ML17311A281
| ML17311A281 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/12/1994 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17311A282 | List: |
| References | |
| NUDOCS 9409230079 | |
| Download: ML17311A281 (42) | |
Text
'gpss RECg P
~
0 lA0 0 +w*e+
UNITED STATES NUCLEAR REGULATORY COMM(SSiON WASHINGTON, D.C. 2055&4001 9409230079 940912 DR ADOCK OgOOOS28
- PDR ARIZONA PUBLIC SERVICE COMPANY ET AL.
OCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
1 ENDMENT TO F CI TY OP RATING GENS 2.
Amendment No. 80 License No. NPF-41 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric
- Company, Southern California Edison
- Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated October 27,
- 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance
{i) 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 Commission's regulations; D.
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 Commission's regulations and all applicable requirements have been satisfied.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C{2) of Facility Operating License No. NPF-41 is hereby amended to read as follows:
0
'>I I
3.
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 80, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated into this license.
APS'shall operate the facility in accordance with the Technical Specifications and the-Environmental Protection
- Plan, except where otherwise stated in specific, license conditions.
This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications
'Theodore R. quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Date of Issuance:
September 12, 1994
!t
TTACHMENT TO L ENSE AMENDMENT AMENDMENT NO. 80 TO FACI ITY OPERATING LICENSE NO.
NPF-41 DOCKET NO.,'STN 50-528 Replace the following pages of the Appendix A Technical Specifications with the enclosed.pages.
The revised pages are identified by amendment number and contain. vertical lines indicating the areas of change.
Remove XVII
,)-4 6-20 6-.24 nsert XVII
)-4 6-20 6-24
0 4l
,"f I
DMINI STRATI VE CONiROLS
$fCTJON
~AG 6.5.3 NUCLEAR SAFETY GROUP (NSG)
FUNCTION...................................................
6-10 COMPOSITION................................................
6-10 CONSULTANTS.................,...............................
6-10 REVIEW o ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~
6-10 AUDITS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ o ~
6-11 AUTHORITYo o ~ o ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
6-12 RECORDS
~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o o ~ ~ ~ ~ ~
~ ~
6-12 6,6 R
POR A
VENT A T ON......................................
6-12 6.7 SAF TY IMIT VIOLAT ON..................,....................
6-13 6.8 PROCEDURES AND PROGRAMS......................................
6-13 6.9 REPORT NG RE UIREMENTS 6.9. 1 ROUTINE REPORTS.....................................
t4 STARTUP REPORT......................................
6-18 6-18 ANNUAL REPORTS.............................................
6-19 MONTHLY OPERATING REPORT............................
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT..
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT.......
s..
CORE OPERATING LIMITS REPORT........................
6-20 6-20 6-20 6-20a 6.9. 2 SPECIAL REPORTS.............................................
6-21 1
6 0
R COR R T NT ON............................................
6-21 6.
I RAD AT 0 PROT CT ON PROGRA................................
6-22 6.
2 H
GH RADIATIONAREA.....-.......-.....-....-....,...........
6-23 6.
3 PROC SS CONTROL PROGRAM (PCP)...............................
6-24 PALO VERDE UNIT 1 XVII AMENDMENT NO. ~~,-69.,
80
ADMINISTRATIVE CONTROLS INDEX SECTION PAGE
- 6. 14 OFFSITE 'DOSE CALCULATION &IANUAL 6-24
'g"
""'ND SOLID WASTE TREATMENT SYSTEMS 6'24'ALO VERDE - UNIT 1 XVIII AMENDMj.:NT NO.
DEFINITIONS CORE OPERATING LIMITS REPORT 1.9a The CORE OPERATING LiMITS REPORT is the unit-specific document that provides core operating limits for the current operating reload cycle.
These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Technical Specification 6.9.1.
Plant operation within these operating limits is addressed in individual specifications.
DOSE E UIVALENT I-131 1.1O,DOSE.E)UIVALENT I-131.shall be that concentration of I-131 (microcuries/
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 and Test Reactor Sites."
7 - AVERAGE DISINTEGRATION ENERGY 1.11 E shall be the. average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) -of the sm of the average beta and gamma energies per disintegration (in HeV) for isotopes, other than iodines, with half-lives greater than 15 minutes, making up at least 95X of the total noniodine activity in the coolant.
ENGINEERED SAFETY FEATURES
RESPONSE
TIHE
- 1. 12 The ENGINEERED SAFETY FEATURES RESPONSE TIHE shall be that time interval from when the monitored parameter exceeds its -ESF actuation setpoint at the channel sensor until the ESF equipment is, capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays where applicable.
IL
.1.13 The FREQUENCY NOTATION specified for 'the performance of Surveillance Requirements shall correspond to'the intervals defined in Table.1.1.
GASEOUS RADWASTE SYSTEM
- 1. 14 A GASEOUS RADWASTE SYSTEH shall be any system designed and installed to reduce radioactive gaseous effluents by.collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
1.15 IDENTIFIED LEAKAGE shall be:
a.
Leakage into closed systems, other than reactor coolant pump controlled bleed-off flow, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or 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 c.
Reactor Coolant System leakage through a steam generator to the secondary system.
PALO VERDE - UNIT 1 1-3 AMENDMENT NO. 69
EF INITIONS l.'16 Kz., is the k effective calcu'lated by cons'idering
'the actual CEA con~
figuration and assuming that the. fully or partiall,y inserted full-length CEA of the highest worth is fully withdrawn.
" BIRJKJIXWSLE
'1.17 MEMBER(S)
OF TH'E PUBI IC shall include all persons, who are not ocqupp-
,tionally associated with the plant.
This, category does not include emplpyqes, of the licensee, its contractors, or vendors.
Also excluded from this, category
.are persons who enter the site to service equipinent or,to,make deliveries, This category does include persons who use portions of the site for recrea-
'tional, occupational, or other purposes not associated with the plant.
OFFSIT OS CA CUI A Ot MANU~A~ODCfQ
,1.18 The OFFSITE 'DOSE CALCULATION MANUAL'(Ot)CM) sha'll contain the methodology and.parameters used in the calculation of,offsite doses resulting from, radioactive gaseous and liquid effluents,,in, tlute r:alculation of gaseous and liquid effluent monitoring Allan'/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program.,
The ODOM shall also contyini (1) the Radioactive Effluent Controls and Radiological Environmental Moniitoring Programs required by-Section.6.8.4, and {2) desIcriptions of the informatiion, that should be included in the Annua'l Radiolpgi,cal Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.7 and 6.9.1.8.
~0.
BllX<<"'1.19 A system, subsystem -.train, component, or device shall be OPERABLE or have OPERABILITY when.it
$ s capab'le of performing its specified functi,on(s) and when all necessary attendant instrumentation, controls, electrical, power,,
cooling or seal water, lubrication or other auxiliary equipment that are required for the.ystem,
. ubsystem, train, qomponent, or, device to perfo~,it~
function(s) are 'also capable of performing their related support funct,iop{s).
~RII I X MjO!
1.20 An OPERATIONAL MODE (i.eMODE) shaIll icorrqspond to any one inclusive combination of core reactivity condition,, power level, and cold leg reactor coolant temperature specified
'in Tattle 1.2.
PALO VERDE - UNIT 1 1-4 AMENDMENTNO.+8;-~ 80
ADMINISTRATIVE CONTROLS REPORTING RE UIREMENTS Continued
'6.9.1.2 The Startup Report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions 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 described.
'Any additional specific details required in license conditions based on other coceitments shall-be included in this report.
6.9.1.3 Startup reports shall be submitted within (I) 90 days following completion of the startup 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 Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.
ANNUAL REPORTS" 6.9. 1.4 Annual reports covering the activities of the unit as described below for the previous calendar year.shall be submitted within the first calendar quarter of each year..
The initial report shall, be submitted within the first calendar quarter of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis of.the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions,*" e.g., reactor, operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling.
The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20K of the individual total dose need not be accounted for.
In the aggregate, at least 80K of the total whole body dose received from external sources should be assigned to specific major work functions.
Annual reports shall also include the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.7.
The following information shall be included:
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.prior the the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one
- A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station.
- "This tabulation supplements the requirements of 520.407 of the 10 CFR Part 20.
PALO VERDE - UNIT 1 6-19 AMENDMENT NO. N, 62
'"'D4 analysis after the radioiodine activity wais reduced to less than limit.'ac'h result should include date and time of sampling, 'and the, radioiodine concentra-tions; (3) Clean-up system flow history s'tarting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the'irst sample in which the limit was exceeded; (4) Graph, of the I-131 concentrlation and one other radioiodine isotope concentr'ation',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 speciific actiivity of the, primary coolant exceeded tlhe radioiodine limiit.
~PMIWtlUIII 6.9.1.6 Routine reports of operating statistics and shutdown experience,,
including documentation of all challenges 'to'the safety valves, shall be
-submitted on a monthly basis to the Director, Office of Resource Hanagement U.S. Nuclear Regul;atory Commission, Mashington, D.C. 20555, with a copy to the, Regional Administrator of the Regional Offich of the NRC, no later than the, 15th of each month following the calendar moAth covered by the report.
0: Ll v'II: J ~AP T
6.9.1.7 The Annua'1 Rad'iological Environmental Operating Report covering the operation of the uinit,-during the previous calendar year shall be submitted before Hay 1 of each year.
lhe report shall include summaries, interpretations,,
aind analysis of trends of'he results iof the Radiological Environmental Ht>nitoring Program for the reporting period.
The material provided shall be consistent wi th the objectives outlined in (1) the ODCH'nd
~
(2) Sections IV.,B.i2,,IV,;B.3, and IV.C of Appendix I to 10 CFR Part 50.
N 1 ijFESjT ELE iJl~l 6.9.1.8 The Annual Rad'ioactive Effluent Release Report, covering, the operati'on of the unit during the previous calendar year shall be submitted before Hay 1
i of each -year.
The report shall include a'summary of the quantities of
'adioactive liquid and gaseous eff'luents and solid waste released from the unit.
The material provided shall be (I-)'consi'stent with the objectives outlined in the ODCH and PCP and (2) in c6nf6rmance <<rith 10 CFR 50.36a',and Section IV.B.1 of,Appendix I to 10 CFR Part 50.
- A single submittal'may'e made for a multi-unit station.
- A single submittal may be made for a multiple unit station.
1'he st/bmittal should combine thosie sections that are common~to all units at the staition;~
however, for units with
. eparate radwaste
- systems, the submittal shall specify the release of'adioactive materiial from each unit.
PALO VERDE UNIT I 6-20 AHENDHENT NO. M-,A+ 80
ADHINISTRATIVE CONTROLS 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 CFR'art '20, each high radiation area in which the intensity of radiation is greater.than 100 mrem/hr,but 'less than 10DD mrem/hr shall be, barricaded and conspicuously posted as a.high radiation area and entrance thereto 'shall be controlled'y requiring issuance of a Radiation Expo-sure Permit (REP)".
Any individual or group of individuals permitted to enter
.such areas shall be provided with or accompanied by one, or more of the
'.fol 1 owing:,
a.
A radiation monitoring device which continuously indicates the radiation:dose rate in the area.
b.
A radiation monitoring device:which continuously integrates 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'n the area has been established and personnel have been. made knowledgeable of them.
c.
A radiation protection qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the,
.activities.within the area and shall perform peri'odic radiation
,surveillance, at the frequency specified by the facility Radiation Protection Supervisor or his designated alternate in the REP.
6..12.2 In addition to the requ'irements of,Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in,'I hour a dose greater, than 1000 mrem shall be provided with locked doors.to prevent unauthorized entry, and the keys shall be main-tained under the administrative control of the.Shift Supervisor on duty and/or radiation.protection supe'rvision.
Doors shall remain locked except during periods of access by personnel:under,an approved
'REP which shall, specify the dose rate levels in the immediate work area and the maximum, allowable stay time.for individuals in that area..
For individual'reas accessible to personnel with: radiation levels such that a major portion of the body could receive in 1'hour a dose in excess of 1000 mrems*", that are located'within large, areas,
.such:as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then:that
'area:shall be roped off,.conspicuously posted and a 'flashing ':light,shall.'be, activated as a warning:device.
In lieu of 'the stay time specification of the REP, direct or remote (such as use of closed circuit TY cameras),continuous surveil,lance maybe made by personnel qualified in radiation, protection procedures to provide positive exposure control"over the
.activities within the area.
"Radiation Protection, personnel or personnel escorted by Radiation Protection
,personnel shall, be exempt from the REP issuance requirement. during the perform-ance of their assigned radiation, protection duties, provided they are otherwise following.plant radiation protection:procedures for entry into high radiation
- areas.
'""Measurement made at 18 inches from source of radioactivity.
PAL'0 VERDE - UNIT 1 6-23
'ANENDHENT. NO. Z7, 62
ADMINISTRATIVE CONTROL
'KILFJaA' LIAJ Changes to the PCP:
a.
Shall be rlocumented and records of reviews performed shall"be retained as required by Specificagiqn p.li0.2.qFa This documen$ atjon, shall contain:
(1)
'Sufficient information to support the change together wit.h the appropriate analyses or evaluations justifying the changq(s) hindi (2)
A determination..that the change will maintain the overall conformance of the sol'idified was'te'product to existing
>> equire-,
ments aif l=ederal, State, or other applicable regulationsi b.
Shall become effective after revtiew, aqd acceptance by the PRB and the approval of the Plant Nanage>>.,
~6. I OF OOlj AI I FJ MMAjMILllll OUS AN S 'AS REAPlENT J
I:IIILIae.mFJALl
~SY ~M+
- 6. 15.'1 Licensee-'initiated major changes,to,the radioactive waste systems (liquid, gaseous, and solid):
Shall
.bIe reported to the Comaission in thIe Annual Radioactlre Effluent Release Repiort, for the period in which the evaluation was,'eviewed.
by the PUB.
The discqssiorj of'ach change shall a)ntain:
1)
A summary of the evaluation that
'led, to the determination that the change could be made in accordance, with 10 CFR 50.59t Changes to the ODCN:
.a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6. 10e2.q.
This documentation shall contain:
(1)
Sufficient information to support the, change together with the appropriate analyses or evailuqtiqns justifying the change(s) and (2)
A determinatiain that the change will maintain the 'level of radioactive ef'fluent control required by 10 CFR 20.106,'40'FR,'art 190s 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 ianna not adveI sely impact the accuracy or reliability of eff'Iuent
- dose, or setpoint calculations.
b.
Shall becohie effective after reyiey hand,acceptance by the. PRtl aind the approval iof the -Plant ltianagqr.i
,c.
'Shall be submitted to the iCommipsiioniini the form of a.complete, legib'le copy of the entire ODCH, as, peart, of or concurrent with t.he Annual Radioactive Effluent Rellease iieport, for tha period of the report in which an'y change to tlhe ODCH was made.
Each change shall
- be ident,ified b>i markings 'in the margin of the affected pages,,
,clearly indicating the area of "the page that wEIs changed, and shall,'ndicate the date (e.,g., month/year) the change was implemenite>>i.,'Licensees may chose to submit the informatiorl called for in this specif'ication as part of the annual,FStitR update.
PALO VERDE - UNI1 1
6-I?4 AMENDMENT NO. M,Aps;~ 80
qgR Rfop c<
~o n
I o
I Y
Cy o~
0 +)i*4+
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 205R~I RIZONA PUBLIC RV C
COMPANY A.
DOCKET NO STN 50-529 ALO VERDE NUCLEAR-G NERAT NG STAT ON UN NO.
MENDMENT TO C
T P
RA G
S Amendment No.67 License No. NPF-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
'D.
E.
The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric
- Company, Southern California Edison
- Company, Public Service Company of New Mexico, Los Angeles 'department of Mater and Power, and Southern California Public Power Authority dated October 27,
- 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Part I; The facility will operate in conformity with the application, the provisions, of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) 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 Commission's regulations; 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 The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations
.and all applicable requirements have been satisfied.
2.
Accordingly, the license is.amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-51 is hereby amended to read as follows:
Ik 4
3.
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through. Amendment No.
67, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
APS.shall operate the facility in accordance with the Technical Specifications and the Environmental Protection
- Plan, except where otherwise stated in specific license conditions.
This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.
FOR 'THE NUCLEAR REGULATORY COHHISSION
Attachment:
Changes to the Technical Specifications Theodore R. quay, Director Project Directorate IV-2'ivision of Reactor 'Projects III/IV Office of Nuclear Reactor Regulation
.Date of. Issuance:
September 12, 1994
I~
II I
II
TTACHMENT TO LICENSE AM NDMENT AMENDMENT 'NO.
67 TO FACILITY OPERATING ICENSE NO. NPF-51 OCKET NO.
STN 50-5 9
'Replace 'the following,pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the.areas of change.
remove XVII
'1-4 6-20 6-24 XVII 1-4 6-20 6-24
ii
N EX DMINISTRATIVE CONTROLS g:CT'~ON
~AG 6.5.3 NUCLEAR SAFETY GROUP (NSG)
FUNCTION ~'
~ ~ ~ ~ ~ o
~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ o 6-10 COMPOS ITION o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ o ~ ~
6-10 CONSULTANTS.............-...................................
6-10 REVIEW o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ o ~
6-10 AUDITS ~ ~
~ ~ ~ ~ ~
~
~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
6-11 AUTHORITY~ ~ ~ ~
~
~ ~
~
~ ~ ~ ~ ~ ~
~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ow o ~
~ ~ ~
~ ~
~ ~ ~ ~ ~ ~ ~
6-12 RECORDS....................................................
6-12 6.6 REPORTABLE V NT ACTION............................:.........
6-12 6.7 SAFETY LIMITVIOLATION.......................................
6-13 6.8 PROC URES AND PROGRAMS......................................
6-13 6.9 R
PORT NG R
UIREMENTS 6.9.1 ROUTINE REPORTS...................................
STARTUP REPORT....................................
6-18 6-18 ANNUAL REPORTS
~ ~ o
~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~
~
~ ~ ~
~ ~
~ ~ ~ ~ ~
~ ~ ~
~
MONTHLY OPERATING REPORT...................................
6-19 6-20 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.........
6-20 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT.................
CORE OPERATING LIMITS REPORT...............................
6.9.2 SPECIAL REPORTS............................................
6-20 6-20a 6-21 0
R COR NT 0
~ ~ ~ ~
~ ~ ~ ~ ~ ~
~ o ~ ~ ~
~ ~
~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~
~ ~ ~ ~ ~
~
~
~ ~ ~ ~ ~
6-21 6.
A ON P 0 T ON PROGRA................................
6-22 6.
2 IGH ADIAT ON AR A.........................................
6-23 6.
3 PROC S
CONTRO PROGRA (PCP)...............................
6"24 PALO VERDE - UNIT 2 XVII AMENDMENT NO.~ M,~ 67
ll ADMINISTRATIVE CONTROLS
~CTI ON INDEX',
JPA<X EEJJIEEE-Ut" MEEE..:........,........::..:.....
EJ I
<<! !~LIE
)L~NSO~I WAS~T; TeA~Mt:NT~YST.MS....,...... >.........E.......
6-2'4
.PALO VERDE
-, UNIT 2.
XVIII
DEFINITIONS CORE OPERATING LIMITS REPORT 1.9a The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current operating reload cycle.
These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Technical Specification 6.9.1.
Plant operation within these operating limits is addressed in individual specifications.
0000 Fll I I E I I-IE 1.10 DOSE E(UIVALENT I-131 shall be that concentration of I-131 (microcuries/
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.ofTID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."
E -
AVERAGE DISINTEGRATION ENERGY 1.11 E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in HeV) for isotopes, other than iodines, with half-lives greater than 15 minutes, making up at least 95K of the total noniodine activity in the coolant.
ENGINEERED SAFETY FEATURES
RESPONSE
TIME 1.12 The ENGINEERED SAFETY FEATURES, RESPONSE TIHE shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays where applicable.
m
"'.13 The FRE(UENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
GASEOUS RADWASTE SYSTEM 1.14 A GASEOUS RADMASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity pHot to release to the environment.
IDENTIFIED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be:
a.
Leakage into closed systems, other than reactor coolant pump controlled bleed-off flow, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or 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 c.
Reactor Coolant System leakage through a steam generator to the secondary system.
PALO VERDE - UNIT,2 1-3 AMENDMENT N0.55
EF IN IT IONS K.
1.16 K., -is the k efFective calcu1lated by consi,dering the actual CEA con-figuratson and assuming that the fully or partiailly inserted full-length CEA of the highest inserted worth is fully withdrawn.
M RS 0
H~U@
.1.17 MEMBER(S) OF THE PUBLIC shiall include ajll jpersons,who are not occupai-
,tionally associated with the plant,.
This, category does not include employees of the licensee, its contractors, or vendors.
Also excluded fr'om 'this category are.persons who enter the site to, serv]ce, equipment or to make deliveries.
This, category does inc'lude persons who use portions of the si$ e for recreational, occupational, or other purposes not associated with tihei plant.
0 C
IJQJO.UI&ll SLIGII21
.1.18 The OFFSITE,DOSE CALCULATION HANUAL (Ofj)CH) sha'll,contain the methodology and parameters used in 'the calculation of,offsite doses resulting from radioactive gaseous
.and liquid effluents, in thie ralculation of gaseous and liquid effluent monitoring Atjarm/Trip Setpoipts,
.and in the conduct of the Environmental Radiological 'Monitoring Program.,
Tt~e ODE'H +hall also, contain (1) the Radioactive Effluent Controls,and Radiological Environmental Monitoring Programs required by Section 6.8.4, and (2) descriptions ofithie information that should'e
.included in the Annual Radiological Environmenta)
Operating.and Annuial Radioactive Effluent Release Reports required by Specifications 6.'9.-1.7,,and 6.9.1.8.
OP ERABLE OP ERABILI'IY 1.'19 A system, subsystem'train,-
component, or device shall be OPERABLE or have OPERABILITY when it is capable nf perfo'rming its specified function(s),
.and when all nece sary attendant
'instrumentatiqn, controls, electrical
- power, cooling or seal water, lubrication or-ether au>(iliary equipment that are required for the system, subsystem, train~ component,,or device to perform its
'function(s) are 'also capable.of performin!g the'tr related support function(s).
- j. 'IIJOK 1.20 An OPERATIONAL MODE (i.e.
MODE) shajll jcoprespond to any one inclusive
.combination.of co're.reactivity.condition,, pt'twer level, and cold leg rgacgor, coolant temperature:specified in Table 1.2.
'PALO VERDE UNIT 2 1-'4 AHENDHENT NO. M; +8; 67
ADYiINISTRATIVE CONTROLS REPORTING RE UIREHENTS Continued ANNUAL REPORTS" 6.9.1.2 The Startup Report.shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions 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 described.
Any additional specific details required in license conditions based on other commitments shall be included in this report.
,6.9.1.3 Startup reports shall be submitted within (1) 90 days following comple-tion of the startup test program (2) 90 days following resumption or commence-ment of commercial power operation, or (3) 9 months following initial criti-cality, whichever is earliest.
If the Startup 'Report does not cover all three events (i.e., initial criticality, completion of startup test program,,and re-sumption or commencement of commercial operation) supplementary reports shall be submitted.at least every 3 months until all three events have been completed.
6.9. 1,4 Annual reports covering the activities of the unit as described below for the previous calendar year, shall be submitted within the first calendar quarter of each year.
The initial report shall be submitted within the first calendar quarter of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions,"" e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special. maintenance (describe maintenance),
waste processing, and refueling.
The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less: than 20K 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 should, be assigned to specific major work functions.
Annual reports shall also include the results of specific activity analysis in which the, primary coolant exceeded the limits of Specification 3.4.7.
The following information shall be included:
(1) 'Reactor power 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 fi~st sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one "A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station.
<<"This tabulation supplements the requirements of 520.407 of the 10 CFR Part 20.
PALO VERDE - UNIT 2 6-19 AMENDMENT NO. Zl, 48
IEE NNUAL REPORTS Conf;'inued~
I analysis after the radioiodine activity was redijiced to less than limit.
Each result should include date and time of sampl/ng, and the'adioiodine concen-
-trations; (3) Clean-up.ystem f'low 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 firs't sample in which the limit was exceeded; (4)
Cpraph of the I-131 concentrat'ion and one other radioiodine isotope concentration in m'icr'ocuries
'pei gram a's 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 t$ e
~
primary coolant exceeded the radioiodine ]imit.,
ONTHLY OP RAT NG ~RP~RJ 6.9.1.6 Routine reports of operating statistics and shutdown experience including documentation of'll challenges to the safety valves, shall, be, submitted on a monthly basis to the Director;, Pffice of Resource Hanagement U.S. Nuclear Regulatory Commission, Mashipgt,nn D.C, 20555, with a copy to the Regional Administrator of the Regional Office of the 'NRC, no later than the 15th of each month following the cale~ndpr youth covered by the repor).
'L'<<L E
Al.
E I 6.9. 1.7 The -Annual Radiological Environmental Operating Report covering~ tile, operation of the unit durincj the previous calendar year shall be submitted, be-fore.May 1 of each year.
Tfie report shall include summaries, interpretations, and.analysis of trends of'he results of the R'adiological Environmentpl
'Honitoring Program for the reporting period,.
,The material provided slhall tre consistent.with the objectives outlined in (1) the 'ODCH,and (2) Sections IV;B.2, IV.B.3, and IV'.C of Appendix I to 10'FR Part 50.
LlMLEILKJI!BENI".
6.9.1.8 The Annual Radioactive 'Effluent Release Report covering the,operatiqn of the unit during the previous calendar year,'shall be submitted before, Hay 1 of each year.
The report shall include a summary of the quantities pf,'adioactive liquid and gaseous effluents arid sol,id waste released from (he unit.
'The material provided shall. be (1) consistent with the objectives outlined in the ODCHEand PCP and (2) in coriformanci~ with 10 CFR 50.36a and Section IV;B.l of Appendix I to 10 CFR Part 50.
- A single submittal may be made for a jul,ti-unit,stytion,
- Asingle submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station;
.however, for units with separate radwaste
- systems, the
. ubmittal sha'll specify the release of radioactive materia'I from each unit.
PAI.O VERDE UNIT.2 6-20 AMEQDHfjNT( NP.~ 67
ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA 6.12.1 In lieu of,the "control device" or. "alarm signal" required by para-graph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Expo-sure Permit (REP)*.
Any individual or group of individuals permitted to enter
- such
- areas:shall be provided with or accompanied by one..or more of the following:
a.
'A.radiation monitoring device which continuously indicates the radia-
'tion.dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radia-tion.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 knowledgeable of them.
c.
.A radiation protection qualified individual (i.e., qualified in radia-tion protection, procedures) with a radiation dose rate monitoring
.device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation sur-ve'illance at the frequency.specified'y the facility Radiation Protec-tion Supervisor or his designated alternate in the REP.
,6.12.2
'In addition to the requirements of Specification 6.12.1, areas accessible to personnel'ith radiation levels such that.a ma'jor portion, of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose greater than 1000 mrem shall be provided with locked doors 'to prevent unauthorized entry,.and the keys shall be maintained under the administrative control:of".the Shift Super visor on duty and/or radiation protec-tion supervision.
Doors shall remain locked except during periods of access by personnel under an approved REP which shall-specify the dose rate levels in the immediate work area.and the maximum:al.lowable:stay time for individuals in that area.
For individual areas accessible to personnel with radiation levels such that a major portion of the body could"receive in '1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrems"", that, are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around'the individual areas, then that area, shall be roped.off, conspicuously posted and:a 'flashing light shall. be activated as a
warning device.
,In lieu of 'the stay.time specification of the REP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made.by personnel qualified in radiation protection procedures to provide positive exposure control over the activities;within the area.
- "Radiation 'Protection personnel or personnel'scorted by Radiation Protection personnel shall be exempt from.the REP issuance requirement during..the. perform-ance of their,assigned, radiation protection duties, provided they are otherwise following;plant radiation, protection procedures for entry into high radiation areas.
""Measurement made at,18 inches from source of radioactivity.
PALO VERDE - UNIT 2
.6;23 AMENDMENT NO. g 48
3 P
C SS CON R~OPROGF'AM~gP'L Changes to the PCP:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.q.
This documen!tation
,shall contain:
(1)
Sufficient information.to support; the, change together with the
~ppropriate analyses ar eva!luations, justifying the change(s) and (2)
- A, determination that the change will maintain the overall cop-f'ormance of the
. olidified !waste product, to existing
- requirements of l-ederal, State, or other.applicable regulations.
b.
Shall become effective after review apd.acceptance by the PRB and the approval of the. Plant Manager.
4 OFFSI DOS CA, CU A'T ON NANUA~O~C Changes to the ODCN:
.a.
Shall be-documented and records of reviews performed shall be retained as required
!by Specific:atiop 6.10.2.q.
This documentation shall contain:
(1)
Sufficient information to support 4he, change together w$ tP tPe appropriate anal,yses or evyluptions justifying the change(s),
and (2)
A determination that the change wi'll maintain the level of radioactive effluent control,required by 10 CFR 20.106, 40 CFR Part
]l90, 10 CFR 50.36a, and Appendix I to ICl CIFR Part,50,and not adversely im!pact.the accuracy or reliability of effluent,
- dose, or,--setpoint.calculations.
b.
Shall become effective after review.and acceptance by the PRB and
.the approval.of the Plant Manager..
C.
,Shall. be.submitted to tire Commission in the Form of a complete,,
legible copy of the entire ODCM as
-a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of, the, report in which any change to the ODCN was made.
Each change shall
.be. identified by markings in.the margi'n of the affected pages,
.clearly indicating the area of;the page ti~at was changed, and shall, indicate the date (e.,g., month/year) the,c'.hange was implemented.
Ll5 II JO II jNGZ'TOMRAlLOACtB II 0
N HOl'l I'T lIIEAT
~ST~MS*
6.15.1 Licensee-initiated major changes to.the radioactive waste systems (liquid, gaseous,
.and solid):
Shall be reported to the Commission in the Annual Radioactive,
'Effluent Release Report for the period in which the evaluation, w~s review by the PRB.
The discussion of each change, shall contain:
- Licensees may chose to submit the information called for in this specification as part of the annual FSAR update.
PALO VERDE - UNIT 2 6>>24 AMENDMENT NQ. 4; M; <Hh 6i'
~
. pe RE00 0
Cy Cl Ih
. '~
~
0
~O
">>*++
t UNITED STATES NUCLEAR REGULATORY COMMlSSlON WASHINGTON, D.C. 2055&0001 ONA PU IC S RVIC COHPANY T AL.
OCK T NO.
STN 50-530 LO ERD NUCLEAR G NERATING STATION UNIT NO.
3 H
N H NT TO FACI TY OPERAT NG ICENSE Amendment No.
52 License No. NPF-74 2.
The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric
- Company, Southern California Edison
- Company, Public Service Company of New Hexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated October 27,
- 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will, operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) 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 Commission's regulations; D.
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 Commission's regulations and all applicable requirements have been satisfied.
Accordingly, the license is amended by changes to the Technical Spqcifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-74 is hereby amended to read as follows:
4~
l
(2) Technical S ec'cations and nvironmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 52, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
APS 'shall operate the facility in accordance with the Technical Specifications and the-Environmental Protection
- Plan, except where otherwise stated in specific license conditions.
.3.
This license amendment is effective as of the date of issuance and must
,be fully implemented no later than 45 days from the date of issuance.
FOR THE.NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Theodore R. quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Date of.Issuance:
September 12, 1994
0
TTACHMENT TO LICENSE AMENDMENT MENDMENT NO.
TO FACI ITY OPERATING LICENSE NO.
NPF-74 OCKET NO.
STN 50-530 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the.areas of change.
Remove insert XV,II 1-4 6-20 6-24 XVII 1-4 6-20 6-24
0 J
ND X
ADHINISTRATIVE CONTROLS
~SC'i/ON
~AG 6.5.3 NUCLEAR SAFETY GROUP (NSG)
UNCTION...................................................
F COHPOSITION o ~
~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~, ~ ~ ~ ~ ~ ~ o ~ ~ ~ o ~ ~
~
CONSULTANTS ~ ~ ~ ~ ~
~
~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
EVIEW o ~ ~ ~ ~
~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
R UD ITS ~ ~ ~ ~ ~
~ ~ ~
~ ~ ~ ~
~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
A UTHORITY..................................................
A R
I'I ECORDS..........................................:.........
6-10 6-10 6-10 6-10 6-11 6-12 6-12
.6 R
PORTABL V NT ACT ON......................................
6-12 6.7 SAF TY M T V 0 AT ON.......................................
6-13 6.8 PROC DUR S
AND PROGRAMS......................................
6-13 6.9 R
PORT NG RE UIREMENTS 6.9.1 ROUTINE REPORTS.,::.........................................
6-18 STARTUP REPORT.....................,.........................
6-18 ANNUAL REPORTS.............................................
6-19 MONTHLY OPERATING REPORT...................................
6-20 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT........
-CORE OPERATING LIHITS REPORT.....................'.
6-20 6-20 6-20a 6.9.2 SPECIAL REPORTS............................................
6-21 6.
0 RECORD R T NT ON............................................
6-21 RAD A ON PROT CT ON PROG 6-22 6.1 H
GH RADIATION AREA.........................................
6-23
6-24 PALO VERDE - UNIT 3 XVII AMENDMENT NO.~,~ 52
ADMINISTRAT IVE CONTROLS INDEX SECTION PAGE 6.14 OFFSITE DOSE CALCULATION NANUAL.....,'..,'...',,.......;..........
6-24 6.15 MAJOR CHANGES 'TO RADIOACTIVE LI UID,'GA'SEOUS'ITEMTIIREKCKETE PALO VERDE - UNIT 3 XVlt1I
(
DE FI NIT I GNS CORE OPERATING LIMITS REPORT 1.9a The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current operating reload cycle.
These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Technical Specification 6.9.1.
Plant operation within these operating limits is addressed in individual specifications.
DOSE E UIVALENT I-131 1.1O DOSE EQUIVALENT I-131 shall be that concentration. of I-131 (microcuries/
gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133,,I-)34.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 and Test Reactor Sites."
E - AVERAGE DISINTEGRATION ENERGY
- 1. 11 Y shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half-lives,greater than 15 minutes, making up at least 95K of the total noniodine activity in the coolant.
ENGINEERED SAFETY FEATURES
RESPONSE
TIME
- l. 12 The ENGINEERED SAFETY 'FEATURES'ESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays where applicable.
.mL "
1.13 The FREQUENCY NOTATION specified for the. performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
GASEOUS RADWASTE SYSTEM
- 1. 14 A GASEOUS RADWASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for.delay or holdup for the purpose of reducing the total radioactivity,prior to release 'to the environment.
IDENTIFIED LEAKAGE 1.15,IDENTIFIED LEAKAGE shall be:
a.
Leakage into closed systems, other than reactor coolant pump controlled bleed-off flow, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or 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 c.
Reactor Coolant System leakage through a steam generator to the secondary system.
PALO VERDE - UNIT 3 1-3 AMENDMENT NO. 42
DEFINITIONS K
- 1. 16 K., is the k effective calcu'tated by considering the actual CEA con~
figurat'ion and assuming that 'the fully or partially inserted full-length CEA of the highest inserted worth is fully witlhdrawn.
M R
S OF TH ~PI~LC 1.17 MEMBER(S)
OF THE PUBI.IC shall include all persons who are not occupa-tionally associated with the plant.
'This, category does not include emplpyqes, 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.
This category does include persons who use portions of the site for recreational, occupational, or other purposes,not associated with the plant.
OFFSITE 00SE CAt.CUILAT~ON MANUAL~OOCHQ 1.18 The OFFSITE
'DOSE CALCULATION MANUAL,(ODCM) shall contain the methodolOgy and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents,,in, the calculation of gaseous and liquid effluent monitoring A1lam/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program.,
Tge ODCH shall also contaiin (1) the Radioactive Effluent Controls and Radiological Environmental Honitoring Programs required by Section 6;8.,4,,ang (2) descriptions of the information that should be included in the Annual Radiological Environmenta'I Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.'9.1.,7,and 6.9.1.8.
OPERABLE OPERA~8 LITY
- 1. 19 A system, subsystem,,
train, component, or device shall be OPERABLE or have OPERABILITY when it iis capab'ie of performing its specified functiion(s)~,
and when all necessary. attendant instrumentation, controls, electrical power,,
cooling or seal water, 'lubrication or other auxiliary equipment that are required for the sys'em, subsystem, train, component, or device to perform,its function(s) are also:capable of'ierforming their related support function(s).,
~AT IIODj&EI; 1.20 An OPERATIONAL NODE (i.e.,
MODE) sh~ll,'correspond to any one inclusive combination of core -react'ivity condition, power level, and cold leg reactor coolant temperature speci fied lin 'Table '1.'2.
PALO VERDE - UNIT 3 1-4 AMENDMENT INO. %;H+
52
ADMINISTRATIVE CONTROLS REPORTING RE UIREHENTS Continued 6.9. 1.2 The Startup Report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions 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 described.
Any additional specific details required in license conditions based on other commitments shall be included in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the star tup 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 Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all.three events have been completed.
ANNUAL REPORTS"
- 6. 9.'1.4 Annual reports covering the activities of the unit as. described below for the previous calendar year shall be submitted within the first calendar quarter of each year.
The initial report shal-1 be submitted within the first calendar quarter of the year following initial criticality.
6.9. 1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure.according to work and job functions,"* e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance; special maintenance (describe maintenance),
waste processing,
=and refueling.
The dose, assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than, 20K,of the individual total dose need not be accounted for.
In the aggregate, at least 80K of the total whole body dose received from external sources should be assigned to specific major work functions.
Annual reports shall. also include the results of specific activity analysis in which the primary coolant exceeded'the limits of Specification 3.4.7.
The following information shall be included:
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior the the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one "A single submittal may be made for a multiple,unit station.
The submittal
,should combine those sections that are common to all units at the station.
""This tabulation supplements the requirements of 520.407 of the 10 CFR Part K.
PALO VERDE - UNIT 3 6-19 NENDHENT N. 5, 34
0 ADMINISTRATIVE CONTROLS analysis after t'e radioiodine act'ivity was reduced to less than limit.
Each result should include date and t,ime of sampling and the radioiodine concentra-tions; (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 1-131 concentvlation',
and one other radioiodine 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, primary coolant exceeded the radioiodine l,imit.,
~E IM 6.9.1.6 Routine. reports of operating statistics and shutdown experience, including documentation of all challenges to the safety valves, shall be submitted on a monthly basis to the Director Office of'esource Hanagi.ment, U.S. Nuclear Regulatory Commission,
'blashington, D.,C. 20555, with a copy to the Regional Administrator of the Regional Of'fiice'of the
- NRC, no laterlthlani the 15th of each month following the calendar month covered by the report.
L I
I::LlIR Mi.."L~E 6.9. 1.7 The Annua'1 Radiologica'1 Environmental Operating Report covering, the operation of the unit, during the previous ca'lendar year shall be submitted
'efore Hay 1 of each year.
II'he report shall, include summaries interpretations and analysis:of trends of the results of the Aadiologlic41
)
Environmental Hcinitoring Program for the repprtjing period.
The material provided shall be consi,stent with the objectives outlined, in (1) the ODCH and
{2) Sections.IVB.2, IV..B.3, and IV.C of Appengix I,to 10 CFR Part 50.
6.9. 1.8 The Annual Radioactive Effluent Release Report, covering the operation of the unit during,the previous calendar year sha'll be submitted before Hay 1
of each year.
.'The report, shall include a summary of the quantitie's of radioactive liquid and gaseous effluents and solid waste released from the unit.
The material provided shall be (1) consistent with the objectives outlined in the ODCH and -PCP and (2) in.conformance with 10 CFR 50.36a'nd
'Section,IV.B.1 of Appendix I to 10 CFR Part 50.
- A single submittal may be made for a multi-unit station.
- ~A single submittal may be made for. a multiple unit station.
The submittal should combine those sections that, are common to all units at the station; however, for un'its with separate radwaste,systems, the,sulbmittal shall specify the release of rad'ioactive materiel from each unit.
PALO VERDE - UhtIT 3 6
2fP AMENDMENT NO. +4, 52
AOMINISTRATIVE CONTROLS
- 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 CFR Part 20, each high radiation area in which the intensity of radiation is greater than,100 mrem/hr but less than.1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Expo-sure Permit (REP)".
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates 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 knowledgeable of them.
c.
A radiation protection qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance, at the frequency specified by the facility Radiation Protection Supervisor or his designated alternate in the REP.
- 6. 12.2
.In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major.portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose greater.than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and.the keys shall be main-tained under.the administrative control of the Shift Supervisor on duty and/or radiation protection supervision.
Doors shall remain locked except during periods of access by personnel under.an approved REP which shall speiify the dose rate levels in the immediate work area and.the maximum allowable stay time for individuals in that area.
For individual areas accessible to personnel with radiation levels such that a major, portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrems"*, that are located within large areas, such as PWR containment,
.where no enclosure exists for purposes of locking, and no enclosure can, be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as:a warning device.
In lieu,of the stay time specification of the REP, direct or remote {such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.
"Radiation Protection personnel or personnel escorted by Radiation Protection personnel shall be exempt from the REP issuance. requirement during the perform-ance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.
""Measurement made at 28 inches from source of radioactivity.
PALO VERDE -.VNIT 3 6-23 AMENDMENT NO. 34
Changes to the PCP:
a.
Shall be documented and records of peyiews performed sha'll be retained as required by Specificatipn 6.10.2.q.
This documentatIion shall contain:
(1)
Sufficient information to support the change together with the appropriate analyses or eya'IuaItiqns justifying the change(s) and (2)
A determination that the change wil'I ttIair>tain the overall conformance of the solidified waste, product, to existing require; ments of Federal,
- State, ormother applicable regulations.
b.
Shall become effective after.review and acceptance by the PRB and the approval of the 'Plant Nanager.
LJl II I'~DIK Changes to the ODCN:
a.
Shall be documented and records of,reviews performed shall be retained as required by Specification
- 6. 10.2.q.
This documentation shall contain:
(1)
Sufficient information to siupporf the, change together with, the appropriate analyses or ev@luationq justifying the change(s) and (2)
A determi,nation 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 I to 10 CFR IPart 50 'and not adversely impact the accuracy qr reliability of effluent,
- dose, or.'setpoint calculations.
b.
Shall become effectivIe after review and acceptance by the PRB and, the approval of the Plant Nanager.
- C.
Shall be submitted to 'the Commission,in,the form of a compleIte,i
'legiblle copy -of the entire ODCN,as, part, of, or concurrent with the Annua'll Radioactive'Effluent Releasie RepI)rt ftIr the, period of the report in which any change to the GDCN was made.
Each change shalI 1
i be identified by markings in the mgrgin of the affected pages,,
clearly indicating the spirea of -the page that was changed, and sha'll indicate the date (e.g., month/year) 'the change'as
.implemented.
6.15.)
Licensee-initiatecl major changes to the radioactive waste system (liquid, gaseous, and solid):
Shall be. reported
'to the.Commis, sion in the Annual Radioactive >>
I Effluent Release Report for the period in which the evaluation was reviewed by the PRB.
The discussion of each change shall contain:
'*Licensees may chose to submit the information called for in this specification as part of the annua'1 FSAR update.
PALO VERDE - UNIT 3 6-24 ANENDMENT NO..84,, Q* 52