ML20029C644

Amend 89 to License NPF-30 Revising TS Re Changes to Submittal Frequency for Radioactive Effluent Release Rept

ML20029C644
Person / Time
Site:	Callaway
Issue date:	04/14/1994
From:	Wharton L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20029C645	List: ML20029C644 ML20029C646
References
NUDOCS 9404200364
Download: ML20029C644 (9)

Text

.

l

.gq

,=w\\

i 4

. UNITED STATES 3

.j-'

N4 f j NUCLEAR REGULATORY COMMISSION

. O f

WASHINoTON. D C. 2'J0f4 0001 s....-[

i 3

1 UNION ELECTRIC COMPANY LAllAWAY PLANT UNIT 1 DOCKET NO. 50-483 AMENDHENT TO FACILITY OPERATING tlCENSE Amendment No. 89 l

License No, l'PF-30 l

1.

The Nuclear Regulatory Comission (the Commission) has found that:

.)

A.

The application for amendment filed by Union Electric Company (UE, the licensee) dated September 24, 1993, complies with'the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in -10 CFR Chapter I, 3

i i3.

The facility will operate in conformity with'the applicatien, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; 0.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety'of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

j

^

2.

Accordingly, the license is amended by changes to the Technical Spectitcations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. HPF-30 is hereby 1

amended to read as follows:

-j I

i i

9404200364 940414 PDH ADOCK 05000403

)

p PDR

- -.m, r

,~

.m.3....,,..v,.,,,m,.~-sime,,.-u-w,-,,,.,,,,,,-,,,-------.,

- i' (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised I

through Amendment No. 89, and the Environmental Protection Plan contained 'in Appendix B, both of which are attached hereto, are hereby incorporated into the license. VE shall operate the facility.

in accordance with the Technical Specifications and the i

Environmental Protection Plan.

3.

This license'emendment is effective as of its date of issuance.

The Technical Specifications are to be implemented within 30 days from the i

date J N uance.

1 FOR THE NUCLEAR REGULA ORY COMMISSION Q

dykbl(

L. Raynard Wharton, Project Manager Project Olrectorate III-3 Division of Reactor Projects !!!/IV/V Office of Nuclear Reactor Regulation Attcchment:

Changes to the Technical Specifications Date of issuance:

April 14, 1994

'I i

.-r.'

=

w. w m --, - -, - - - - ---,,v - -.

- - - - _ -......-_x_

i re l

{

6TTACHME!tLT TO LICENSE AMEtlDHEtlT fl0 fs9 OPERATING llCINSE NO NPF-30 l-DOCKET NO. 50-481

'l

i Revise Appendix A Technical Specifications by removing the pages identified

j below and inserting the enclosed pages.

The revised pages are identified by il the captioned amendment number and contain marginal lines indicating the area of change.

The corresponding overleaf page is also provided to maintain document completeness, I

BLMQVI LilSIFl i

i XX XX l

1-4 1-4 i

3/4 11-1 3/4 11-1

}

3/4 11-3 3/4 11-3 f

ll 6-20 6-20 6-25 6-25 i

l

{

\\

l 1

\\

1 a

r.

.._f.

~ -

J J.

inou ADMINISTRATIVE CONTROLS 5i!ClL%

emf.

6.5.2 HUCLEAR SAFETY REVIEW BOARD (HSRB) function 6-9 Composition 6-10 Alternates 6-10 Consultants

. 6-10 Heeting frequency

. 6-10 Qualifications

. 6-10 Quorum

. 6-10 Review

. 6-11 Audits

. 6-11 Records

. 6-12 6.5.3 TECHNICAL REVIEW AND CONTROL Activities

. 6-13 Records 6-14 5.0 REPORTA3LLEyENT ACTION 6-14 1

6,7 S AJ.ET Y L IM I T V IOL AT IM....................

6-14 (J

PROCIOVRES AND PRQGRAMS 6-15 kJ REPORT E d [QUIREMENTS 6.9.1 ROUTINE REPORTS i

6-19 Startup Report

................, 6-19 Annual Reports 6-19 Annual Radiological Environmental Operating Report 6-20 Annual Radioactive Effluent Release Report 6-20 l

Monthly Operating Report 6-21 Core Operating Limits Repo,t 6-21 6.9.2 SPECIAL REPORTS 6-21 f.J0 R EC ORD RHmi1M.......

. 6-21 (JI_MQIAT10!LfBl{H10N PROGPAM...

j 6-23 j

CALLAWAY - UNIT 1 XX knendment No. 28, 40, SS,89 j

i

I I

!!iDE X i

i ADMitil5TRATIVE C0iiTROLS SECTION PAGE 6.1 R E S P0 N S I B i l l T Y.................................................

6-1 r

6.2 ORGANIZ AT 1_0!i 6.2.1 ONSITE Atl0 0FF5ITE ORGAtlIZAT!0N...............................

6-1 l

6.2.2 UNIT STAFF...................................................

6-2 l

FIGURE 6.2-!

DELETE 0................................................

6-3 l

FlGURE 6.2-2 DELETED.............................................

6-4 l

IABLE 6.2-1 MI N I MUM SH IF T CREW COMP 051T !0!i..........................

6-5 i

1 6 2.3 INDEPENDENT SAFETY ENGINEER!tiG GROUP (ISEG)

L Function......................................................

6-6 Composition.......................

6-6 Responsibilities........................

6-6 Records.....................................................

6 6 6.2.4 S H I F T T E C H ti ! C A L A DV I SO R......................................

6 - 6 6.3 Ut!!T STAFF QUALIFICATI0t15.......................................

6-6

6. 4,, _T R A l ti ! NG,....

6-7 6.5 REVIEW AND AUDIT

~

6. ~. 1 ON.51TE REVIEW C0!NITTEE (ORC) function...,

6-7 l

Composition.................

6-7 i

Alternates.................................................... G-7 Me e t i n g F r eq u e n c y.............................................

6-7 Quorum...........................

6-7

.^

Responsibilities................

6-3 Records.....

6-9 CALLAWAY - UNIT 1 x1x Amendment No. 37 m,

m_

t l

_n

,i W

W,.

LEFINITIONS r

E _ AVERAGE O!SINTEGRATION EtlERGY 1.12 C shall be the average (weighted in proportion to the concentration of I

each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and ganma energies per disintegration (in MeV) for isotopes, other than todines, with half-lives greater than 15 minutes, making up at least 957, of thc total noniodine activity in the coolant.

ENGINEE, RED SAFETY FEATURES RESPONSE TIME 1.13 The ENGillEERED SAFETY FEATtJRES (ESF) RESPONSE TIME shall be that time

]

[

interval from when the monitored parameter exceeds its EST Actuation Setpoint j

at the channel sensor until the ESF equipment-is capable of performing its -

i safety function (i.e., the valves travel to their required positions, pump l'-

discharge pressures reach their required values, etc,). Times snall include diese) generator starting and sequence loading delays where applicable.

FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance l

Requirements shall correspond to the intervals defined in Table 1.1.

10ERTIFIED LEAKAGE 1.15 IDENTIFIED LEAXAGE shall be:

l Leakage (except CONTROLLED LEAXAGE) into closed systems, such as a.

pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank i or 9

l f

b.

Leakage into the containment atmosphere from~ sources that are both specifically located and known either not to Interfere with the operation of leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or Reactor Coolant System leakage through a steam generator to the c.

Seconda ry Ecolan t Sys tem.

My>iERRELAY_TMT 1.16 A MASTER RELAY TEST shall be the energi2ation of each master relay and.

I verification of OPERABIL11Y of each relay.

The MASTER RELAY TEST shall include a tantinuity check of each associated slave relay.

MEMBE,R(5) Of i4E PUBLIC 1,17 MEMBER (S) 0F THE PUBLIC'shall include all persons who are not occupa.

l T

tionally associated 'with the plant.

This. category does not. include employees.

of the licensee, its contractors or vendors.

Also excluded from this category

- are persons who enter the site to service equipment or.to make deliveries.

Inis' category does include persons.who use portions of the site for_ retred-tional, occupational, or other purposes rat associated with the plant.

(ALLAWAY - UMit.1 1 '3 -

Amendment No'. 13, Ti, 58 s

4

-.e

OtrlNITIONS QLD l!E 09.5 LCALCMLA U91 MANV%

1.18 The OffSITE 005E CALCULATION MANUAL (00CH) shall contain the methodology and parameters used in the calculation of of fsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid ef fluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Manitoring Program.

The ODCH shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Honitoring Programs required by Section 6.8.4, and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Ef fluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.7.

l OPIPMLL.0PIPMlLlH 1.19 A system, subsystem, train, component or device shall be OPERABLE or have OPE PABILITY when it all necessary attendantis capable of performing its specified function (s), and when instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the

system, subsystem, train, ccmponent, or device to perform its function (s) are also rapable of performing their related support function (s).

OP!? ail @ Lf90L - MQOE 1.?0 An GPERAI!ONAL HODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

PMSIC Li(STS 1.21 PHf 5ICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the core and related instrumentation:

(1) described in Chapter 14.0 of the FSAR, or (2) authorized under the provisions of 10 CFR (0.59, or (3) otherwise approved by the Commission.

fEl55V?L20$0ARLLEAKME 1.7' PRES 5URE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nont solable fault pipe wall, or vessel wall.

in a Reactor Coolant System component body, PF0({ R (ON!POU'E00?,Mi 1 2)

The PROCE55 CONIR01. PROGplJi shall cont ain the current formulas, sampling, anal ses, tests, and determinations to be mide to ensure that the processing and f

packaging of solid radioactive wastes based on demonstrated processing of actual simulated wot solid wastes will be accomplished in such a way as to assure or compliance with 10 CFR Parts 20, 61, and 71, and State regulations, burial ground requi ements, and other requirements governing the disposal of solid radioactive waste.

[VEGL ;_fV3G Di9 1.24 PURGi or PURGING shall be any controlled process of discharging air or gas frcm a confinerent to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner thit repl, cement air or gas is required to purt fy the confinement.

(AllAWAY - UNIT 1 1-4 Amendmen t No.ll, !!, 30, SS,89 nn,6WrerWWW:wmwwwwanvnwnmmsewnwnmwmmmmmmeranw'rnmmw mm,mme.n

FJQl0 ACTIVE EfflUM11 y'

Ll@lDR@P TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to 150 Curies, excluding tritium and dissolved or entrained noble gases:

Reactor Hakeup Water Storagt Tank, a.

b.

Refueling Water Storage Tank, Condensate Storage Tank, and i

c.

d.

Outside temporary tanks, excluding demineralizer vessels and the liner being used to solidify radioactive waste.

AE_PMASlLill: At all times.

ACl1Q!!:

1 With the quantity of radioactive material in any of the above a.

listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the i

events leading to this condition in the next Annual Radioactive Ef fluent Release Report, pursuant to Specification 6.9.l.7.

l b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added and within 7 days following any addition of radioactive material to the tank.

I;<

CALLAWAY - UNIT !

I 3/4 11-1 Amendment No. 53.89

)

'i r e r u,%=n"x v7 n p,

a

. _ _ ~ _

\\

i i

EaDLOAW1LLE11&E!LU f3PL911vE GAS _HDTURE LLHJ11HG W101Il0N F91DPERAT10tl 3.11.2,5 The concentration of oxygen in the WASTE GAS HOLOUP SYSTEM shall be limited to less than or equal to 3X by volume whenever the hydrogen concentra-tion exceeds 4% volume.

APPLL(ADJ W l:

At all times KLL@

With the concentration of oxygen in the WASTE GAS HOLOUP SYSTEM a.

greater than 3% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, b.

With the concentration of oxygen in the WASTE GAS HOLOUP SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4x by volume, immediately suspend all additions of waste gases to the system and reduce the concentration on oxygen to less than or equal to 41 by volume, then take ACTION a. above.

the provision of Specifications 3.0.3 and 3.0.4 are not applicable.

r

{liVLLLLSMLEL@l@Ci(NTS 4.11.2.5 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 and oxygen monitors required OPERABLE by Specification 3.3.3.10.

(

(. A L L t.Wto UN11 1 3/4 11-2 Amendment No. 37, 30,86 t

%%-, n m,mm sevi s i~M""'

' '," ' " ",,nennm-~ ~~s 1

.I

M.010EI1YLff.LLVI!!U LAS STORASE_IANXS LIMITING CONDITION FOR OPERAT10N 3.11.2.6 tank shall be limited to less than or equal to 2.5 x 10The quantity of radio i

Curtes of noble gases (considered as Xe-133 equivalent).

APPLICABI(1)): At all times, f

Atl108:

With the quantity of radioactive material la any gas storage tank a.

exceeding the above limit, immediately suspend all additions of I

radioactive material to the tank and, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank contents to within the limit, and describe the events leading to this condition in the next Annual Radioactive Effluent Release l

Report, pursuant to Specification 6.9.1.7.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEliLANCE REQUIREMENTS 4 11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 7 days when radioactive materials are being added and within 7

)

days following any addition of radioactive material to the tank.

1 n

'i I

CAllAVAY - UNIT 1 3/4 11-3 Amendment No. 50,69

?

I 1

+

l 1

.5 ItiTENTIONALLY BLANK l

1

.i

.i

.1 1

i

-4

)

1 i

I

-)

l 1

i CALLMAf - l! NIT 1 3/4 11-4 through 3/4 11-18 Amendment fio.

50 deleted i

j 1

9

]

(

.,,. - - - -.,... -,.......,. - -,....,..... -,................ -...... -.... 1 l

4

_~

'I A3]iljilSTRAT!VE CONTROLS PROCCOURES AliD_ PROGRAMS (Continued)

Rad,iololifal_Environmenta l Moni toring Pro 2 ram (Continued) 9 3)

Participatton in a interlaboratory Comparisen Program to ensure that independent checks on the precision and accuracy of the measuronents of radioactive materials in eniironmental sample matrices are performed as part of the quality assurance program for environmental monitoring, f.]

REPORTING REQUIREMENTS t.

ROUTINE REPOR,TS

6. 9.1 in addition to the app 1tcable reporting requirenents of Title 10, Code f ederal Regula tions, the following reports shall be submitted to the Regional of s

Administrator of tne NRC Regional Of fice unless otherwise noted.

I 1

5 Tp3TU_ _,1E.P0R T P

f;. 9.1.1 A sumnary report of plant startup and power escalation testing shall be-sunnitted following:

(1) receipt of an Operating License. (2) amendment to the t icense involving a planned increase in power level, (3) installation of fuel that has a dif f erent design or has been manuf actured by a dif ferent fuel supplier, and (4) modifications that may have significantly altered the nuclear, r

thermal, or hydraulic performance of the plant.

fa. 9.1. 2 The Startup Report shall address each of the tests identified in the FSAR ard shall include a description of the measured values of the operating tonditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be

'i descrioed.

Any additional specific details required in license conditions based on other comitments shall be included in this report.

6. 9.1. ] Startup Reports shall be submitted within:

(1) 90 days following completion of the Startup Tes t Program (2) 90 days followinq resumption or i

comencment of commercial poner operation, or (3) 9 months following initial i

c ri tic 31i ty, whichever is earliest.

If the Startup Report does not cover all three events ( i. e., initial criticality, completion of Startup Test Program, and resumption or cow.encement of comercial operation) supplenentary-reports shall be submitted at least every 3 months until all three events have been i

completed, I.

AZUAL.R.E POR.T.S.

6.4.1.4 Annual Reports cosering the activities of the unit as described below b

for tne urevious n 'endar year shall be submitted prior to March 1 of eacn I

vejr.

Ihp in t (' } } t'eport irall be sutFrit ted prior to March 1 of the year follfwinq

• ) t t i f l l r t t T C a l l f, y.

(AbtkakI L

,,k b* 9 endment No. //, 50

[

[

f ADMINISTRATIVE CONTROLS M!iVALRRORD (Continued) 6.9.1.5 Reports required on an annual basis shall include a tabulation on an contractors) receiving exposures greater than 100 mrems/yr a associated man-rem exposure accordin reactor operations and surveillance,g to work and job functions, *e.g.,

inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing refueling.

The dose assignments to various duty functions may be estimated

, and based on pocket dostmeter, ILO, or film badge measurements.

totalling less than 20% of the individual total dose need not be accountedSmall exposu

for, in the aggregate from external sources s,hould be assigned to specific major work fu which the primary coolant exceeded the limits of Specificat following information shall be included:

The hours prior to the first sample in which the limit was exceeded:(1) Reactor power of the last isotopic analysis for radiotodine performed prior to exceeding the (2) Results limit, results of analysis while limit was exceeded and results of one analysts after the radiolodine activity was reduced to less than limit.

result should include date and time of sampling and the radiciodine Each concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the prtmary coolant exceeded the radiolodine limit.

flRW3 LM 0 l 0 L Q 0 lML E U11R0!M tLIALQEEMLI!!LRff 0RI 6.9.1.6 operat ton of the unit durinThe Annual Radiological Environmental Operating Repor before May 1 of each year. g the previous calendar year shall be submitted The report shall include sumaries, Environmental Monitoring Program for the reporting period. inte provided shall be consistent with the objectivos outlined in (1) the OOCH and The material (2) Sect tons IV.8.2, IV.B.3, and IV.C of Appendix ! to 10 CFR Part 50.

MMLM010MllVLEELVENIELEASLREf0RI 6.9.1.1 The Annual Radicastive Effluent Release Report covering the operat ion of the unit during the previous calendar year of operation shall be sulmitted before May I of each year.

released from the untt.the quantitles of radioactive liquid and gaseous efflu l

The material provided shall be (1) consistent with 5~,,36a and Sec t ion IV.8.1 of Appendix ! to 10 CFR Part 50.the o Inis tabulat mn swple.cnt s the requirements of $ 20.407 of 10 CFR Part 20.

CALLAWAY tm! T 1 6-20 Amendment No. H, SG,89 W pw m darmmnwamme"m*4

ADHINISTRATIVE CONTROLS

6. D PRQG1HRftiTRQL PROGPM (PCfl (Continued) b.

Shall becomo effective after review and acceptance by the ORC and the approval of the Plant Manager.

5.dLELS11LM1 lag 1!1 TION MANUAL (00clu Changes to the OOCH:

Shall be documented and records of reviews performed shall be retained a.

as required by Specification 6.10.2a.

This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix ! to 10 CFR Part 50 and not adversely impact tbc accuracy or reliability of effluent, dose, or setpoint calculattens, b.

Shall become effective after review and acceptance by the ORC and the approval of the Plant Manager, Shall be submitted to the Contnission in the fortn of a complete, c.

legible copy of the entire OOCH as a part of or concurrent with the Annual Radioactive Ef fluent Release Report for the period of the l

report in which any change to the OOCH was made.

Each chan identified by markings in the margin of the affected pages,ge shall be clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

CAttAWAY. UNIT 1 6-25 Amendment No. 53,39

,___----,,------s