radiological environmental monitoring (Specification 3/4.12) 1. Meteorological monitoring instrumentation (specification 3.15)

j. Radioactive Liquid Effluent Instru=entation (Specification 3.3.3.8) k.

Radioactive Gaseous Effluent Instrumentation (Specification 3.3.3.9) l Amendment No. 6-21

s t TABLE 6.9-2 LES_ REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN EINIROt#4 Reporting Levels Fish Milk Vegetables or Gases (PC1/m3) (pC1/Kg, wet) (pC1/1) (pC1/Kg, wet) Airborne Particulate Water Analysis (pC1/1) 4 H-3 2 X 10 4 3 3 X 104 Mn-54 1 X 10 i x so 4 E-59 4 x so* 3 X 10 3 Co-58 1 X 10 4 1 X 10 2 4 co-60 3 X 10 2A 40 e b-Z.n-66 3 X 10*2 Zr-Nb-95 4 X 10 3 1 X 102 O 0.9 'l I-131 2 3 3 60 1 X 10 1 X 10 10 Ca-134 30 3 70 2 X 103 2 X 10 20 Cs-137 50 3 X 102 2 Ba-La-140 2 X 10 (a) For drinking water samples i l i

6.10 PICORD PITD."* ION _ The following records shall be retained for at least five years: P 6.10.1 Records and logs of facility operation covering time interval a. at each power level. Records and logs of principal maintenance activities, in-spections, repair and replacement of principal items of b. equipment related to nuclear safety. ALL REPORTABLE OCCURRCiCES submitted to the Comission. c. Racords of surveillance activities, inspections and calibrations d. required by these Technical Specifications. Records of changes made to Operating Procedures. e. Records of radioactive shipments. f. Records of sealed source and fission detector leak tests and g. results. Records of annual physical inventory of all source material of h. record. Records of reactor tests and experiments. i. The following records shall be retained for the duration of the 6.10.2 Facility Operating Licenses Records of any drawing changes reflecting facility design modifications made to systems and equipment described in a. the Final Safety Analysis Report. Records of new and irradiated fuel inventory, fuel transfers b. and assembly burnup histories, Records of facility radiation and contamination surveys, c. Records of radiation exposure for all individuals entering d. radiation control areas. Records of gaseous and liquid radioactive material released e. to the environs, Records of transient or operational cycles for those facility cenponents designed for a limited nun.ber of transient cycles. f. Records of training and qualifications for current members g. of the plant staff. I 6-23 Amendment No. dB ?

h. Records of in-service inspections perfor=ed pursuant to these Technical Specifications.

i. Records of Quality Assurance activities required by the QA

Manual,

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 GR 50.59.

k. Records of meetings of the PORC and the SRC. 1. Records of analyses required by the radiological environmental monitoring program. 6.11 RADIATION AND RESPIRATORY PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection sha?.1 be prepared con-sistent 'rith the requirements of 10 GR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure as to maintain exposures as far below the limits specified in 10 GR Part 20 as reason-able achievable. A respiratory protection program as described in Regulatory Guide 8.15, Revision 0, will be developed and implemented for respiratory equip ' ment, as required in 10 GR 20.103 (f). 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 GR 20, each high radiation area in which the intensity of radiation is 1000 mrem /hr or less and 100 mrem /hr or greater shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit *. Any individual or group of individuals permitted to enter such areas shall be provided or accompanied-by one or more of the following: A radiation monitoring device which continuously indicates a. the radiation dose rate in the area. l b. A radiation monitoring device which continuously intagrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made l knowledgeable of them. Health Physics Personnel shall be exempt from the RWP issuance requirements l for entries into high radiation areas during the performances of their assigned radiation protection duties, provided they comply with approved l radiation protection procedures for entry into high radiation areas. Amendment No. 6-24 g

An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. c. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit. The requirements of 6.12.1, above, shall also apply to each high radiation area in which the' intensity of radiation is greater than 1000 mrem /hr. 6.12.2 In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the shift supervisor on duty and/or the plant Radiological and Environmental Superintendent or his designee. / [ 6.13 orrsITE coSE' CALCULATION MANUAL (CD 3) 0 ( 6.M.1 The 00CM shall bq approved by the Ccmmission prior to implementation. 1 6 6.M.2 Licensee initiated changes to the 00CM: 1. Shall be submitted to the Commission in the Monthly Operating Report within 90 days of the date the change (s) was made effective. This submittal shall contain: Sufficiently detailed information to totally support the rationale a. for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with I appropriate analyses or evaluations justifying the change (s); b. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and Documentation of the fact that the change has been reviewed and \\ c. found acceptable by the -413RGK Pof.c. Shall become effective upon review and acceptance by the W fof C. 2. LJ % l l I 6-25 Amendment No. e

14-

6. SiF PROCESS CONTROL PROGRAM (PCP) 14 6.13.1 The PCP shall be approved by the Commission prior to implementation.

e4 6.15.2 Licensee initiated changes to the PCP: 1. Shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain: a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; b. A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c. Documentation of the fact that the change has been reviewed and found acceptable by the M PoEc.. 2. Shall become effective upon review and acceptance by the M PoAc.. 6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and solid) 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid): 1. Shall be reported to the Commission in the Monthly Operating Report for the period in which the evaluation was reviewed by the:$tsst a-A- G--7 ;, The discussion of each change shall contain: 4y 3 a. A summary of the evaluation that led to the determination that 4 the change could be made in accordance with 10 CFR 50.59; e1 b. Sufficient detailed information to totally support the reason for the change without benefit of. additional or supplemental i information; 12 A detailed description of the equipment, components and processes 'g. c. involved and the interfaces with other plant systems; E. d. An evaluation of the change which shows the predicted releases [ of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; .P An evaluation of the change which shows the expected maximum e. exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto; f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; j l

6 (o.IS (Cat g. An estimate of the exposure to plant operating personnel as a result of the change; and h. Documentation of the fact that the change was reviewed and found acceptable by the 448R0$. foR.C. 2. Shall become effective upon review and acceptance by the M_ polc, i l l l \\ . _ _.}}

ML19309H038

Contents

Text

Dear Mr. Berry:

Enclosures:

6.7.1 violated

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ML19309H038

Text

Dear Mr. Berry:

Enclosures:

6.7.1 violated

Navigation menu

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