ML19270H498
| ML19270H498 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/28/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19270H497 | List: |
| References | |
| NUDOCS 7910160340 | |
| Download: ML19270H498 (6) | |
Text
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-w UNITED STATES
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NUCLEAR REGULATORY COT,1f,11SSION e
- , NO.#.
E A ASHINGTCN. D. C. 205 55 s, ^*. 2,% f f 9
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'7 CCMMCNWEALTH EDISCN COMPANY DCCKET NO. 50-10 DRESDEN NUCLEAR ?CNER STATION UNIT ';C. 1 AMENCMENT 70 CACILITY CDERATI.';G LICENSE Amendment 'io. 31 License No. DPR-2 1.
The Nuclear Regulatory Commission (the Commission) has fcund that:
A.
The a;; plication for amendment by the Commenwealth Edison Company
(:he licensee) dated November 2,1977, as su::ple ented May 16, 1978, June 9, 1978, Octcber 19, 1978 and March 7,1979, conclies with the stancards and requirements of the Atomic Energy Act Of 1954, as amended (the Act), and the Comissicn's rules and regulations se: ferth in 10 CFR Chapter I; 5.
The facility will c;erate in conformity with the acclica:icn, the provisions of the Act, and :ne rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by :nis amendment can be conducted without endangering the health and safety of the ;ublic, and (ii) that such activities will be conducted in ccmpliance 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 C.:R Par 51 of the Cc mission's regulaticns and all applicable recuirements have been satisfied.
D 7,91,8_7 91016 0 3 + o
h 2-2.
Accordingly, the license is amended by changes to the Technical S:ecifications as indicated in the attachment to this licanse a endment and paragraph 2.C(2) of Facility C;erating License ';o.
- R-2 is hereby amended to read as foll0ws:
(2) Technical S:scifications The Technical Specifications contained in A;;endix A, as revised thecugh Amendment "o. 3I, are hereby incorporated in the license.
The licensee shall Operate the facility in accordance with the Technical Scecifica icns.
3.
This license amendment is effective as of the date of its issuance.
FOR TFE NUCLEAR RE3ULATORY CCMMISSION
'.4 W./ 7 7['he! %
/
Dennis L. Ziemann, Chief
' /
- g, Operating Reac Ors 3 ranch =2 s_,
L Division af C: era:ing Reactors
- ::ac nment:
Changes to the Technical 5:ecifications Ja:e cf Issuance: Sectenber 28, 1979 2379 i83
ATTACHMENT TO LICENSE AMENCMENT NO. 31 FACILITY OPERATING LICENSE NO. DPR-2 DOCKET NO. 50-10 Change the Accendix A Technical Specifications by removing the pages described belcw and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 70 70 75 75 76 76 77-85 (Table J.6.1) 237?
!84
- 5. s.
1.1711 1 ItlG CONDI I Iori 101 OPl:lt AT I oil 1.o SilitVlilI.I.AtlCli Ill.Qlllio Iti.fil'.
. - -... - -.. - ~ -. -.. - -.
1:
.salety Valves li. Salety Val ves 1.
Innisng scarto power ope:ating coniti-A minimum of 1/2 of all safety valves Q
5) tsons an.1 whenever the react or t oolant shall be henth checkeil or replaced with a Q
g picssure is gi eat er t han 90 ps ig anil hencia checked valve each reluct ing outage.
t empe s at ut e grea t e r t han 320*l:, all
'llie allowable set point error for each ten of the safety valves shall be valve is t i i..
The safety valve nominal operable settings shall be as fo ll ows :
M 2.
Il Specification 3.o.1:.1 is not met, 2 valves at 1210 psig an oidenly shutdown shall be initiated 2 valves at 1220 psig and t he react or coolant picssure and 2 valves at 1230 psig tempeiatore shall be leclow 90 psig 2 valves at 1210 psig c._
anil 320 *1 wiIhin 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />.
2 vaives at I250 psig b
WF Si ruc t ura l Integrity I
Structural integrity The s t ruc t ural integrity as the primary 1.
lleginning March 4,19//, atid updated syst em bound.iry shall be maintaineil at every 40 nionths thereaf ter, the the level m e.[ni real ley t he ASMii lloi t er and component inservice inspection Pressure Vessel Code, Sect ion XI, "Itut es prograni shall be performed in fo r Inscivice inspect ion of tinclear Power accordance with Section XI of the Plant Components", 1971 lidition (ASMii ASME Boiler and pressure Vessel coile, Section xt].
Component s of t he Code atid Addenda as reytiired by p r ima ry sys t em honnilai y whose inservice 10 CfR 50, Sectinn 50.55a(g),
examination reveals the absence ut llaw except where specific written i nit i ca l i ons or llaw indications not in relief has been given by the exiess ul Ihe allowable inilication stan-flRC pursuant to 10 t'l R 50, ila s il. of t h i s Code are acceptable fo r Section 50.55a(g)(6)(i).
coint s alueil se rvi t e.
I' l a n t operat iten wi th IJ components whith have inservice examina-(*
Icon llaw indicalion(s) in excess of t he N
altowable inifical ion s t unita rds of Ihe Code w
CD LT1 Amendment tio. ps, 31 70
1:a s e..
'Y cons i den ed adcapaa te to assuse accusate readings iodine and part iculat es a re 2.4 pCi/sec and (d
ut the monitors.
I f conduct i vi t y i:= wi t hin i t s the sphere ventilating air flow is 6000 cfm.
G 3
nosmal sange, chlorades and ot her impuri t ies FLuiy yea s of caperience is s cact or chemi s t ry t
will also be wi t hin t hei r normal ranges.
't h e has :Juswn 108 pCi/l t o be a normal level of dE'P2) scattor coolant samples will also be used t o ti act ivi t y in reactor wat er.
.the nameplate detcamine ihe i;alorides.
't h e re t o n e, the rating of Ihe cont a innuent ventalation tans is C)
samp I a ng ireignuncy is cons ide s ed adcagnat c 6575 e i.m.
113 ing ihese assumpt ions, t he 231 0) to detect long-t erm t hanges in the chloride allowable leakage rate is 0. 311 gpm wh s ch son inntent.
1:.ot opi c ana ly:.cs reipii red by corresponds to about 10-6 pCi/ml is: the U"J c0 Speciiicatson 1.6.C.l.h may be pert'oimed by sphe re vent i I at ing ai r.
't he r e fo re, Ihe a 1: "' '* 8 58du-action levels lis t ed in Sect ion 4.6.D. I.d and M
f reipai re st eps t o be instituted for locating h
D.
Coolant 1.caLagg - 1.calage from the primary p ri ma ry sys t em icals long befo re t he act ivi ty b
systA Iinto -the sphere will be discharged level reache:, a limiting license condition, with the sphere ventilating air up the Ilnit I limperience has shown the leaks can located stack.
'this means that t he prima ry :>y:> t em when aisborne beta radioact ivi t y concent rat ions leakage will have a direct cifect on the are in the range of 10-9 to 10-pc/mi,
- ,t ack gas at t ivi t y release rate.
providing general containment areas are at nommai background concentrations.
't h e step incicase and its magnitude spectiicd an.5. b.18. 4 w i l l indicate a rapid change in the Speci ficat ion 4.b.H. I.d reapai res that station
.. ackrate.
I f this change is not precedeil by management he notiiicd as soon as practicable an incicase in t he oil gas release rate, it and that cliorts to locate the source ol way indicat e a subs t ant i al leak has developed salioact i vi ty he s t a rt ed prompt ly.
Fo r t he in the primary syst em wi thin the react o r inns po:>e o f t h i s :.peci l'i cat ion, as soon as containment.
A relatively :.hort time. 8 pract icable should be defined as noti f icat ion hones, is allowed t o islent ily the sonice of within
.'4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and prompt ly shall mean as
~
the increased radioact ivity discha rge rat e as soon as regularly scheihiled pers:nniel can 1,e othen t han an uni:.olat al le prima ry sys t em assigned to the t a :. L.
leak before a :,hnt ihm s of the reactor is Id in i t i at eil.
'the shut down can he tesmanated by li Sat ely Valves - limperience in sa fet y valves
'd coreccting the piohicm that p roilut eil t he ope ation shows that a-testing of 50*. o f the N
h i ghe r di:.cha rge rate.
salcty valves per relucting outage is adcapaate tu elet ce t t at linics or det criorat ion.
The
'the pi s mary syst em leak size that will create tolerance value is speci fical in Sect ion li t limiting stack gas release rat e i:> calculat ed of t he AStili lioi ter an l Pressure Ves:.cl Code w
a cx as 101 lows.
Assumptions are maile that the as ill, of design pressure.
s car t o r wa t e r gi o:.3 81 activity is 10'8 p(. g / l, t he license l iini t for t he release of Amendnient. No. 14, 31 75
11a u l a. :
F.
St ruct air al leit enn i t y - Conamonweal t h IGlii.oss Cotapany s ecor,n t eca; time importance of irnpectlon of t ho:.e areau wlitcli are presesitly not.
accesullele and will study ased imp leme:nt, if
( h p rac t leale le, new means t o include t l.ose
[ Q arcate vi t hin the inspectton :e rog rar4.
This inspection provideu turther asuurance that
( 3 grous detects aie not occurring alter c
~
the systein is in aiervice.
This inspection C
will reveal probleia areas sliould they C c occur before a leak develops.
g C==>
C In.iddittoa, extensive vieinal inspection c'
for leaku will be inade periodically on b
critical sy st eins.
The inspection prograia
[D apeciile.1 encoinpasses the major areas of the vessel and piping systeins within the e on i a l mnen t. The inspection period is b.esed on the oleser ved rate of growth of ele t ect s from fatigue studies sponsored by the AEC.
These studies show that it requires thousands of siress cycles at u t r esse:, beyond any expected to occur in a r eac t o r tiy:.t em t o p rop.igat e a crack.
We tent frequency cutablie.hed is at intervals such that in enanparison to study resulas only a small nuinber of streuu cycles, at v.nlucu below limits will occur.
On thin banlu, it la considered that the test I n cejiselic i ell d & c adeaginat e.
rJ (A
NW CD N
Anemiment No. }d,31