ML20237F159
| ML20237F159 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/19/1998 |
| From: | Weiss S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20237F129 | List: |
| References | |
| FOIA-98-175 NUDOCS 9809020099 | |
| Download: ML20237F159 (17) | |
Text
- _ - _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ .
+ -__,--_
}' m arg j+(o .\ ,e llNITED STATES -
- NUCLE AR REGUL ATORY COMMISSION
'e. J 5 'yW ,I wAswmoton. o. c. rosss s, w /
YANKEE ATOMIC ELECTRIC COMPANY
~
,y ~,y DOCKET NO. 50 029(s+ r. ~ - y .
.,q YANKEE NUCLEAR POWER STATION'(Yankee-Rowe)
AMENDMENT TO POSSESSION ONLY LICENSE Amendment No. 147 License No. DPR-3
- 1. The U.S. Nuclear Regulatory Comission (the Commission or the NRC) has found that:
l A. The application for amendment filed by Yankcc Atomic Electric Company (the licensee) dated September 16, 1992 complies with the f standards and requirements of the Atomic Energy Act of 1954, as i
amended (the Act), and the Comission's rules and regulations set forth in 10 CfR Chapter I; B. 1he f acility will be maintained in conformity with the t.pplication, the provisions of the Act, and the rules and regulations of the Commission; C. Thereisreasonableassurance:li(i[that'theactivities' 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 set forth in 10 CFR Chapter I; 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 Cf.1.a :t 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, 4 and par. graph 2.C.(5) is deleted and paragraph 2.C.(2) of Possession Only titense No. OPR-3 is hereby amended to read as follows:
l 9809020099 990827 PDR FOIA BLOCK 99-175 PDR gg U9 02 0097 w
f[h.Ih, $b,khSDM * * % f..
.i.
3 Ms. Jane H. Grant Yankee Rowe Docket No. 50-29 CC:
Dr. Andrew C. Kadak, President Mr. David Rodham, Director and Chief Executive Office ATTN: Mr. James B. Huckerheide Yankee Atomic Electric Company Massachusetts Civil Defense Agency
- 580 Main Street 400 Worcester Road i Bolton, Massachusetts 01740-1398 P. O. Box 1496 Framingham, Massachusetts 01701-0317
! Thomas Dicnan, Esq.
Ropes and Gray Chairman, Franklin County One International Place Commission l Boston, Massachusetts 02110.2624 425,Hain4 Street
" Greenfield',' Massachusetts 03101 Mr. N. N. St. Laurent Plant Superintendent Executive Director Yankee Atomic Electric Company New England Conference of Public Star Route Utility Commissioners
! Rowe, Massachusetts 01367 45 Memorial Circle Augusta, Maine 04330 Rosident Inspector Yankee Nuclear Power Station Citizens Awareness Network U.S. Nuclear Regulatory Conmission P. O. Box 83 P 0. Box 28 Shelburne Falls, Massachusetts 01370 Monroe Bridge, Massachusetts 01350 l Regional Administrator. Region !
U.S. Nuclear Regulatory Commission 475 Allendale Road l King of Prussia, Pennsylvania 19406 Robert M. Hallisey, Director Rediation Control Program Massachusetts Department of Public Health 305 South Street Boston, Massachusetts 02130 Commissioner Richard P. Cedano vermont Department of Public Service 120 State Street, 3rd Floor Montpelier, Vermont 05602 Mr Jay K. Thayer Vice President and Manager of Operations Y dlikUe Atomit [lectric Company 580 Main Street Bolton. Massachusetts 01740-1398 l
l C -- __
O ShQlOACTIVE EFFLUENTS BASES 1]4,11,2,5 (DELETED)
U,idL_L 6 CAS S TOP.AC E TANK Restricting t he quantity of radioactivity contained in the waste gas surge drum (TK-36) and associated waste cover gas volume servicing the primary drain tank (TK-30), waste holdup tank (TK-31) and the activity dilution decay tank (TK-32) provides assurance that in the event of an uncontrolled release
]l of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not onceed 0.5 ram. This is consistant with Standard keview Plan 15.7.1, " Waste Cas system Failure *.
The curie limit for noble gases (considered Xe-133) given in Specification 3.11.2.6 is based on the calculated radionuclides inventory of the waste gas surge ' rum and associated cover gas system in use at the plant (equivalent to 30,000 cubic feet at ST?). The radionuclides inventory is based on the conservative assumptions that the plant has been operating at 618 MWt with one pe r c e n t failed fuel and that a cold shutdown has occurred near the l end of a n e qu i l i b r i um co r e cycle. It is assumed that 100% of the noble gassa are removed from the reactor coolant and transported to the waste gas surge drom/ cover gas system.
The t o t a l bod y g arna dose (0.5 ram) is calculated based on the criteria g i v e r. in NUREG 01JJ, Section 5.6.1 using an exclusion boundary dispersion ec=ff.cient (m/Q) value of 7.62 x 10-4 see m-3.
l j jf,[d l , 3 SQMp PAD 10 ACTIVE WASTE 1
l This s pe c i f i c a t i o r. implements the re qu ireme nt of 10 CTR Pa rt 50.36a and l Cer.eral Design criterion 60 of Appendix A to 10 CFR Part 50. The process parneeters included in establishing the PROCESS CONTROL PROGRAM (PCP) may include, but are not limited to waste t ype , waste pH, waste / liquid eclidification agent / catalyst ratios, waste oil content, waste principal of e c r. s t i t u e r.t s , m;zang and curing times. This Specification and the PCP address the handling of wet waste ( 11 gu l d e v a po r a t o r bot t om s and spent resins) only.
i ifj,11,4 TOIAL DOSE This erecification is provided to meet the dose 1Lmitations of 40 CTR Part 190 o at have been i nc o r po r a t ed into 10 CFR Part 20 by 46 FR 18525. The s pec i f i c a t ion r equ i re s the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive affluents exceed twice the design objective doses of Appendix I. For sites containing up to 4 yANr.EE-POVE B 3/4 11-5 Amendment No. 44, 147
-.- - . . l
., ,; - gw - .
MAIN COOLANT SYSTEM BASES The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity > 1.0 UCl/ gram DOSE EQUIVALENT l-131. but within the allowable limit shown on Figure 3.4-1, accommodates possible lodine spiking phenomenon which may occur following changes in THERMAL POWER. Operation with specific activity levels exceeding 1.0 uCi/ gram' DOSE' EQUIVALENT I-131 ~but within the limits shown'on Figure 3.4-l'must be restricted to no more than 10 V
percent allowed of bythe unit's figure yearly 3.4-1 operating:
increase the.2thour-timensincesthe-activityilevels-boundary by a factor of up to 20 following athyroid.steam dose generator at'the site
! postulated tutic rupture.
Reducing i a to < 514*F prevents the release of activity should a steam generator ygbe rupture since the saturation pressure of the primary coolant is below the lif t pressure of the atinospheric steam relief valves. The surveillance requirements provide adequate assurance that excessive specific' activity levels in the primary coolant will be de-tected in suf ficient time to take corrective action. Infonnation ob-L tained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of' isotopic analyses following power changes may be permissible if justified by the data obtainec.
I l
3/4.4.8 PRESSURE / TEMPERATURE LIMITS A.11 components in the Main Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes. These cyclic loads are introduced by normal load, transients, reactor trips, and startup and shutdown operations.. During startup and shutdown. the rates of temperature and pressure Changes are limited so that the' maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.
YANXEE-R0WE B 3/4 4-6 I
r
a 4 %<
MAIN COOLANT SYSTEM ..?'1 '
,b -
l R&sts 144.4.6 (DELETED) s
)]L_4 . 7 $PECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure l that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appropriately small f raction of Part 100 llaits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM. The values for the limits on specific-activity represent interLa 1Laits based upon a parametric evaluation by the commission of typical site locations. These values are conservative in that s pec i fic s ite pa r ame t e r s o f the Y ANKZr-ROVE s it e , such as sete boundary location and meteorological conditions, were not considered in the evaluation. The Commission is finalising site specifio criteria which will be used as the basis f or the reevaluation of the specific activity limits of this site. This reevaluation may result in higher limits. ;
1
\
l l
l l
l Y AN r.E E - POVI B 3/4 4-$ Amendment No. 147 a
o l
h l
I d
i INTENTILMALLY BLAW.
YANFlE-ROVE 3/4 11-13 Amendtnant No. 147 h _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ _ _
l.
e,, ... , c. . .
. y: . 5 ., ;y.':l. .c,
-(~ 2
, .~ .j I
1 l
INTENTIONALLY'-
BLANK l'
l Y ANKE E-ROWE 3/4 4 14 Aine ndme n t No. 147
INTENTIONALLY BLARK i
Y MiKI E - ROWE 3/4 4-13 Ame nd:ne nt No. 147
x : , ,c ,,
- , ,7 4 ,
gy, INTENTIONAL 1,Y BLANK s
l l
a
- E-ROWT 3/4 4-22 Arne ndtr e nt No. 147 L _
MA1H C001. ANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued) 1 .. - w. ..o;
- d. With more than two leaking {ncore detection system thimbles which are valved off but not plugged when in H30E 1, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEltt ANCE REQUIREMENTS 4.4.5.2 Main Coolant System leakages shall be demonstrated to be within each of the above limits by;
- a. Monitoring the containment atmosphere particulate radioactiv-ity eeniter at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except when & Main Coolant System water inventory has not been performed within the predeus 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then monitor the containment atmosphere i particulate radioactivity monitor at least once per hour,
- b. Monitoring the Containment drain tank monitoring system a t least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- c. Performance of a Main Coolant System water in'ventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during steady state operation, and
- d. Monitoring the reactor head flange leakoff system at least once per 24 hCurs, l
3/4 4-1I tcendment No. H , 58 YAuEE aC%E h?9. 3
F
.131.1 ADv!N!STRAilvt CONTR0t5 SiCT10N .PfAQ Consultants . . . . ................ 6 10 Hecting Frequency . . ............s. ,. . . . . . . . . 6 10 Ouorum . .. . . . . . ................. 6 10 Review . . ....................... 6 11 Audits . ................ 6 11 AuthCrity . . . . . ............... 6*12 ReCO'C5 . . . ................ 6*12 f (-
3 IN iDf4 DEN' A 'J 01 T AND REVIEW . . . . . . . . . . . . . 6 12
,f.6 ti;0:~A?t! CviNi ACTION . . . . . . . . . . . . . . 6 13 6.7 Ster', t!w!' v!0tATION . . ... . . . . . . . . . . . 6 13
,e e c: . cr( .. . . 6-13 I
lc o st' :- sc. ci :rers-c
'l
',; O ( . 9 .' C".'!NT REPO:TS ................ 6 14 i
R;U'!NE RCc0RTS (OfLETCD) . . . . . . . . . . . . 6 15a l6.9.3
(.9.4 ((t[Ti . . . . . ..... .......... 6 16 6.9.5 UN10UC REPORTING R(0V!R[H[ HTS . . . . . . . . . . . . 6 18
'(.9.6 SSECIAL REPORTS . . . . . . ' . .. .'. . . . .. . . . . 6 22 I f.;: FCCS:D *[TfNTICN ............. . . . . 6 22
- 11 FA:lA710% PSOTECil0N PROGRAM . . . . . . . . . . . . . . . 6 23
( ? H: GH RA0!ATION ASEA . ................... 6 24 f !? (Nvir0Nv?N' OVAL!r! CATION . ........... . . . . 6 24 5 14 P RO:( 5 5 C ON Y PC's #80' CAM . . ................ 6 25 f 15 CFr$:TE D05f CALCULATIONAL MANUAL . . . . . . . . . . 6 25 l ,i 16 ** J:r Cu1NG(5 TO R A:10 ACT ! VE (10910. G AS EOUS A ND 50',10
(^ .;; wtitt TREAT *[N' 5'5T(v5 . . . . . . . . . . . . . 6 26 l
l VAN (( DDst IV Amendment NO. 467-60, 104. 147
~
..t
- mu>M
- py . ..: ,
l INDEX BASES l SECTION PAGE 3/4.4 MAIN COOLANT SYSTEM 1/4.4.1 MAIN COOLANT LOOPS . . . . . . . . . . . . . B 3/4 4 1 l
3/4.4.2 and 3/4.4.3 SAFETY VALVES . . . . . . . . . . . . . . B 3/4 4 1 3/4.4.4 PRE 55UR12ER , . . . . . . . . . . . . . . . . , . B 3/4 42 3/4.4.5 MAIN COOLANT SYSTEM LEAXAGE . . . . . . . . . . . B 3/4 43 3/4.4.6 CHEMISTRY (DELETED) . . . . . . . . . . . . . . B 3/4 45 i 3/4.4.7 SPECIFIC ACTIVITY . . . . . . . . . . . . . . . . B 3/4 45 3/4.4.6 PRESSURE / TEMPERATURE LlHITS . . . . . . . . . . B 3/4 46 3/4.4.9 STRUCTURAL INTEGR!TY , . . . . . . . . . . . . . B 3/4 4 11 l 3/4.4.10 STEAM GENERATOR $ . . . . . . . . . . . . . . . . B 3/4 4 12 t
l 3/4.5 EPEDGENCY CORE COOLING SYSTEMS (ECCS) l 3/4.5.1 ACCUMULATOR . . . . . . . . . . . . . . . . B 3/4 51 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS . . . . . . . . . . . B 3/4 51 3,4.5.3 SATETr th)ECTION TANK . . . . . . . . . . . . . B 3/4'5 2 3'4.5.5 ECCS SU55v5 TEM LEALAGE . . . . . E 3/4 53 i
l l
i I
l yANLEE R:ai X Ame ndme n t N o . 54, j 4 7
i I NDEX.
BASES ..
% af 4 SECTION PAGE 3/4.0 -APPLICABILITY............................................. B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS l 3/4.1.1 B O RA T 10 N C O N T R 0L . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 1-1 1 1
- - 3/4,1.2 B O RA T 10N S Y S T EM S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 1-3 l
3/4.1.3 M OV A B L E C ON TR OL R 00 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 1-4 i
l 3/4.2 POWER DISTRIBUTION LIMITS ;
f:
3/4.2.1 P LA K L IN EAR HEAT GENERAT ION RATE. . . . . . . . . . . . . . . . . . . . . . . . B 3/4 2-1 3/4 2.2 and 3/4.2.3 NUCL' EAR NEAT FLUX AND~ NUCLEAR ENTHALPY l RISE HOT CHANNEL FACT 0RS............................... B 3/4 2-2 3/4.2.4 DNB PARAMETERS.......................................... B 3/4 2-3 3/4.3 INSTRUMENTATION-3/4.3.1 R EAC TOR PROT ECTIVE SYSTEM INSTRUME HTAT10N. . . . . . . . . . . . . . . B 3/4 3-1 3/4.3.2 ENGINE ERED SAFEGUARDS SYSTEM INSTRUMENTATION. . . . . . . . . . . . B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION.............................. B 3/4 3-1 i
j i
YANKIE-ROWE IX !
.I EE LIMITING CONDITIONS r0R OPER ATION AND SURVEllL ANCE RE0VIREMENTS SECTION PAGE 3.4.9.12 SPENT FUEL Pli BUILDING ISOLATION . . . . . . . . 3/4 9 13 3.4 10 ttfCIAL TCST ErCEPTIONS 3/4.10.1 SHUIDOWN FARGIN., . . .... . . . .... . . . . . . 3/4.10 1 l
l 3/4.10.2 . CONTROL R00 OPERABILITY AND INSERTION LlHlTS . . 3/4 10 2
^
3/A.10.3 PRESSURE / TEMPERATURE" LIMITATION REACTOR l CRITICAtlTY , . . . '. ... ... ...,. . . ... . . .
. 3/4 10 3 L 3/4.10.4' PHYSICS TESTS . . . . . . . . . . . . . . . . 3/4 10 4 l
3/4,1C.5 EEDUCED LEVEL OPERATION WITHOUT COLD LEG OPENING 3/4 10 5
~
3/4.1056 REDUCE 0 LEVEL OPERATION FOR COLD LEG OPENING .. 3/4 10 7 3/4.10.1 RCOuCEO LEVEL OPERATION FOR COLD LCG OPEN]h6 Wi1H LOW 0(CAY HEAT . , . . . . . .. . . , , . , . . . . 3/4 10+9
'4.11 La?;0ACTIvf ErrttitsT5 l
3'4.11.1 (10U10 EfftVENTS C..':c't'ati;n . . . . . . . . . . . . . . .~3/4 11-1 i- 0:se . . . . . . . . . . . . . . . . 3/4 11 4 itcuic Rac.aste Treatment.. ,... . . . . . . . 3/4 11 5
. L i a #i d H 1 dup Tanks . . . . . . . , . . . . . . 3/4 11-6 3/4.11;2- GA5[C.'5 ffFtVENTS s Dese Rate . . . . . . . . . . . . . . . . . . . 3/4 11 7 Dose: Noble Geses . .. . . . . . . . . . . . . . 3/4 11 10 Dose: Iodine 131, Tritium, and Radionuclides in Particulate form . . . .. . . . . . . . . 3/4 11 11
. 3/4 11 12 l
Gaseous Radwaste Treatment. . .. . . . . . .
Eaplosive Gas Hixture (Deleted) . . . . . . . . . 3/4 11 13 )
Gas Storage Tank . . ... . . . . . . . . . 3/4 11 14 I !
34.;1.3 50;10 RA010ACilVE WASTE , . . . . . . . . 3 .' 4 11 15 !
i i
l l
TAN.If+EdWI Vill Amenament hc. 60--434- 147 l
.,..,,a-...- ..L... ~ . . . , - - . . . - - - I w_____-__________-____-_____-__- -___ --_-_ _~_-
', , , t lE.L.E LIMITING CONDITIONS FOR OPERAT!0N AND SURVE!LL ANCE REQUIREMENT $
SECTION PAGE MAIN COOL ANT SYSTEM (Cont {nutd) 3/4.4 6 CHEMISTRY (DELETED) . . . . . . . . . . . . . .
3/4 412l 3/4.4.7 SPECir!C ACTIVITY . . . . . . . . . . . . . . . . 3/4 4 16 3/4.4.8 PRESSURE / TEMPERATURE LIM 115 Main Cociant System . . . . . . . . . , , 3/4 4 19 Pressurizer . . . . . .. . . . . . . . . . . 3/4 4 25 3/4.4.9 SiouCTURAL INTEGRITY . . . . . . . . . . 3/4 4 26 2'4.4.10 5'EAM GENERATORS . . . . . . . . 3/4 4-32
: 8 furects:v cone C00tfNG SYSTEMS (ECCS) 3 / 4 . 5 .1 ACCUMULATOR . . . . . ....... . . . . . . 3/4 51 3/4.5.2 ELCS SUBSYSTEMS.. . . . . . . . . . . . . . . . . 3/4 53 3/4.5.3.1 ECCS SUBSYSTEMS . . . . . . . . . . . . . . . . . 3/4 59 3 /4. 5. 3. 2 ECCS SUBSYSTCHS . . . . . . . . . . . . . . . . . 3/4 5 11e 3/4.5.4 5Ar[TY INJECTION TANK .. . . . . . . . 3/4 5 12 3/4.5.5 ECC5 5UBSYSTEM LEAKAGE . . . . ... . . . 3/4 5 13
- s c:s 4'suts- 5<5:Eus 3/4.6.1 PRI"Acv CONTA]NMENT Containment Integrity .. . . . . . 3/4 61 Ccr.tainment Leaka9e . . . . . . . . 3/4 62 Ctr.tainment Air lock . , , , 3/4 6.a lrternal Pressure . . . , , , . . , 3/4 6.$
Air Tencerature . . . . . . . . . . . . . . 3/4 66 Containment Vessel Structural Integrity . . . . . 3/4 67 Continuous Leak Monitoring System . . . . . . . . 3/5 6 8 3/4.6.2 CONTAlHMENT 150LAT10H VALVES. .. . ........ 3/4 6 9 Amendment No. 46 '-54 :-th Y A S *:E E C 0 '= E V 90 -t39:147
AJ,l/_(hMNT A TO LICENSE AMENDMENT NO.147 epistSS10.N ONLY LICENSE NO. OPR-3 DOCKU !!Qt.3.0-912 Replate the f ollowing pages of the Appendix A Technical Specifications with the attached pages. The revised pages hre identified by Amendment number and contain vertical lines indicating the area of change, hpMu Insert V V vill Vill IX unchanged r X 1
XV XV 3/4 4-11 ..nchanged 3J4 4 12 3/4 4-12 34 4 13 3/4 4-13 34 4 14 3/4 4-14 3/4 11-13 3/4 11-13 R 3/4 4-5 8 3/4 4-5 j B 3/4 4-6 unchanged b 3/4 11-5 8 3/4 11-5 ihn urthangad pages are the reverse side of revised pages that were doubie-sided.
, i I I 1
l l
i I
L-______________ _ _
. . < , we.x4@ps,+9Ewa sc G3 h ,, > ,
- e i
(2) ltEh01CA.32ecifications I
t The Technical Specifications contained in Appendix A, as revised through Amendment No. 147, are hereby incorporated in the license. The licensee shall possess and maintain the facility in accordance wit h the Tec.hnical Sp2cifications, and Paragraph 2.C.(5) of Possession Only License No. OPR-3 is deleted.
3 19 s license amendment is effective as of its date of issuance.
l TOR Tile NUCLEAR REGULATORY COMMISSION utf S ff Seymour H. Weiss, Direc or Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation A t t a <. hme n t :
i'Hw, to ibn Technical ipe
- i f': d l i 'P.
! ,a t e is .u a' t e F; h r ...a r f , > , !~)J
(
i i
- _ _ _ . . _ _ - - _ _ _