ML20214P739
| ML20214P739 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/28/1978 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20214P736 | List: |
| References | |
| TAC-7359, NUDOCS 8706030511 | |
| Download: ML20214P739 (7) | |
Text
.
DOCKET NOS. 50-2,4_55 50-336 ATTACHMENT 1 MILLSTONE NUCLEAR POWER STATION, UNIT NOS. 1 AND 2 j:
PROPOSED REVISIONS TO ENVIRONMENTAL TECHNICAL SPECIFICATIONS j
i 8706030511 780217 PDR ADOCK 05000245 FEBRUARY, 1978 P
ppy
November 23, 1976 Unit 1 Floor Drain Sample Tanks Waste Collector Sample Tanks
()
Decontamination Solution Tank i
Waste Surge Tank l
Unit 2 Aerated Waste Monitor Tank Coolant Waste Monitor Tank Condensate Polishing Waste Neutralizing Sum e l
H.
The operability of each automatic isolation valve in t e liquid radwaste discharge line shall be demonstrated quarterly.
i I.
If limiting conditions in 2.4.1.2.A through 2.3.1.2.H above are exceeded, plant operations shall be modified as required to re-store compliance with these specifications. Prompt reporting requirements for exceeding these limiting conditions for operation are detailed in Srction 5.6.2.a. (1).
2.4.1.3 Monitoring kequirements A.
Prior to release of each batch of liquid waste, a sample shall be taken i
from that batch and analyzed for the concentration of each significant gamma energy peak in accordance with Table 2.4-1 to demonstrate compliance with Specification 2.4.1.1 using the flow rate of the strean into which the waste is diccharged during the period of discharge.
B.
Sampling and analysis of liquid radioactive waste shall be performed in accordance with Table 2.4-1.
Prior to taking samples from a monitoring
(
tank or sump, at least two tank / sump volumes shall be recirculated or equivalent mixing provided.
C.
The radioactivity in liquid wastes shall be continuously monitored and recorded during release. Whenever these monitors are inoperable for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, two independent samples of each tank to be discharged shall be analyzed and two plant personnel shall in-dependently check valving prior to the discharge. If these monitors are inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no liquid waste tank shall be released and any release in progress shall be terminated, i
D.
The flow rate of liquid radioactive waste shall be continuously measured and recorded during release. Whenever this monitor is in-operable for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, manual logging at in-tervals not to exceed one (1) hour will allow continued discharge.
If these monitors are inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no liquid waste tank shall be released and any release in progress shall be terminated.
All liquid effluent radiation monitors shall be calibrated at least Guarterly,4 E.
by means of a radioactive source which has been calibrated to a Nati6nal Bureau of Standards source. Each monitor shall also have a channel functional test monthly and channel instrument check prior to making a release.
2.4-2
MG1 1975 i
)
In addition to these limiting conditions for operation, the reporting requirements of Specification 2.4.1.2.C delineate that the licensee i
shall identify the cause whenever the cumulative release of radioactive materialu in liquid wastes exceed one-half the design objective annual quantity during any calendar quarter and describe the proposed program of action to reduce such releases to design objective levels on a timely basis.
This report must be filed within 30 days following the calendar quarter in which the release occurred.
j i
The monitoring requirements given under Specification 2.4.1.3 provide assurance j
that radioactive materials in liquid wastes are properly controlled and 1
monitored in conformance with the requirements of Design Criteria 60 and 64.
These requirements provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive liquid wastes re? cased to the environment. Reports on the quantities of radioactive materials released in liquid wastes are furnished to the Commission according to Section 5.6.1 of these Technical Specifications in conformance with M gulatory Guide 1.21.
On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may, from time to time, require the licensee to take such action as the Commission deems appropriate.
Monitoring Requirements 2.4.1.3 A through E and G and H will apply to the J
Condensate Polishing Waste Neutralizing Sump discharges only when the l
steam generator gross activity exceeds 1 x 10-7 uCi/ml. Discharges from
(
these sumps will be terminated when the Steam Generator or the S.J. A.E.
t Radiation Monitors alarm, until Monitoring Requirements 2.4.1.3A through E and G.and H are met.
)
The points of release to the environment to be monitored in Section 2.4.1 include all the monitored release points as provided for in Table 2.4-3.
]
2.4-5 i
t
.~
Ii x
3 3
l Ow s
}
)
n) 2 A
eo3
(
(
li(
8 m
bt) 5 6
5 8
6 7
0 5
8 5
8 aal
~
~
~
~
t rm 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
ct/
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 eni t eC x
x x
x x
x ecp 6
Dn(
5 5
5 5
5 5
7 o
9 C
1
~
9 1
tsu g
s s
u r
r A
s e
e a
i t
t s
t t
y i
i l
m m
f a E
E on 1
1 A
a s
3 a
3 s
e m
e 1
m 1
e py m
s m
s yt a
a I
3 a
I a
Ti G
G a
3 G
G a
S v
h 1
h
~
I i
l d
0 p
l 0
d p
S t
a e
4 l
I a
4 e
l Y
c p
v 1
A p
1 v
a L
A i
l i
l A
c o
a 9
s 0
1 c
a o
9 s
0 N
n s
L 8
s 9
3 n
L s
8 s
9 A
i s
3 o
1 i
s 3
o r
i a
r r
r r
a i
r r
r D
P D
B S
H G
S I
P B
D S
H G
S NA G
O N
ILPM
)
A 5
S
(
)
(
)
e 6
e D
1 t
(
t I
(
e i
e i
U e
t s
h t
s Q
h t
i o
t i
o I
y t
i s
p n
s p
L gc n
s o
m o
o m
nn o
o p
o M
p o
E ie M
p m
C
/
m C
V l u h
/
m o
e o
I pq c
h o
C y
}
)
l C
y T
me t
c C
l 6
p l
C ar a
t y
r
(
(
m y
r A
SF B
a y
l e
y y
a l
e O
B l
h t
l l
S h
t I
h k
t r
k k
t r
D c
e e
n a
e e
e n
a A
a n
e o
u e
e n
o u
R E
O W
M Q
W W
O M
Q 15 26 RR n
PP w
DD o
s d
oo e
u w) tt s.
e-oy 0H
.eNe l1 et R
B n 3
l O
ae e
t r
st p R nsm n
o2 oo a
t NN keau l
at dWS de n
o ri tt i c a n
)
o en nn ur T o g g7 qu C nn(
C nU ee e(
mm i o r
ii y
G dd LS o rhzs r
nn t osie a
m ee i /il s P
m a
mm ndl aa i
e AA onore r
t MaPtl P
S A
B C
U
+
August'19, 1976 Table 2.4-1 (Continued)
~(1)
A composite sample is one in which the quantity of liquid sampled is I
proportional to the quantity of liquid waste discharg;cd..
(2)
For certain mixtures of gamma emitters, it may not be possible to measure -
radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations.
of such radionuclides using measure.1 ratios with those radionuclides which are routinely identified and measured.
(3)
The detectability limits for activity analysis are based on the technical feasibility and on the potential signifieance in the environment of the quantities released. For some nuclices, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they shall also be reported.
(4)
The power level and cleanup or purification flow rate at the sample time shall also be reported.
(5)
To be representative of the average quantities and concentrations of radio-active materials in liquid effluents, samples should be collected in pro-portion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite should be throughly mixed in order for the.
composite sample to be representative of the average effluent release.
~
(6)
These analyses are required when the steam generator gross activity (sampled and analyzed 3 times per week as per the Safety Technical 3
Specifications Table 4.7-2) exceeds 1 X 10 7 p Ci/ml.
(7)
Sampling and analysis of the Condensate Polishing Waste Neutralizing Sumps, for the activity analysis shown in Table 2.4-1, are r onlywhenthesteamgeneratorgrossactivityexceeds1x10-9 quired
(
uC1/ml.
)
i 2.4-16 Amendment No. 30 to DPR-21 Amendment No. 14 to DPR-65 l
i
e f
bcC
)
a b
(#.
l m 1
hker gnva iael X
X X
HTLA Q
gn cs i
ii l
ps p
oy X
X m
X X
X a
tloa s
s sn e
I_A e
i h
t t
i s
dX l
X X
X X
e i
t
,l I
a b
c a
i p
S a
a dn N
C h
X X X
X i
O p
X 1
I l
T s
A s
A i
C s
d l.
I y
e 2
F l
vs I
a l e X
X X
X X
e C
n os l
E A
sa b
P sC a
S i
T D
LA C
,I X
X X X X
y t
I n
N i
H y
o C
t p
E si T
sv e
oi X
X X
X X X s
Y rt a
B G,Ac e
l D
e E
r R
I r
M U o
E Q en T
E bl o m
)
S R
api a
d Y
rmt X
X X
X X
X e
e S S Gaa r
u R
St t
n E E S
s i
T L
t S
P s
s n
A M
un s
o W A oor e
C S
uio c
(
D ntt o
I D
iai r
3 U N ti n X
X X
X p
Q A nd o I
oaM h
b.
L S
CR c
2 R
a R
O oe e
e W T t v l
P I
l r
b N
l a o
O ov f
a T
2 M
r t n d
T T no X
e I
N oi X
r N
E Ct i
UU a
u L
ol q
F t o e
F us r
E AI s
D e
N i
A n
t so i
S sis k_
l cam S
et r i E
a b
X C
oia X
X X
t a
O rdl p
R PaA e
a P
R g
c a
F k
r s
O n
o i a
t s
N l
O s
y l
I
)
r a T
t e
e n.
A t
s m
n t
t e
C n
e e e e
s e
O i
T p
t t
m r
L o
(
i s
e o
e o
a v
e h
P P
y p
P t
o W
l t
e S
i
(
s l
e e
l e
P y
F g
u e,
s p
g n
S
(
f t s a
m r
w e
ns e
at e
a m
a o
g
's g
s i p r cn l
S e
h d
r n
p hm ie e
t c
w a
k) i ss su e dm R
e s
s o
h nd l
t h
ne t
y i l
c ae o
S iS t
i r r
s S
D B
s Tt o
l i
o e
i a
C g
og y su W
t e
r D
en n
P n l
nq s
n t
o gi d
i n me s
s a
s t
r am e
d i
o ur e
u l
e a
e ra s
l ez l
r o o w
r t
ot o i ti s
os
=
t e
o d
e a
t n l
u al e
ci S
n C
a n W So C
B d
s a
R e
C sa u
ey s
l y
G e
r r
e) nr l
sl s
l r
d c
oy a ns et c ea e
e a
i m i ol e
ind u n hn c
c m
u a
v dl l
bi I
Ta o
s i q
e r
t a c
ra ne r
i r i t
e ui u
ur oN P
M P
L S
S Ot N
TD C w*s o
[
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-336/245 CC: REID R W ORO: SWITZER D C DOCDATE: 02/17/78 NRC NE NUC ENERGY DATE RCVD: 02/24/78 XTYPE: LET TEF.
NOTARIZED: YEE.
COPIES RECEIVED LTR 3 ENCL 40 UDJECT:
?cENI.E NO DFA-21 0 65 AFPL FOR AMEND: ENVIROW TECH SPEC PROPOSED-
@NGE CONCERNING REVISIlJG SECTION 2. 4, RADIOACTIVE EFFLUENTS, TO ICORPORATE INTO THE ETS REE.TRICTIONS ON THE RADIOACTIVE WASTE OFLUENT.
REVIEWER INITIAL:
XJM
- . ANT NAME: MILLSTONE 4 2 DISTRIBUTER INITI AL:
MILLSTONE tu
- -*e,****-e,***$
DISTRIEUTION OF THIS MATERIAL IS AE. FOLLOWS +*****************
CHANGE REQUESTS FOR ENVIRON TECH SPECS (ADPEND-B)
(DISTR 15U~i10N CODE COO 4)
N FOR ACTION:
DR CHIEF REID++W/ ENCL
'RCJ MGR CONNER **W/ ENCL LIC ASST INGRAM**W/ ENCL.
INTERNAL:
REG FILE **W/ ENCL NRC PDR**W/ ENCL I & E*+W/2 ENCL OELD**W/ ENCL GOSSICK 8e STAFF **W/ ENCL HELTEMES**W/ ENCL EISENHUT**LTR ONLY B GRIMES **W/ ENCL J MCGOUGH**W/ ENCL DENTON & MULLER **LTR ONLY BALLARD**W/ ENCL VOLLMER**LTR ONLY J COLLINS **W/ ENCL KREGER**W/ ENCL EXTERNAL:
LPDR'S WATERFORD, CN**W/ ENCL NATL LAE**W/3 ENCL NSIC**W/ ENCL TIC **W/1 ENCL M'
ACRS CAT B+4-W/16 ENCL DISTRILUTION:
LTR 40 ENCL 37 CONTROL NBR:
780590020 SIZE: 2P+1P*6P
- 4+++++-******4-*******++*****
THE END
+++*******************++*******+++'
...._.J