ML19317G712
| ML19317G712 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 04/12/1978 |
| From: | Kaplan D, Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19317G713 | List: |
| References | |
| NUDOCS 8003270688 | |
| Download: ML19317G712 (3) | |
Text
,
. ~. - -.. -
4 N
g (lf 9 q
- A j
. FFG!!i.ATORYf I:
3RMATION DISTRIBUTION sV5L (6:I D E )
'V ill DISTRIBUTION EOF' TNCOMItG r!ATEPTAL 4
- REC; > COLIER K R ORo
- r f A~~T T if M JJ OV DATE v 4 ' 8. 2. ' M SACRA. 9NTO WS! UTIL D ! T.T usie PC 'JD.
.4.'l
?
NF.C COFIES PECEI'/ED i DOCTYFC: LETTER NOTAFI 7ED: NO LTR 1 Et!CL a0 l SUT), tEC 7 :
f r0RMARDi.HO.i.IC NO TPP-4 AFPL FOR i.iFND ;40 ~B aFFENDI: B iECH EFECS PROPO9EO
! CHANGE CONCERT!ING M'.!! SIGHS = TO ii r Si..*iPi. INa - NE riO:liTGRIeiG MZQUIRFNENTS COP IGASEOUS. RADIOACTIVE EFFLUEHi. at SUT?JECi t vo.1LI TY.
i l
I
g*(
f PLAMT marie: RANCHO GECO (:? MUD i F EVI Etif-R INI T I AL:
D ISTRIEUTOik INITIAL:
t 4 H +m++*->+*44:t*. DICTRIBUTION OF THIS MATERI AL IS A5 FOLLOW 5
- m 444343^**44^**
i i
C HHw w. nexOESTS FOR EFWIRON TECH SFECS (AFPEHD B) f (DI5TnII.UTIOri CODE COO 4 )
4 1
-On m.; it N' f L ? ' -'- ' - ' '-
v !Jf G T N Gl, J
i I NTERi !Ai.
FEO FIL E++WAF1 Ni-:C PDRmjRNCL OELIa*W/ ENCL 1
~ ;E r.c t.
1 60Si:,Ir.K P.
E.T AFP >4i/EliCL HELTE HES+eWfi_NC L i
t EIEEiWUT*-sLTR OHLY EEB+-W/Euc L J HCOO!..lGHeeW/ENCI dei!rOri _ HULL EiW5Lre Onty i
BALLftRO**W/ ENCL VOLLMER"eLTR OHLY J COLLIN5M W/ ENCL KFEGEhen:/Ehcie EXTERNAL.
LPDR'S SACPAMENTO, CA**W/ ENCL REGION V+-4-W/ ENCL i
11ATL LAB **W/.? ENCL k
D pD 0g l
N51Ds41/EriCL
.rutw i
TICo*W/1 ENCL hu "I\\'
I I'
ACRS C A T R e v u.e 1., ENFL s.- c l
t 1
1 i;
i, l
4 I
I i
- - DISTRIT,UTIOhi
LTR 43 EiJnt. in -
COi 4 TROL HEF
^J I
, - 3,/,s v i t g...
4, "t.,r
- ---s",>>>-+
P4c b Pr p.-t +. t p e en oc n e M i
- t-tf e t et-e ea,94-u s-r-THE E.N'
<- e rr-m 3..
~
l 8003 270[ g u
a l
4
.ttg*vw='F4'$wPWf***w-7-f*
s-,,ww-e,<w+=--
g,,e,w...,
wai-,.y
+g, iyw-w q, e-s-e--ar my-em'.e r-'w v c m we--w ww 'we ure-w'e-----*wvrww w= aF* ew erwine euzumsyv'=#www =ww'rwe te ev* eeve-w 'ww w eemw www 'w Wv t
t' s
~ gSMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT C) 6201 S Street, Box 15330, Sacramento, California 95813; (916) 452 3211 April 12, 1978
~
Director of Nuclear Reactor Regulation ATTN: Karl R. Coller Assistant Director for Operating Reactors Division of Operating Reactors L,
U. S. Nuclear Regulatory Commission Washington, D. C. 20555 3
s o
.n, m
i:
v>
~3 Re: Operating License DPR-54 0
Docket No. 50-312 Proposed Amendment No. 56
Dear Mr. Goller:
In accordance with 10CFR50.90, the Sacramento Municipal Utility District hereby proposes to amend its Operating License DPR-54 for Rancho Seco Nuclear Generating Station, Unit No.1 by submitting forty (40) copies of Proposed Amendment No. 56.
Technical Specifications, Appendix B, Section 2.6.4 sets forth the sampling and monitoring requirements for gaseous radioactive effluents.
In the two and one-half years that the plant has been in operation, the need for several deletions, additions, and revisions to the specifications has become ob vio us.
The first request is to add a monitoring requirement to section 2.6.4.B and a sampling requirement to Figure 2.6-2 for auxiliary building exhaust fan E F-A-9.
This fan (19,000 scfm) takes suction from the controlled area of the auxiliary building and has an unmonitored exhaust on the auxiliary building roof. While the equ pment in areas serviced by the fan (electrical penetrations, motor control centers, and other ventilation equipment) are not sources of radioactivity, airborne activity released from nearby equipment could reach the fan suction.
On the grade level of the auxiliary building, where one of the fan suction gratings is located, the solid radwaste drumming station and access hatches for the radwaste ion exchangers represent potential sources of airborne activity since they are not isolated from the fan suction by structural walls.
The addition of monitoring and sampling requirements for this release point will assure that airborne activity is not released without being detected and measured. Curren tly, the fan exhaust does not have a monitor; and until one is installed, the fan will not be utilized.
Specification 2.6.4.B requires monitoring of gaseous releases to the environment, and specifies corrective action if the monitors are inoperable.
The specification does not identify what the release points are for those h
a pe s o
b (.tC s a 1
mm
- i,-
,y 1
- [*
7)
A 4
~ Director of Nuclear Reactor' Regulation April 12, 1978 gaseous' releases. The proposed change to this paragraph identifies release
- points requiring-monitoring as the auxiliary building and_ reactor building stacks, :in addition to fan EF-A-9. previously' mentioned. Rewriting the paragraph in this manner. identifies all gaseous radioactivity release points, eliminating any confusion that might arise from the vague wording of the
- current sp'ecification.
A new paragraph is proposed, which would.specify monitoring requirements for the Conden'ser Air Ejector and the Gland Seal exhausts. Neither of these streams is an environmental release point, because they are routed to the auxiliary building stack.
For tnis reason, no sampling requirement is proposed; and'the. monitoring is only required for gaseous' activity.
The purpose for monitoring these streams is to identify primary to secondary leakage, which is effectively accomplished by the proposed paragraph.
.The final change is proposed for Table 2.6-2, which is lis ted as a requirement in paragraph 2.6.4.F.
Similar to the change made for the monitoring paragraph, exhaust fan EF-A-9 requirements have been added, and
~
the two other environmental release points have been identified. The require-for' Condenser Air Ejector sampling has been deleted since it is not an ment environmental release point.
Respectfully. submitted, Ad
,, A
[hh.d$.Mattimoe Assistant General Manager and Chief Engineer JJM:RJR:sc I
Enclosures w
N
?
i
(2)
If the average release rate of all iodines and radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter is:
8.55 x 106q
>1 (3)
If the amount of iodine-131 released during any calendar quarter is greater than 0.5 C1.
D.
During the release of gaseous wastes from the primary system waste gas holdup system, the effluent monitor shall be operating and set to alarm and to initiate the automatic closure of the waste gas discharge valve prior to exceeding the limits specified in 2.6.3.A (1) above. The operability of the automatic isolation valves shall be demonstrated quarterly.
E.
The maximum activity to be contained in one waste gas storage tank shall not exceed 135,000 curies (considered as Xe-133).
2.6.4 Specifications for Gaseous Waste Sampling and Monitoring A.
Plant records shall be maintained and reports of the sampling and analysis results shall be submitted in accordance with Section 5.6.1 of these Specifications. Estimates of the error associated with each reported value should be included.
B.
Gaseous releases to the environment, except from the turbine building ventilation exhaust and as noted in Specification 2.6.4.C, shall be continuously monitored for gross radioactivity, and the flow measured and recorded. These releases originate from the reactor building stadc, from the auxiliary building stack, and from the radwaste service area fan (EF-A-9). Whenever a monitor at one of these release points is inoperable, grab samples shall be 56 taken and analyzed daily for gross radioactivity.
If a monitor is inoperable for more than seven days, releases from that point shall be terminated.
C.
The condenser air ejector and the gland seal exhausts shall be continuously monitored for gaseous radioactivity.
If a monitor is' inoperable, grab samples shall be taken and analyzed daily j
for gaseous radioactivity.
D.
During the release of gaseous wastes from the primary system waste gas holdup system, the gross activity monitor, the iodine col-lection device, and the particulate collection device shall be operating.
E.
All waste gas monitors shall be calibrated at least quarterly by means of a known radioactive source which has been calibrated to a National Bureau of Standards source. Each monitor shall i
have a functional test at least monthly and instrument check at least daily. Proposed Amendment No. 56 J
~
y - -
.s e
F.
. Sampling and analysis of radioactive material in gaseous waste, particulate form, and-radioiodine shall be performed 56 in accordance with Table 2.6-2.
Bases The release of radioactive materials in gaseous wastes to unrestricted areas shall not exceed.the concentration limits specified in 10 CFR Part 20, and in accordance with the requirements of 10 CFR Part 50.36a.
-These specifications provide reasonable assurance that the resulting annual air dose due to gamma radiation will not exceed 10 mrad, and.an annual air dose due to beta radiation will not exceed 20 mrad from noble gases and that the annual dose to any organ of an individual from iodines and particulates will not exceed 15 mrem. At the same time these specifications permit the flexibility of operation, compatible with con-siderations of health and safety, to assure that the public is provided with a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within-the concentration limits specified in 10 CFR Part 20.
It is expected that using this operational flexibility under unusual operating conditions, and by exerting every effort to keep levels of radioactive material in gaseous wastes as low as practicable, the annual releases will'not exceed a'small fraction of the concentration limits speci14ed in 10 CFR Part 20.
These efforts should include consideration of meteorological conditions during releases.
.There is a reduction factor of 243 by which the maximum perm'ssible concentration of radioactive iodine in air should be reduced to allow for_the grass-cow-milk' pathway.
(The factor is 1220 for the grass-goat-nd.lk. pathway.) This factor has been derived for radioactive iodine, taking into account the milk ' pathway.
It has been applied to radionuclides of iodine where milk is not a pathway. of exposure or for the other radio-nuclides.
The ' design objectives have been developed based on operating experience taking into account a combination-of system variables including defective fuel, primary system leakage, primary to secondary system leakage, and the perfermance of the various waste treatment systems.
For Specification 2.6.3.A(1) dose calculations have been made for the
-critical sector. 'These calculations consider site meteorology, buoyancy characteristics, -and radionuclide content of the effluent
_ Proposed Amendment.No. 56