ML19260B013
| ML19260B013 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/26/1979 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18081A716 | List: |
| References | |
| P78-159-57, NUDOCS 7912060335 | |
| Download: ML19260B013 (69) | |
Text
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LIST OF PROPOSED CHANGES TO THE DRAFT RADIOLOGICAL EFLUENT TECHNICAL SPECIFICATION Comment No.
Page Change Justification la 1-1 Redefine We don' t agree that process control the p ocess control program should be a set of operating procedures.
The o riginal defi-nition is too restrictive.
lb i-2 Redefine We have changed the Solidification definition to emphasize that waste such as rags etc. may not be uniformly distributed.
Ic 3/4 3-44 Change section This change is consistent i from 3.3.3.8 with our present speci-to 3.3.3.7 fications.
ld 3/4 3-44 Change word?
This change clarifies station log la exactly which log is o rig inal sur-to be updated.
veillance require-ment 1.3.3.8..
to liquid release permit 1
3/4 3-45 Delete word Gross radioactivity
" e f fluen t" monitors provide from item 1.b automatic termination and indicate that of SGB blowdown.
there is one Effluent is therefore monitor steam not directly monitored g ene r ato r but is indirectly.
monitored.
Action statement number are resequenced.
2 3/4 3-45 Delete original Our facility does not Item 1.c have a separate turbine building.
All d rains are routed to the main condenser and recycled.
1520 095 P78 159 57 60 32555 79120 SNGS-UNIT 1
s LIST OF PROPOSED CRANGES TO THE DRAFT RADIOLOGICAL EFLUENT TECHNICAL SPECIFICATION Comment No.
Page Change Justification 3
3/4 3-45 Delete original The locating of a item 2 radiation monitor on the service water would be impractical due to the large dilution factor caused by the service water.
It is more effective to measure the source of activity before dilu-tion occurs.
In addition, the facility has a closed loop component cooling system and there is no e f fluer.t.
4 3/4 3-45 Delete original Rinse water, flush, footnote and slurry waste from the station's conden-sate demineralizers are not anticipated to be active enough to ever require auto-matic termination.
However, any effluent from the condensate demineralizers will be continuously monitored.
5 3/4 3-46 Delete item 3.b Since pump curves are discharge canal used to estimate the flow monitors discharge canal flow rates action #21 is not required.
It is therefore unnecessary to include item 3.b.
6 3/4 3-46 Delete word See Comment fl.
effluent in item 3.c 1520 096 P78 159 58 SNGS-UNIT 1
4 LIS'.' OF PROPOSED CHANGES TO THE DRAFT RADIOLOGICAL EFLUENT TECHNICAL SPECIFICATION Comment No.
Page Change Justification 7
3/4 3-46 Delete item 4 Alarm / trip set points are not recorder controlled.
8 3/4 3-46 Delete item 5 Tank overflow is highly unlikely for possible radioactive outdoor storage tanks.
The refueling water storage tank and the primary water storage tank may contain activity.
- However, their overflow is routed to the liquid radwaste treatment system.
Although the individual tanks do not have special dikes or retention ponds since this would be poor utilization of station property, these tanks are of the highest quality and are designed to hold their integrity even through an earthquake:
These tanks are designed to Nuclear 1,
Seismic 1 Class.
9 3/4 3-46 Delete footnote See above comment.
10 3/4 3-47 Delete item 6 The f acility does not need continuous com-posite samplers for sampler flow monitors.
The SGB liquid effluent passes through a radi-ation monitor prior to its discharge, there-fore,.a continuous compositor, hence, a sampler flow monitor is not required.
P78 159 59 SNGS-UNIT 1 1520 097
LIST OF PROPOSED CHANGES TO THE DRAFT RADIOLOGICAL EFLUC. TECHNICAL SPECIFICATION Comment No.
Page Change Justification 10 (Cont'd)
Th e facility does not have a turbine building.
See comment # 2.
11 3/4 3-47 Delete footnote See comment #4.
12 3/4 3-49 Delete word See comment #1.
" effluent" item 1.b 13 3/4 3-49 Delete item 1.c See comment #2.
14 3/4 3-49 Delete item 2 See comment #3.
15 3/4 3-49 Delete item 3 See comment #10.
16 3/4 3-50 Delete item 4 See comment #7.
17 3/4 3-50 Delete item 5 See comment #8.
18 3/4 3-50 Delete footnote Not to be referenced in text if section 5
.2 deleted.
19 3/4 3-51 Delete footnote Radiation monitors (1).3 and (1).4 must be removed from active service to have periodic calibrations.
It is not reasonable to have the isolation valves that the moni-tor control to adti-vate and slam shut each time that the system is calibrated.
Most modern RMS systems ccme equipped with a special test mode which unlike the operate mode blocks the trip action of the system although the alarm indication is not inhibited.
1520 0,10 P78 159 60 SNGS-UNIT 1
LIST OF PROPOSED CHANGES TO THE DRAFT RADIOLOGICAL EFLUENT TECHNICAL SPECIFICATION Comment No.
Page Change Justification 20 3/4 3-52 Delete footnote This requirement 4
doesn't apply.
See comment #3.
21 3/4 3-52 Delete footnote See comment #7.
6 22 3/4 3-52 Delete footnote See comment #8.
7 23 3/4 3-52 Add sentence A channel check is to footnote on not required if channel check pump curves are utilized.
23a 3/4 3-53 Redefine sur-This clarifies that veillance re-the ODCM is not a quirement procedure but is a 4.3.3.8.3 document which is to be used as a guide.
23b 3/4 3-54 Delete item Those changes are 1.b-3 and 2A necessary to account for presently installed equipment.
24 3/4 3-56 List vent in Required applicable portion as item 4.0 25 3/4 3-56 Resequence foot-These systems are notes and reword routed to the vent also containment header system.
purges in item.
26 3/4 3-56 Delete SGB The effluent from this system is not monitored.
Pro-vision 5.6.3 of NUREG 0133 will be elected.
1520 091 P78 159 61 SNGS-UNIT 1
LIST OF PROPOSED CHANGES TO THE DRAFT RADIOLOGICAL EFLUENT TECHNICAL SPECIFICATION Comment No.
Dage Change Justification 26a 3/4 3-57 Reword action Our station has the statement 29 ability to also mon,itor the vent with another monitor called the plant vent / containment monitor.
27 3/4 3-59 Co r ? e et item 2 Required.
specify type of moni oring system 2 f-3/4 3-61 Change table as See comments 24-25 indicated and 26.
t 29 3/4 3-62 Delete (1).4 See comment 19.
30 3/4 3-62 Change the word The RMS is designed
" intended" to to function to a very
" normal" high range.
Th e system will not be tested periodically with high activity source over its
" intended" range but will be tested over its normal range in order to prevent unnecessary radiation exposure.
30a 3/4 3-63 Change the As long as the solutio e channel cali-used are standards the bration from oxygen content shouldn't 4% oxygen to
- matter.
2% oxygen 31 3/4 11-3 Change words plant Present wording is continuous re-vague.
Failure to leases, into steam make this change generator blowdown. may imply that all releases from sta-tion, however tri-vial must be con-tinuously monitored.
P78 159 62 SNGS-UNIT 1
4 LIST OF PROPOSED CHANGES TO THE DRAFT RADIOLOGICAL EFLUENT TECHNICAL SPECIFICATION Comment No.
Page Change Justification 32 3/4 11-3 Change words con-This change is nec-tinuous to weekly essary since con-in Item 8 Table tinuous releases do 4.11-1 first item not account for a down.
large percentage of the radioactivity discharged.
Grab samples may be over conservative some weeks and under conservative others.
Continaous sampling is not noccssary.
Thic change is consistent with the present ETS for Salem Units 1 and 2 for SGB monitoring.
33 3/4 11-3 Change words con-See Comment 32.
tinuous to com-posite.
34 3/4 11-4 Delete word con-See Comment 32.
tinuously from Item D Table 4.11-1 footnotes.
35 3/4 11-4 Delete Item F.
No longer referenced.
36 3/4 11-6 Delete action Q.2 Drinking water is not from Spec.
taken from the receiv-3.11.1.2.
ing water body.
l520 101 P78 159 63 SNGS-UNIT 1
LIST OF PROPOSED CHANGES TO THE DRAFT RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS COMMENT NO.
PAGE CHANGE JUS"tIFICATION 37 3/4 11-7 Change words, "over 31 days The Company plans to op-would exceed 0.06 mrem to the erate 4 nuclear reactors total body or 0.2 mrem to any at the Artificial Island organ," to, "over a calendar Site.
The licensee would quarter would exceed 0.375 mrem need flexibility of opera-to the total body or 1.25 mrem tion, compatible with con-to any organ."
siderations of health and safety, to assure that the public is provided with a dependable source of power.
This change is consistent with 10CFR50-App. I Section IV.
The value proposed corresponds to one eighth of the annual design objectives.
38 3/4 11-8 Delete page.
See item 8.
P78 160 48/49 SNGS - Unit 1 1520 102
LIST OF PROPOSED CHANGES TO THE DRAFT RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS COMMENT NO.
PAGE CHANGE JUSTIFICATION 39 3/4 11-11 In Item C, delete all other re-The condenser air ejectors lease points, except for air are the only potential ejectors.
significant release point.
40 3/4 11-11 Delete Item D, and replace by Required release point for the words, " plant vent."
monitoring.
41 3/4 11-11 Delete Footnote F on Table The spent fuel pool exhaust 4.11-2 under sampling frequency.
lead to the plant vent where it is sampled.
42 3/4 11-12 Delete Footnote F.
See Footnote 41.
43 3/4 11-15 Change Spec. 3.11.2.4 from See Comment #37.
"over 31 days would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation" to "over a calendar quarter would exceed 1.25 mrad for gamma radiation and 2.5 mrad for beta radiation."
44 3/4 11-17 Delete Page 3/4 11-17.
Our system is not designed to withstand a hydrogen ex-plosion.
45 3/4 11-19 Add 36 00 curies to space Requested information.
indicated.
We feel that weekly is more we propose that the surveillance practical, requirement be weekly instead of within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
46 Intentionally blanked 47 3/4 12-3 Replace Tables with current Required.
Radiological Monitoring Pro-grams.
P79 02 07 1520 103
LIST OF PROPOSED CHANGES TO THE DRAFT RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION COMMENT NO.
PAGE CHANGE JUSTIFICATION 48 Intentional blank 49 Section 6 Change words " Plant Superintendent" to " Station Manager."
50 Section 6 Change " Unit Review Group" to "Sta-tion Operating Review Committee (SORC)."
51 Section 6 Change " Company Nuclear Review and Audit Group" to " Nuclear Review Board (NRB)."
52 Section 6 Change " Superintendent of Power Plants" to " General Manager -
Electric Production."
53 Section 6 Change "Vice President Operations" to "Vice President Production."
54 6-13, Delete Item 6.8.1.b.
The REMP is not a safety 6-14 related system and should not require approval by a Senior Reactor Operator.
55 6-15 Delete parathentical reference
P79 02 08 1520 104
1.0 DEFD::TIONS f CHAtulEL CA:.::UTION t.9 A Ch!.':':EL CALIBRATION shall be the adjustment, as necessary, of the l
, channel :u*.put such that it responds with the necessary range and accuracy to 'me.m values of the parameter which the channel monitors.
The CHA.*uiEL
- CALIBRATIC
- : shall enconpass the entire channel including the sensor and
'alam and/or trip functions, and shall include the CHAinJEL FC::"TIONAL TEST.
The CHANNEL CALIBRATI0tl may be perfomed by any series of sequential, over-lapping or total channel steps such that the entire channel 1.s c al ib ra ted.
t
- iCHAtalEl CHECK 1.10 A CHAta:EL CHECK shall be the cualitative assessment of channel be-
.havior during operation by observation. This detemination shall include, where possible, comparison of the channel indication and/or status iith other indications and/or status derived from independent instru.entation
. channels measuring the same parameter.
CHAtulEL FUNCTIONAL TEST 1.11 A CHA!alEL FUNCT10tlAL TEST shall be:
Analog channels - the injection of a simulated signal in to a.
the channel as close to the sensor as practicable to verify OPERABILITY including alam and/or trip functions.
b.
Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alam and/or trip functions.
SOURCE CHECK 1.27 A SOURCE CHECK shall be the qualitative assessment of channci response when the channel sensor is exposed to a radioactive source.
N SPROCESSCONTROLPROGRAM 1.28 A PROCESS CONTROL PROGRAM (PCP) shall be the nanual
' describing the program of sampling, analysis, and evaluation within which SOLIDIFICATION of radioactive vastes from liquid isystems is assured.
Requirements of the PCP are provided in ISpecification 6.14.
1-1 F a l e.-
L'ni t 1 1520 105
l.0 SEFINITIONS (Continued) 50L:0!FICATION
,_l.29 SOLIDIFICATION shall be the conversion of radioactive I, liquid wastes from treatment systems to a ho=ogeneous (uniformly
' dis -ibuted), monolithic, i==obilized solid with definite volume and shape, bounded by a stable surface of distinct outline on iall sides (free-standing).
'CCFSITE DOSE CALCULATION MANUAL (00CH)
An OFFSITE DOSE CALCULATION MANUAL (00CM) shall be a manual ce 1.30
'ing tne methodolcgy and parameters to be used in the calculation of off-site ccses due to radioactive gaseous and liquid effluents and in the
!l calculation of gaseous and liquid effluent monitoring Instrumen
'. al arm /trie se t cints.
i Specificatice 6.15.
Recuirements of the 00CM are provided in GAEEC23 R DWASTE TREATPENT SYSTEM I.31 A GASEC.S RA0 WASTE TREATHENT SYSTEM is any system designed I
stalleo to ry:. e radioactive gaseous effluents by collecting primary e coolart systea l or hoicuc for tne purpose of reducing the total radioactivity prior release to the envirarrnent.
i VENT!LATION E :"AUST TREATMENT SYSTEM 1.32 A NEHTI ATION EXHAUST TREATMENT SYSTEM is any system designed and l
installed to educe gaseous radiciodine or radioactive material in parti-culate for n 1.
effluents by passing ventilation or vent exhaust gases l
through charccal adsorbers and/or HEPA filters for the purpose of reinoving l
iodines or pa--iculates from the gaseous exhaust stream prior to the l
release to the envirorrient.
effect on nobl e gas effluents.Such a system is not considered to have any Engineered Safety Feature (ESF) atnospheric cleanuo systems are not considered to be YENTILATION EXHAUST TREATMENT SYSTEM co ;one-ts.
I Sale = - Unit 1 1-2 l'
1520 iu,b
_,7
TABLE 1,2 FREQUENCY NOTATION NOTATION FREOUENCY S
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
O At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
SA At least once pe.- 184 days.
R At le.st once per 18 months.
S/U Prior to each reactor startup.
P Completed prior to ea:h release.
N.A.
Not applicable.
1520 107 Salem - Unit 1 1-3
INSTRUMENTATICH RADI0 ACTIVE LIOUID EFFLUENT INSTRUMENTATI0tl
' LIMITING C0!.DITION FOR OPERATION 3.3.3.7 The radioactive liquid effluent monitoring instrumentation
!* channels shun in Table 3.3-11 shall be OPERAELE with their alarm / trip a setpoints set to ensure that the limits of Specification 3.11.1.1 are linct exceeded.
i APPLICABIL!'Y: As shown in Table 3.3-11.
lll ACTION:
l l
a.
With a radioactive liquid effluent-monitoring instrumentation j.
channel alarm / trip setpoint less conservative than a value which will ensure that the linits of 3.11.1.1 are met, imme-c li diately suspend the release of radioactive liquid effluents il monitcred by the affected channel or declare the channel in-operable.
1 b.
W1th Me or more radioactive licuid effluent monitoring in-strume tation channels inoperable, take the ACTION shown in Tabl e 2. 3-11.
E c.
The provisions of Specifications 3.0.3 and 3.0.4 are not ll appl icabl e.
SURVEILLANCE REOUIREMENTS p4.3.3. 7.1 The setpoints shall be deter nined in accordance with procedures as described in the 00CM and shall be recorded in the liquid release pe.cnit
- 4.3.3. 7.2 Each radioactive liquid effluent monitoring instrumentation j channel shall be demonstrated CPERABLE by perfonnance of the CHANHEL
); CHECK, SOURCE CHECK, Cl4ANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST
'. operations during the MODES and at the frequencies shown in Table 4.3 7 4.3.3.7.3 Records - Auditable records shall be maintained of all radioactive liquid effluent monitoring instrumentation alarm / trip setpoints.
Se1' points and setpoint calculations shall be available for review to ensure that the limits of Specification 3.11.1.1 are met.
Salem - Unit _
1520 103
TABLE 3.3-11 RADICACfl*JE L10U19 Eff LutliT 12.::ITORil:G lilSTRU:titlTATIO:1 s,
II Hit!It10M ACT10tl_.
8 Cllat::lCLS APPLICABILITY _
OPERABLE c
INSTRUMEtlT g
o 1.
Gross Radioactivity Monitor:
Providing Automatic Termination g
of Release At all tinas during releases 23 (1)
Liquid Raduaste Effluent Line a.
24 At all times during blowdown b.
Steam Generator Slowdown (1)/ per S. <;
Line
- 2. 7 Flow Rate lleasurement Devices At all times during release 25 Liquid Radwaste Effluent Line (1) a.
1:
(
26 At all times during blowdown Y2.
Stea:n Generator Blowdown Effluent (1)/Per S.G fn b.
Line LT1 i d
- =Pum;> curves may be utilized to estimate flow; in such cases, action statement 21 is not requ re t-G
~
O O
43 l
TABLE 3.3-11 (Continued)
TABLE NOTATION ACTION 23 With the number of channel Minimum Channels OPERASLE requirements OPERAB resuMd for up to 14 days, provided that prior to initi ti, effluent a release:
a ng 1.
with SpecificationAt least two independent samples ar 4.11.1.1.3 e analy:ed ir accordance
, and; 2.
At least two technically qualified Staff indepencently verify the releasmembers of the Fa and discharge valving; e rate calculations Otherwise, asr.end release of radioacti pa thway.
ve effluents via this ACTION 24 With the number of channel Minimum Channels OPERABLE requireme samples are analyzed for gross radi nt, effluent releaser, via days provided grac a limit of detection of at least 10-gctivity (beta or gamma) uCi/ gram; 1
At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when th secondary coolant is > 0.01 uti/ gram COSE EQUIe s 2
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the VALENT I-131.
secondary coolant is 3 0.01 uC1/g.am DOSE EQUIsp ACTION 25 With the number of channels OPER VALENT I-131.
required by the minimum channels o ABLE less radioactive effluent than perable relea.ses via this pathway mayrequirement, continue for up to lh estimated at days provided least onceper 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> durint; the f2.ow releases.
rate is e.c t u al ACTION 26 With the number of chann l Minimum Channels OPERABLE requireme
, effluent releases via rate is e i
releases.stimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actu
{
sales. Unit 1
\\520 \\\\U 3/' 3-48
7 TABLE 4.3-7 P
O RAD 10 ACTIVE LIQUID EFFLUDIT MONITORiflG IllSTitullErlTA110fl SURVEILLANCE REQUIRDIENTS e
CllAfillEL CllANNEL SOURCE CHAtit!EL FullCl10NAL
?
INSTRUMENT CilECK CilECK CALIBRATION TEST 1.
Gross Beta or Garrma Radioactivity Honitors Providirg Alarm and Auto-matic isolation a.
Liquid Radwaste Effluents Line D*
P R(3)
Ofl) b.
Steam Generator Blowdown D*
H R(3)
O(1)
Line 2.
Flow Rate Measurement Devices a.
Liquid Radwaste Effluent Line 0(5)
{
N.A.
R q
Ib}
b.
Steam Generator Blowdown Line D
ti. A.
R q
g S
- During releases via this pathway hJ C'3 amme=4 W
T/.l!LE
- 1. '.7 (Cont m TAGLE t!.:' ~ ~' t ?!
(1) The
- * '. FUttf.'. iO!l TEST shall al so C m "' rate th.it aut:':n t'c i st.. !
,,n of thi; pt.".::.it.y and cct:* ;l roa' al ar 1 annrnciatica c..;rs i f.;. j c f t!.c fol l o o cor.di tio r..,
- e. i s t :
1:.;tru...ent in jic.. :s '.1:;asur d 1.ev-10 abe. e f.*.. alarn/;-ip a.
t t p'.. i n t.
b.
lore g power (3) The initial CE'.!mEl CtLICTf'TIO!! for radicac tivity measurement pr-stru. ::ntatica : halloc perf iued using one or..: ore of the refarence standards cc. tified by thc !;ational Bureau of Standarris or using standards that have bec.n obtained frem.up:1icci that participate in measure:. tent assurance w.. tivi tics wi th !GS.
Itw-standards should permit calibra tint the syst' m over i ts intor.Jott rane;c o'f enerqy and rate capa;ilities 1520 112 Salem - Unit 1 J. /4 3-51.
TABLE 4.3-7 (Continueo)
(5) CHA!!!!EL CHECK shall consist of verifying indication of ficw during periods of release. CPANilEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.
Not applicable where pu=p curves are utili::ed.
\\ b2D
\\ \\,'
Sales - Unit 1 3/4 3-52
I IllSTRU"D:TATION
' RAJICACT!vE GASEOUS PROCESS AND EFFLUENT MONITORIttG INSTRuriENTATION LIMITING CONDITION FOR OPERATION
- 3. 3. 3. 8 The radioactive gasacus process and effluent monitoring instru-mentation channels shown in Table ~ 3.3-12 shall bc OPE?.AELE with their alarm / trip setpoints set to ensure that the limits of Specifica-tion 3.11.2.1 are not exceeded.
APPLICABILITY: As shown in Table 3.3-12.
'ACT!ON:
j a.
With a radioactive gaseous process or effluent monitoring in-trumentation channel alam/ trip setpoint less conservative I
than a value which will ensure that the limits of 3.11.2.1 are mec, declare the channel inoperable.
b.
With one or more radioactive gaseous process or effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.3-12.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e.
- SURVEILLANCE REOUIREPENTS 4.3.3.8.1 The setpoints shall be detemined in accordance with crocedures
, as described in the 00CM.
i f 4.3.3.8.2 Each radioactive gaseous process or effluent monitoring instrumen-
[tation channel shall be demonstrated OPERABLE by perfomance of the CHANNEL
. CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANMEL FUNCTIONAL TEST opera-
- tions during the MOCES and at the frequencies shown in Table 4.3-8 4.3.3.8.3 Auditable records shall be maintained of the calculations Described in the OCDM of the radioactive process and ef fluent monitoring instrumentation alarm / trip setpoints.
Setpoints and setpoint calculations shall be avail &Lle for review to ensure that the limits of Specification 3.11.2.1 are met.
i Salem - Unit 1 3/4 3-53 1520 114
y TAllLE 3.3-12
~
O RADI0 ACTIVE GASEOUS Erf tUCitT t 0t4IT0ltitlG liiSTiturlEt11 AIION lilitiflull CilAtitl[LS g
illSTRut4EllT 01'ERAul.E APPL.ICNllLITY PAllAt4ETER ACTlatt P
1.
Waste Gas lloldup System a.
Waste Gas Release Monitor (1)
Radioactivity lleasurement 27 2.
Waste Gas Holdup System combur.ttble Gas flonitoring System w
'l o Oxygen Monitor (1)
$ Oxygen 32 m
I i
i I
c.n N
CD 6
TABLE 3.3-12 (continued) c4 RADI0 ACTIVE GASE0US EFFLUEllT M0tilTORIllG litSTRUMEtlTAT10tl l
U b
o HItill1UM c:
D
'CilAtitlELS I
ItiSTRutiErli OPERABLE APPLICASILITY PARM'ETER ACT.T e
i 3
Plant Vent #
a.
floble Gas Activity Radioactivity Rate Measurement 29 j
Itonitor (1) i b.
Vent Verify presence of cartridge 33 Iodine Sampler Cartridge (1)
)
c.
Vent Verify presence of filter 33 Particulate P. ample r (1)
Filter w
System Flow Rate Measurement 28 2
d.
Effluent System Flow (1)
Rate Measuring Device j
a Sa.T.pler Flow Rate Measurement 28 e.
Vent (1)
Sampler Flow Hate Measuring Device
- The following process streams rt re routed to the plant vent where they are effectively monitored by the instruments described:
y Lf1 FM (a)
Condenser Air Removal Sy::Lem C3 (b)
Auxiliary Building Ventilation System i
(c)
Fuel IIandling Building Ventilation System ci.
(d)
Radwaste Area Ventilation System (e)
Containment Purges t
4 TABLE 3.3-12 (Continued)
TABLE NOTATION
- 0uring rel eases via this pathway.
"Ourhg waste gas holdup system. operation (treatment fo primary system offgases).
ACT10tl 27 Wi th the number of channels OPERABLE 1ess than recuired by the Minimum Channel s OPERA 8LE requirement, the contents of the tank may be released to the enviror. ment for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided that crior to initiating the release:
1.
At least two independent samples of the tank's contents are analyzed, and 2.
At 12ast two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve 1ineup; Othenise, suspend release of radioactive effluents via thi s pathway.
ACT10H 28 With the number of channels OPERABLE less than recuired by the Minimum Channels OPERABLE requirement, effluent releases via this cathway may continue for up to 28 days provided the flow rata is estimated at least once per 4 houre.
ACTION 29 Wi th the number of channel s OPERABLE less than required by the Minimum Channel s ODERABLE requirement, effluent releases via this pathway man continue for up to 28 days provided either grat sa=ples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity within 2h hours or the containmeat plant vent noble gas monitor it placed in the plant vent nade for one hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period in which case grab samples need not be taken.
ACTIOM 30 (Deleted)
ACT10H 31 Wi th the number of channel s OPERA 8LE l ess than required by the Minimum Channe;s CPERABLE recuirement, operation of the waste gas holdup system may centinue for up to 28 days provided orab samples are collected a within ensuing 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
'ast once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed ACTION 32 With the number of channels OPERABLE one less than required by the Minimus Channels OPERA 3LE requirement, immediately sample each receiving tank in
'ervice once a day.
Any tank out of service will be service.
sampled betare being placed in 15 2 0- +1 ~/
SALEM-MET 1
TABLE 3.3-12 (Continued)
TABLE NOTATI0f1 ACTIC!l 33 With the number of channels CPERABLE less than required by the Minimum Channels OPERABLE recuirement, effluent releases via this pathway may continue for up to 28 days, provided sainples are continuously collected wi th auxiliary sampling equipment for periods on the order of seven (7) days and analyzed withia 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the end of sample collection weather per=ittir.,~.
Salem - Unit 1 8
8-58 15 0
TABLE 4.3-8 RADI0 ACTIVE GASEOUS EffLUEllT HorilTORIllG IllSTituf1ErlTAT10tl SURVEILLAllCE REQUIREHEllTS p
CllAtiNEL CilAfitlEL SOURCE CilAtitlEL FullCT10flAL INSTROMEtiT Cl!ECK CilECK CAllultATiott TEST 1.
Waste Gas Holdup System
- a. Waste Gas Release Monitor D*
P R(3)
Q(1)
U 2.
Waste Gas lloidup System comburitible t'
Gas Honitoring System R
d.
Oxygen Honitor D**
ti/A Q(5)
H I
N CD M
w
TABLE 4.3.8 (Continued)
RADI0 ACTIVE GASEOUS EFFLUEllT l;0tilTORIllG INSTRUMEllTAT10tl SURVEILLANCE REQUIR Ee CllAf!tlEL SOURCE CHAtitlEL CilANNElr Fut:CTIONAL I
INSTRUMEllT CliECK CilECK _
CALIGRATI0tl TEST C
_3.
Plant Vent //
I Noble Gas Activity thnitor D*
N.A.
R(3)
Q(2) p e
a.
b.
Vent W 5 N.A.
N.A.
N.A.
Iodine Gampler C ar tride,c c.
Vent Particulate Sampler W*
N.A.
N.A.
N.A.
Filter s'
d.
Effluent System Flow Rate Measuring Device D 8 N.A.
N.A.
N.A.
T e.
Vent Sampler Flow Rate W
- N.A.
R.
Q Measuring Device
- The following process streams are routed to the plant vent where they are effectively monitored by the instruments described:
e (a)
Condenser Air Removal Syste'm (b)
Auxiliary Building Ventilation System I
llandling building Ventilation System (c)
Fuel e (d)
Radwaste Aren Ventilation System
._n tu (e)
Containment Purges a
ru
~
C
TABLE 4.3-8 (Continued)
TABLE NOTATION i
'During rel eases via thi s pa thway.
t "During waste gas holdup system' operation ( trett:ent for primary system I
o f fgase s).
(1)
The CHANNEL FUNCTIONAL TEST shall also dmnstrate that aut matic isolation of this pa thway and control roco al 2m annunciatice occurs if any of the follcwing conditions exist:
1.
Instrument indicates measured levels abcve the alarc/ trip setpoint.
2.
Loss of Power (3)
The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS, otherwise standards used will be obtained from reputable suppliers.
These standards should permit calibrating the system over its normal range of energy and rate capabilities.
For subsequent CHANNEL CALIBRATION, sources that have been realted to the initial calibration should be used, at intervals of at least once per eighteen months.
This can normally be accomplished during, refua. ling outgages.
(Existing plants may substitute previously established calibration procedures for this requirement).
Salem - Cnit 1 3/4 3-62 1520 121
T.LI 4. 3-8 (Continued)
(5 )
The CHANNEL CALIBRATION shall include the use of standard gas samples containing a noninal:
1 Two percent oxygen Salem - Unit 1 3/4 3-63 1520 122
!!3 /a.11
- 23. : :4CT:'.'E E.re'rEN s il Il 13/4.11.1 L:CUID EF:LUE':!5 l
!CG51CENTRATIO!:
LIMITING CC?DITICt: FOR OPERA 7!Ci J3.11.1.1 The concentration of radicactive material released at anytime from the site to unrestricted areas (see Figure 3.!1-1) shall be limited
' to the concentrations specifiec in 10 CFR Part 20, Appsndix B, Table II, Column 2 for radienuclides other than dissolved or entra:ned noble gases.
i I
For dissolved or entrained noble gases, the concer.tration shall be limitec l
to 3 x 10-3 uCf /mi total activity.
I APPLICABILITY: At all times.
ACTION:
With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, immediately restore con-ceatration within the above limits and provide pecmpt notification to the Ccmmission ' pursuant to Specification 6.9.1.12.
I,
!! SURVEILLANCE REOUIREMENTS 4.11.1.1.1 The concentration of radioactive material at any time in liquid effluents released from the site shall be continuously monitored in accordance with Table 3.3-11.
4.11.1.1.2 The liquid effluent contin.uous monitors having provisions for automatic termination of liquid releases, as listed in Table 3.3-11, shall be used to limit the concentration of radioactive material releaseo at any time from the site to unrestricted areas to the values given in Speci-fi c a tion.3.11.1.1.
4.11.1.1.3 The radioactivity content of each batch of radioactive liquid waste to be discharged shall be determined prior to release by sampling and analysis in accordance with Table 4.11-1.
The resul ts o' pre-rel ease analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is limited to the values in Specification 3.11.1.1.
Salem - Unit 1 3/4 11-1 Il 1520 123
l' S'.':VII'_L '!CE EE J:RE"E!!TS (C cntinuedi
,4.11.1.1.5 The radicactivity concentration of licuids disjharge: feca
- contieucus release points shall be determined by collection and a alysis
!cf sampl es in acccedance wi tn Ta:Is 4.11-1.
Th,e resuits of One alyses P shall D' e used aith the calculational methocs in the CDCt1 to assure that
!;the concentrations at the point of release are limited to the values in
- Speci fication 3.11.1.1.
"4.11.1.1.6 "socc s.
The semiarruci Radicactive.Ef fluent Aeleasa s port e
- shall include tne information speci fied in Specification 6.9.1.9.
I i
B af l
e Sales - Unit 1 3 4 11-2 Ib20 124
TABLE 4.11-1 EADIGACT '!E..':'JID 14ASTE SAMPLI.' G A:;0 ANALYSIS 7.c.C27.A" l L:wer imi-I Sampling Minimum Type of Activi y of Detecticr Ly.-culc ne. tease type rrecuency analysis Analysis (LLui m.
Frequency (uCi/=l}3 P
P A. Satch '.!aste P.e-Each 3atch Each Satch Principal Ga.:::a 5 x 10-'
- _s lease Tanks 8 9
Emitters '
I-131 1 x 10-C P
Cne Eatch/M M
Dissolved and 1 x 10-:-
Entrained Gases
.i l
0 c
H-3 1 x 10 -
,Eac. Eatch a
Cc=:csiteC Gross a 1 x 10-7 Each atch Q
Sr-29, Sr-90 5 x 10-0 Cc=positec B. Stea.m Gener.
d Weekly W
Principal Ga= a b
Blowdown Cc= posited Emitters 9 5 x 10-7 I-131 1 x 10-6 M
Grab M
Dissolved and sa ole Entrained Gases 1 x 10-5 3
H-3 1 x 10 Composite Ccepasited
,7 Q
Sr-as, Sr-90 5 x 10-8 Ccepcsited Compo n.te IDl0 12a r-Salem - Unit 1 3f4.g
TABLE 1.11-1 (Continveci
~
TABLE HGTATICM a.
The icwer limit of detection (LLD) is defined in Table Notation a. of Table 4.12-1 of Specification 4.12.1.1.
b.
For certain radionuclides with lcw gamma yield or icw anercies, or for certain radionuclide mixtures, i t may not be possible to measure radio-nuclides in concentrations near the LLD. Under these circumstances, the LLD may be increased inver the gamma yield (i.e., 5 x 10 ;aly proportionally to the magni:ede of
/I, where I is the pnoton abundance expressed as a decimal fraction), but in no esse snall the LLO, as calculated in this manner for a specific racionuclide, be greater than 10% of the MPC value specified in 10 C. R 20, Appendix S, Table II, Column 2, A c mposite sample is one in which the quantity of licuic sam. led is c.
prcportioril to the quantity of liquid waste discharged and in which the methoa of sampling employed resul ts in a specimen whidh i t recre-sentative of the liquids released.
To be representative of the cuantities and concentrations of radic-c.
active materials in liquid effluents, samples snall be collectec in proportion to the rate of flow of the effluent strea:n.
prior to analyses, all samples taken for the ccaposite shall be thoroughly mixed in order for the composite sampie to be recresenta-tive of the effluent release.
A batch release is the discharge of licuid wastes of a discrete e.
volume.
g.
The principal gar:ma emitters for which the LLD specification will
. apply are exclustyely the folicwing radionuclides: Mn-54, Fe-59, Co-Sa, Co-60, 2n-63, Mo-99, Cs-13t. Cs-137, Ce-lal, and Ce-134 This list dces not mean that only knese nuclides are to be detected and reported. Other peaks which are measurable and identi ficble, together with the above nuclices, shall also be identified and repor ed. Nuclides which are belcw the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in LLD's higher than required, the reasons shall be dccumented in the semiannual Radioactive Effluent Release Report.
Salem - Unit 1 1520 126
RADI0 ACTIVE EFFLUE!!TS T,1 quid Effluent:
99.lk.
_LIMITIllG C0!!OITICH FOR OPE?.ATI0fi o3.11.1.2 The dose or dose ccmmitment to an individual
! materials in liquid effluents released to unrestricted areas from I
frcm radioactive each unit shall be limitec:
yl a.
and to j 5 mrem to any organ, andDuring any calendar oy
, i b.
During any calendar ye
,\\ -
110 mrem to any organ.ar to j 3 mrz to the total body and to
{ APPLICABILITY:At all times.
ACTIOM:
With the calculated dose frcm the relet se of r a.
active materials tion 6.9.2, a Special Report which identifies the c
, prepare anc ceeding the limit (s) and defines the corrective actions to be ause( s) for ex-taken to reduce the releases of radioactive mate i l and during the subsecuent three calendar c r a s in licuid L
er average dose or dose ccmmitment to an individual fecm such r leases during these four calendar quarters is vi thi e
total body and 10 meen to any organ.
n 3 mrec to tr -
c drinking wa ter source, andalso include (1) the results of rad q
e b.
The provisions of Specifications 3.0.3 and 3 0 4 are applicable.
not
! SURVEILLANCE REGUIRE!ENTS
[a.11.1.2.1 Dose Calculations.
peffluents shall se determinec in accordance with the Offsite C plation Manual (OCCM) at least once per 31 days.
4.11.1.2.2 R ecerts.
1shall includt tne information specified in. Specification 6 91 Salem - Unit 1 3/4 ll-6 O
i n 0 i c; /
RADI0 ACTIVE EFFLUENTS LIOUID WASTE TREATMENT LIMITING CONDITION FOR OPERATICN
- 3. 11. 1. 3 The liquid radwaste treatment system shall be OPERABLE.
The j system shall be used to reduce'the radioactive materials in liquid wastes prior to their discharge when the projected dose due to i f cuid efflue.it releases to unr_.-tricted arest when e eraged over a calendar quarter would exceed 0.375 cre= to the
.al
+
cody or 1.25 ;re= to any organ, f??LICA3IIITL At all tises.
ACTICH:
With radioactive licuid waste being discharged wi thout trea*:: lent a.
and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a
[
Special Repor which includes the following information:
ii:j 1.
Identification of equipment or subsystems not OPERABLE and i
the reason for inoperability.
i l
2.
Action (s) taken to restore the inoperable ecuip: ent to t
OPERABLE status, i
3.
Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SUP.VEILLANCE REOUIRE!1EHTS 4.11.1.3.1 Doses due to liquid releases to unrestricted areas shall be calculated at least once per 7 days when releases cccur.
4.11.1.3.2 The liqui.d radwaste systen shall be demonstrated CPERABLE at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.
Sslem - Unit 1 3/4 11-7 1520 128.
RADICACTI'!1 I:FLUENTS 3/4.11.2 GAHOUS EFFLUENTS DOSE RATE
, LIMITING C0h21T10N FOR OPERATION
'3.11.2.1 The dose rate, u any time, in the unrestricted areas frcm the site shall be limited to the following values:due to radioacti
\\
The dose rate limit for noble gases shall be 1500 mrem /yr to a.
the total body and j 3000 mrem /yr to the skin, and b.
The dose rate limit for all radiciodines and for all radioactive materials in particulate form and radionuclides other than noble i
gases with half lives greater than 8 days shall be j 1500 mrem /yr l j;
to any organ.
,l: APPLICASILITY:
At all times.
.iACTIOH:
i 1".
' lith the dose rate (s) exceeding the above limits, immeciately decrease the release rate to ccmply with the limit (s) give in Specification 3.11.2.1
.and provide prompt notification to the Commission pursuant to Specifica-
' tion 6. 9.1.12.
It i.' SURVEILLANCE REOUIREMENTS l.
l ii ij 4.11. 2.1.1 The release rate, at any time, of nobic gases in gaseous
' effluents shall be controlled by the offsite dose rate as established
[
above in Specification 3.11.2.1.
h.11.o.l.2 The noble gas effluent continuous monitors having provie. ions for the automatic termination of gaseous releases from the gas decay tanks, as listed in Table 3 3-12, shall be used to limit offsite deses within the values established in Specification 3 11.2.1 when monitor setpoint values are ex-ceeded.
4.11.2.1 3 The release rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined by obtaining representative s uples and perforning analyses in accordance with the in Table 4.11-2.
sampling and analysis progra=, specified Salem - Unit 1 3/4 11-9 il
~20 12^/
[5;R'/EILLANCEREGUIREMENTS I
i 54.11.2.1.4 The dose rate in unrestricted areas, due to radioactive materi-als other than noble gases released in gasecus effluents, shall be determined to be within the required limits by using the resul ts of -he
! sampling and analysis program, specified in Taole 4.11-2, in perfor-ing
'the calculations of dose rate in unrestricted areas.
4.11. 2.1. 5 ' R ecorts The semiannual Radioactive Ef fluent Release Re: ort shall include the information specified in Specification 6.9.1.9.
I
]
, :I 3
I!
I!,,
i!
-iil I
i Salem - Unit 1 3/4 11-10 1520 130
TAfttE 4.11-2 RADIDACTIVE GASE0llS WASTE SAflPLitlG AtID AllAtVSIS PROGRAll 3
Sampiing al s
Type of
[cct L 0) g Gaseous Release Type frequency frequency Activity Analysis (uci/ml)a P.
P b
h j x jo-4 P
A.
Waste Gas Storage Each Tank Each Tank Principal 6anina Emitters Tank Grab Saniple 11-3 1 x 10-6 P
P b
c c
h I x 10-'I 0.
Containment Purge Each Purge Each Purge Principal Gangna Emitters I
Grab 1 x 10-6 11-3 Samnle h
ncipal Ganuna 4Mers I x 10 oEp e C.
Condenser Air when 11-3
) x 10-6 Removal Steaming us System the steam
)
genera-tors to
[
the main a
condenser U
D.
Plant Charcoal l-131 1 x 10-I2 Continuous 9 W
-10 Vent Sample
.I-133 1 x 10 Continuous 9 W
Pe r tict la te Principal Ganina Emitterd'
- ~ple (1-131,Others) 1 x l'0 Sai.
-y; t_n 9
l1 Gross alpha 1 x 10 N
Continuous c3 Composite Particulate Sample
-11 U
Continuous 9 Q
Sr-89, Sr-90 1 x 10 Composite Particulate Sample
TABLE a.11-2 (Continued)
TABLE HOTATION a.
The lower liimit of detection (LLD) i s de fined in Tabl e N'o ta tion a. o f Tabl e 4.12 ' of "peci fication 4.12.1.1.
b.
For certain adionuclides with low gamma yield or low energies, or for certain adionuclide mixtures, it may not be possible to measure radionuclice: in concentrations near the LLO.
Under these circum-stances, the LLD.nay be increased inversely, proportionally to the magnitude of the gamma yield (i.e.,1 x 10-'/I, where I is the photon I
abundance ex ressed as a decimal fraction), but in no case shall the LLD, as cale; lated in this manner for a specific radionuclide, be I
greater thar 10% of the MPC value specified in 10 CFR 20, Appendix B, l
Tabl e II, C. umn 1.
l Analyses shall also be performed following shutdown, startup, or c.
similar operational occurrence which could al ter the mixture of radionuclides.
The ratio of -he sampl e fi cw rate to the sampl ed stream flow ri te g.
shall be knowt for the time period covered by each dose or dose rate calculadon made in accordance wi th Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
h.
The principal gamma enitters for which the LLD specification will apply are exc'usively the following radionuclides:
Xr-88, Xe-133, Xe-13'n, Xe-135 a
for gaseous emissions and Mn-54, Fe-59, Co-58. Co-60, 2n-65, Mo-99, Cs-134 Cs-137, Ce-141 and Ce-144 for particulam emissions. This list does not mean that only these nuclides are :D be detected and reported. Other peaks which are measurable am identifiable, together with the above nuclides, shall al so be ident fied and reported. Nuclides which are below the LLD for the analy.es should not be reported as being present at the LLD level-for tha: nuclide.
When unusual circumstances resul t in LLO's higher than nouired, the reasons shall be documented in the semi-annual eff se report.
3/4 11-12 Salem - Unit 1 15;20 132
RADICACT!iEEFFLUENTS DOSE, HOBLE GASES LIMITING C0!40!TICH FOR OPERATION 3.11.2.2 The air dose in unrestricted areas due to noble gases released in gaseous effluents shall be limited to the following:
Curing any calendar quarter, to j 5 mrad for gamma radiation a.
i and j,10 mrad for Deta radiation; b.
During any calendar year, to j 20 mrad for beta radiation;j 10 mrad for gamma radiation and I
l
'I
- i
'jAPPLICABILITY: At all times.
ACTION:
i i
With the calculated air dose from radioactive noble gases in i
a.
gaseous effluents exceeding any of the above limits, prepare j
+
and submit to the Ccmmission wi thin 30 days, pursuant to Speci-fication 6.9.2, a Special Report which identi fies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose during these four calendar quarters is within l
(10) mrad for gamma radiation and (20) mrad for beta radiation.
I b.
The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e.
SURVEILLANCE REOUIREMENTS 4.11.2.2.1 Dose Calculations Cumulative dose contributions for the i
total time period shall De detencined in accordance with the Offsite Dose Calcul ation Manual (00C!1) at least once every 31 days.
t 4.11.2.2.2 Recorts The semiannual Radioactive Effluent Release Report shall include tne information specified in Specification 6.9.1.9.
Salem - Unit 1 3/4 11-13 1520 133
RADICACTIVE EFFLUENTS DOSE, RADIGICDIHES. RADIOACTIVE MATERI AL IN P ARTICULATE FORM, 'AND RA010t1UCLIDES OTHER THAN NOBLE GASES LIMITIMG CONDITIOM FOR OPERATION I
3.11.2.3 The dose to an individual frca radiciocines, radioactive I
materials in particulate fom, anc radionuclices cther than noble gases wi tn hal f-lives greater than 8 days in gaseous ef fiuents released tc unrestricted areas shall be limited to the following-i' a.
Caring any calendar quarter to j 7.5 mrem to any organ; b.
During any calendar year to j 15 mrem to any organ; and 4
' APPLICA3! LIT": At all times.
ACTICH:
i I
a.
With the calculated dose frcm the release of radinindines, l
radioactive materials in particulate fom, or radionuciides other than noble gases in gaseous effluer.ts exceeding any of the above limits, prepare and submit to the Ccemission with-l in 30 days, pursuant to Specification 6.9.2, a Speciai Report j
which identi fies the cause( s) for exceeding the limit and defines the corrective actions to be taken to reduce the i
j releases of radiciodines, radioactive materials in particu-late fom, and radionuclides other than ncble gases with hal f-I lives greater than 8 days in gaseous ef'luents during the renainder cf the current calendar cuarter and during the i
subsequent three calendar quarters so that the average dose or dose ccrnmit:::ent to an individual from such releases ducir.g these four calendar quarters is within (15) mrem to any organ.
I, t
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e.
SURVEILLANCE REQUIREMENTS 4.11.2.3.1 Dose Calculations Cumulative dose contributicns for the total i
time period snall be cetemir.ed in accordance with the 00CM at least once i
every 31 days.
i 4.11.2.3.2 Reoorts The semiannual Radioactive Ef fluent Release Recort shall include tne infomation specified in Specification 6.9.1.9.
Salem - Unit 1 3/# 11-14
~
1520 134
PA3: Cat';VE EFFi.UENTS
- GASECUS RACWASTE TREAT?'EHT LIMITING CCNDITION FOR OPERATION i
i3.11.I.L The gaseous radvaste treatment system and the ventil tion e..aust treatment radvaste treatment system shall be OPIRABLI.
The gaseous a-system shall be used to reduce materials in gaseous waste prior to their dischar.;e when the radioactive gaseous effluent air doses due unrestricted areas (see Figure to gaseous effluen: releases to would e.xceed 1.25 mrad for 5.1-1) over any calendar quarter gamma radiation and 2.5 = rad for beta radiation.
The ventilation exhaust their discharge when theused to reduce radioactive =aterials in gaseous treat =ent ystem shall be to unrestricted areas doses due to gaseous effluent o
calendar quarter exceeds 0.625 mrem to any organ.(see Figur releases APPLICAsILITY:
At all tine:.
,_ ACTION:
With gaseous waste being discharged for more than 31 da a.
to the Ccmmission within 30 days, pursuant to ys wi thout umt a Special Report which includes the following infor nation:
n 6. 9. 2,
.1.
the reason for inoperabili:y. Identification of equipme 2.
OPERABLE STATUS. Action (s) taken to restore the inoperable e l'
3.
Summary description of action (s) taken to prevent a re-currence.
b.
Tne provisions of Specification 3.0.3 and 3.0.4 are not
(
applicable-r
! SURVEILLANCE RE0VIREMENTS 4.11.2.4.1 Doses due to casacus releases ta calculated at least once per 31 days. unrestricted areas shall be
!: 4.11.2.4.2 once per 92 days unless the apprcoriate system ha
' radioactive gaseous effluents during the previous 92 days east 1
rocess I
Salem - Unit 1 i
3/4 11-15 l
1520 15 m.-
, arp re -.-
RADICACTivE EFFLUENTS DOSE LIMITING C0h0! TION FOR OPERAT Ct!
3.11.2.5 The dose or dose ccemitment to a real individual fecn all
' uranium fuel cycle sources is limited to 3 25 crem t y or period of 12 consecutive month:.
APPLICABILITY: At all times.
FACTION:
With the calculated dose frem the release of radioactive a.
materials in liquid or gaseous effluents exceeding twice the U
limi ts of Speci fications 3.11.1.2.a, 3.11.1.2.b 3.11.2.2.b, 3.11. 2.3.a, o r 3.11.2. 3.b, prepare a,nd submi t a 3.11.2.2.a b
Special Report to the Ccemission pu suant to Specification 6 9 2 and limit the subsecuent releases such that the-dose er ccmmitment to a real individual frcm all uranium fuel cycle ccsa sources is limited to < 25 mrem to the total bod 1
(except thyroid, Aich is 1imited to < 75 mrem) y or any orgar
)
tive months.
over 12 conse:u- !
demonstrates that radiation exposures to all real ind t,
j' from all uranium fuel cycle sources (including all effluent !
pathways and direct radiation) are less than the 40 CFR Part 190 Standard.
Commission to pemit releases whicn exceeds the 40 CFRO Part 190 Sta idard.
I b.
The previsions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREPENTS 4.11.2.5.1 Dose calculations and gaseous effluents snall be detem.ned in accordance with Spe v
ca ti ons 3.11.1. 2.a, 3.11.1. 2.b, 3.11. 2. 2. a, 3.11. 2. 2. b, 3.11. 2. 3. a l 3.11.2.3.b, and in accordance wi th the Of fsi te Cose Calculati
, and 1(00CM).
on ifanual 4.11.2.5.2 Recorts under Speci fication 3.11.2.5.a.Special Reports shall be suomitted as recuired l
Salem - Unit 1 3/4 11-16 1520 136
RADI0 ACTIVE EFFLUENTS COM3UST13;I gas Mix r r l
! LIMITING CCHOITION FCR OPERATICH ti ll3. ll.2. 6c The concentration of oxygen in the waste gas
'jholdup system shalI be 1icited to j 2% by volune.
l APPLICABILITY: At all times.
ACTION:
l a.
Witn the concentration of oxygen in the waste l
gas holdup system > 2% by volume but < 4% by volume, restore lj the concen+ ation of oxygen to witnin the limit 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
l:
b.
With the concentration or oxygen in the waste l
V gas holdup system > 4% by vclume, immediately suspend all coditions of waste ga:es to the system and reduce the concentra-l,;
tion of oxygen to j 2% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
The provisions of Specification 3.0.3 and 3.0.4 are not c.
l:
apolicable.
i.i, SURVEILLANCE RECU: REPENTS I;4.11.2.6.
The concentrations of oxygen in the waste igas holdup system shall be deter ained to be within the above limits
'by continuously monitoring the waste gases in the waste gas holdup system wi th the oxygen monitors requir% OPERABLE by Table 3.3-12 of Specification 3.3.3.9.
I l
l Salem - Unit 1 3/4 11-18 1520 1,/
3
- P.AJ'OACTIVE EFFLUENTS it
!IGASSTOD.AGETANKS I.LIf41 TING CONDITION FOR 00ERATION ln i
ili3.11.2.7 The quantity of radioactivi;y containec in each gas storage tank
!shall be limited to <S4/ecuries noale gases (considereo as Xe-133).
>! APPLICASILITY: At all times i:ACTICH:
i i n any gas storage With the quantity of radioactive material i
l a.
tank exceeding the aoove limit, immediately, suspend all yl additions of radioactive caterial to tree tank and wi thin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> either reduce the tank contents to within the limit ij it or provide prompt notification to the Cor. mission pursuant to si Speci fication 6.9.1.12.
The written followup repcrt shall include a description of activities planned and/or taken to reduce the tank contents to within the above limit.
l b.
The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e.
'Ei.:.VEILLANCE REOUIREMENTS ij4.11.2.7 The quantity of radioactive material contained in each gas
- storage tank shall be detemined to be within the above limit at least ionce per E when radioactive materials are being added t'; the
! tank.
Salem - Unit 1 3/4 11_19 520 130
'PA0!GACTIVf EFFLL'O:TS I
i3/4.11.3 SOLID,UDICACTIVE i:ASTE LI!*!T!?:G C0! 0!TICM FCR CPERATIC?:
~j3.11 3.1-The solid radvaste syotem shall be OPERABM and used to
,9, provide for the SOLIDIFICATI,0N,of licuid was te s, and to en'sure the meeting of the prior to shipmentrequirements of 10 CFR Part 0.0 and of 10 CFR Part 71 from the site.
I APPLICABILITY: At all times.
ACTIO!::
t' With the recuirements of 10 CFR Part 20, 10 CFR Part 71, and a.
the PRCCESS CONTROL PROGRAli of Specification 6.14 not satisfied, suspend shipments of defective containers of solid radioactive wastes from the site.
i j
b.
With the solid radwaste system not GPERABLE for more than 31 days, when required to meet 10 CFR Part 20 and 10 CFR Part 71, prepare and suomit to the Ccemission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following infonnation:
1.
Identification of equipment of subsystems not OPERASLE and the reasons for inoperacility.
2.
Action (s) taken to restore the inoperable equipment to OPERABLE status.
3.
A description of al ternative used for SOLICIFICATIO!: and packaging of wastes.
4.
Summary description of action (s) taken to prevent a re-currence.
The provisions of Specifications 3.0.3 and 3.0.4 are not c.
applicable.
SURVEILLANCE REQUIREFENTS 4.11.3.1.1 The solid radwaste system shall be demonstrated OPERABLE at least once per 92 days, or thare be '.he capability for SOLIO!FICATICH of waste by meeting one or more of the conditions below:
Salem - Unit 1 3/411.h 1520 139
It q su-'!E 'L L M b :E0:E EPEN 75 C:.--i-ac !
I ll By perfomance of functional a.
II ponents of the sclic rac as;e system.tasts of the ecuipmer.t anc ccm-
[
b.
By operatinc the solic racwas e system at least once in tn i
previous 92 days in accor:ance wi th the PROCESS CCNIROL e
C/. TION to be perfomed in ac:cedance wi t c.
![
PR OGRAM.
I:j!k.11 3.1.2 shall be used to verify the SOLIDIFICATION o" atThe Proc lj' repre s entati ve test specimen fro: at least least one of each type Ushsll of wet radioactive vaste.
every tenth batch y PROCESS CONTROL PROGRAM.be processed in acccrdAnce"with procedures The test steci= ens I
I If any test specimen fails to verify SOLIDIFICATIO?
a.
OIFICATION of the batch under test shall be sus:ence,d j
the SOLI-ternative SOLIDIFICATON parameters can be d un til
]
, al-test verifies SOLIOIFICATION.accordance with the PROCESS C n
l detemined by the PROCESS CONTROL PROGR rameters I
b.
verify SOLIDIFICATION,If the initial test specimen from a bat I
vide for the collection and testing of representative testthe i
specimens frcm each consecutive batch of the same type of I
wet waste until 3 consecutive initial test specimens d strata SOLIDIFICATION.
modified as required, as provided in Specification 613 toT emen-assure SOLIDIFICATION of subsequent batches of waste.
t 4.11.3.1.3 shall include tne folicwing infomation for each type of shipped offsite during the report period:
a.
container volure, b.
total curie quantity (determined by measurement or estimat )
e, 1,
$1 Sales - Unit 1 3/4 11-W t#
i OLq
.'!I.T.'II L'.WCE T E0'.'!?!"INTS (C er.ti nu ed )
principal radionuclices (determined by measurement or c.
estima te),
f, l
d.
ty:e cf waste (e;;., spent resin, cc9pacled dry wa 5:e evf.porator bottcns),
ty;e of container ( e.g., LSA, Type A, Type B, large e.
Ovanti ty), and f.
solidification agent i e.g., cement, urea femaldehyde).
i salem - Unit 1 3/4 11 22 II 15z^0 141 r
M 3/4.12 RADICi.C'i! CAL ENVIR0nt E!:ut tot!ITOR!!1G 3/4.12.1 MOMITORING PROGRAft
. LIMITING CONDITION FOR OPERATICH i3.12.1 The radiological enviremental MCnitoring program shall be con-aucted as specified in Taole 3.12-1.
,.'PLICABILITY: At all times.
ii ACTIOH:
i With the radiological enviromental monitoring program not being a.
concuc ed as specified in Table 3.12-1, prepare and submit to the C:rmission, in the Annual Radiological Operating Report, a description of the rassons for not conducting the program as requirec and the p ans 'or preventing a recurrence.
(Deviations are pemitted frcm the r* quired sampling schedule if specimens are uncbtainable due to h4:ard0us conditions, seasonal unavail-aoili y, or to mal function of automatic sampling ecuipment.
the latter, every effort snail be made to cenpleta corrective If acticn prior to the end of tne next sampling period.)
b.
L'ith the confirmed level of radioactivity in an envi mental sampling medium at ron-specified in Table 3.12-1 one or more. of the locations 6 9-2 when averaged over a,ny calendar quarter, prepareexce and submit sffected calendar quarter,to the Commission within 30 d of the end includes an evaluation of any release conditionsa S ecial Report which I
of Tcble 6.9-2 to be exceeded.onmental factors or other aspects
, envir-s This report is not re-result of plant effluents; quired ifthe measured level of radioac the condition shall be however, in such an event, the Radiological Environmental Operating Reportreported and describ c.
Wi th =111:
or fresh leafy vegetable from any of the samples unavailable sample locations required by Table prepare and submit to the to Specification 6.9.2, Commission within 30 days,3.12-1, stant pur-cause of the a Special Report which iden-tifies the The locations from which samples wereidentifies loca and samples.
be deleted from Table which the replacement 3.12-1 provided theunavailable may then locations from sa=ples were obtained are added to the environmental sonitoring program as replacement tions, if available, loca-d.
The provisions of Specifications applicable.
3.0 3 and 3.0.4 are not Salem - Unit 1 3/4 12-5'20 14<
l SURVEILLANCE REOUIREFEHTS 4.12.1.1 The radiological environmental monitorir] samples shall be collected pursuant to Table 3.12-1 frem tne Iccations shown on Figures 3.12-1 3.12-2 and shall be analyzed pursuant to the requirements of and
. Tables 3.12-1 and 4.12-1.
i F4.12.1.2 Recorts - The resul ts 'of analyses performed en the radio-I~ Annual Radiological Environnental Operating Report, pursuant to' jt Specification 6.9.1.6.
i i
d l'
b s
h.
e ii I-i i
I';.
[ saleun-Unit 1 3/4 12-2 II 16')O Idi
TASLE 3. 8 3*8 esvtse=acetst sacretea! eat =evr9stsc Pe ee*=
C ora n=*e se TTpt a ratavrt:T COLLECTICm acTnCO of awaLYlle a regyracy p e ". 0. e.t Stat?ee ret te*afrew tsp
.a g.
a:'.
- t 2001 3.9 ei ssw et v at tal 7 75 3 es ette A
e Orssa tete saatysts %
?
Centtavees low welw e air e err wees ty saepte eene e
118
$,8 el a et vent Seeple celleet ed sampler.
mee43r**
C ewesy ween alesq wLtn filtet 5
anaage Coopeeltlee Cases seen quarterly L
A 2F 3 8.? el 66C of vent T
S 8
- 3s3 188 si st of seattem lett 4.1 et saw ei vent 3.
A.etcoq 1801 3.9 et ffw of went (DI I O
fedine 3 33 emelytes ar e perf ereed O
A T!*.A lepregnated chareesl weeely I
flev.threegn eartridge is senaeeted to a&r parttee: ate u
S 1681 4.4 et hw # eene ett esepter and la collected weemly 3
8.7 mi twf of vest 388 ee site els3 tie at ut of vent
!!!. Drage?
1884 3.9 si sfw et eeat 1831 4.1 on uww of vent 2f3 8.7 di est of vent 13F5 middletown. Dels 9.4 elles w of vest 171 5.8 et 5 of vent Ceems dese-quarterly 2 desleeters will to telleeted from eeen leesties tweeterly e3gg gg.6 miles at of veas e3ng gg og ut et west 238 30.5 og out et vent est
.2 elles t$t of vest tot st ette. pereeaaea vete test s., as www. veet se
.a. desseete, eenseeted At.e. tsnia t. eu.a g..eteeir nos Cees ta, w.t.e intet, er in et ssw ee eat 3/4 12-3 salers - thits 1&2
}
.} O 4
?
9 D *D'T
' D bD D
taakt 3.12 1 (Cant'd.
Ottoa*te=at revia v.ewst e a c t et ec e nt e'wC eeMane COLLECT 10e ettu23 TYPE a rat 0VthCT ESPOSUAE pate se
- s.*ew Cact (Maatew g teer escy or amatygf5 17.
wa?re 11A1 Appreeirately 654 f t sw of vent U
- 1XI 21/2 et wsw of vent two gallen sectie to be celleeted Casma seen seataly n.l.
tel S sa.at end sr.se saagysee sentaly pre,tg;eg.,aten tesag e
eendin gene.;1ew serple celleetlea of quarterly seepeentes F
A C
3 711 8 el w of end Repse Cseets 4.5 en SE et veat tal C 3
45 1 en sits e
e
' 31 1 4.1 at NC el vent Two tellen gr ee sa.91e is tellected Cases seen e CC e=) analyseg W
ase deae meatney eentaly.
9 e
2r3 gre.)
Sales water ca.s le el a!!evet se taaea daily Crees hets eenthly Cease Ist D 8 el hat of vent and composited to a eental osan
- CC p.3 seatnly S A 89 and 53 90 analyses soepte of two galisas em quarterly eassestte W
I I
a G
T.
Twitl**SM fel C 11A1 Outf a!! areas $14' Sd of Two key serples of erst Canaaseen of eetble a
vent are seeled te. e plast 6e pertlea en collection beg er *ar and f resen A
8 sentanavally or waea 8
la season 12C1 meat. Baan etyetite Artifletal Island 2/1 2 el swl of vent (d) Fault 1 LC1 18.2 elles u of vent Saaples are celleetes ca dor tag the aereal ne rvest Radioledine detereinstion 7t ETAT:0N 21 1 4.45 et nut of vent sessen. seated La plastle, of treed leaf vegetetles and f reten if por tsnaale.
en telleet ten 2F1 3 at WWE of vent so f fielen t sample la gela leeted to yield 500 grees Ceana esse en eelleetlea of dry weigns and deae aanvally fd) S 711 1 at w of red perse Creets E
8.5 el SE of seer 8
- 1X1 21/2 et nsw of vent A esoste esaelstlag of Caese spectreeetry of eaen esople beatate ergentees and eestanavallys St 90 seetanneally assectated sedtoest le Laten en eedleeet a
E seelanawally a
T 11A1 Chattell stees 450' Sw of seat 71.
luctsfies Four gallea gret seeste of Caese seen en colleet tem 1 131, ISF1 5.2 et Inf of weet f resh allt is se11.eted saag, sage. en eetleet ten (a) a 2F 4 4.3 el set of went free eaen fare aesteenthly.
men ce=e are en pasturer f
L 5F1 8.9 et t of vent et least mentaly at einer elees E
1871 S.S el ww of vent
- )C 1 16.4 o t t e s ut o f went it) F 11A1 Outf all steer $10' Ed of Two key saastee of flan Caese eesa et editie port tee are sealed La plastle en colleettee I
went beg et }er and f semiana 11, er retee S
nea a
sirl 8/1 el =sw of. eat se se...a f
15ep20 14,o salers thits 152 3/4 12-4
D**D "D ~T)$'
e h S A[l}G ao TAaLE 3.33 1 scoated) ootsattomat t evr eewe e sta t aantetectent oor*ast=c es**oe=
tse**"*f COLLtCTtos atts00 T7ot e Fer0WreCT es*
t=
3*attoe ccet Locattow a recautect er amatvers 4 t %n *** e.
(e) C III St eelen oleinity east posetrate are solened Cease seen en etible A
side of esteery and frosen seatsaaee!!r portion only en sealeetlea N
g III
' west stee et esteery, 3 8 si f ra n sees III withis it el et Stettea Seef portion of sow le***
sospied and f rasen sentaan.elly Ett = loestion (seen at time of ee:.est esa
- a "kle serple.s act}eet to eselleellity of steeghtered eev
- cest ret st at sen e
hi m Units 152
.V4 12-5 1 5 m 0 l '/t 6 c
+
e
Y W
~
TABLE 4.12-1 HAXIHUM VALUES FOR T!!E LOWER LlHITS OF DETECTI0ti (Lt.0)^
s Water Airborne Particulate 0r G Fish Hlik Food Products Sediment Analysis (pCl/l) gpe gj,3)
(pCl/kg, wet)
(pC1/1)
(pC1/k,uet)
(pCi/kg. dry) 9 b
gross beta 4
I x 10~
3I h
2000 (l000 )
54 15 g3 130 59,
260 7
30 Sfl,60 15 Co 130 65 30 2n 260 952r-tib 15
- 131, I
? x 10-2 C
1 60 b
134,137 15(10 ), 18 1 x 10 Cs 140,,t, 15 3
15 N
t CD
+
N
Figure 3.12-1 ON SITE SAMPilNG LOCATIONS ARTIFICIAL ISLAND a
<~,
f l
l
\\
\\,,
l 2 4
$\\
l
,5 Y
/
<c %
i1 g l
'7 16 -r a
?'i maw 1ys l.;
7
~
3
'5(,
hl 14 '
(
\\YT
/
7
\\
- ss) j 6,' 3
, s i
o.4s2 s
4 N'
R(
(
12 6
s
\\
11 x
7
's 10 8
g l
N 4
N i
/
n i
Y u a:,n w,
?
I 1520 148 c.1.
fin 4 + 1
Figure 3.12-2 j
OFF SITE SAMPLING LOCATIONS I
D ARTIFICIAL ISLAND fk i
) PEN VI
- t. E'Q,
'M A N N I N;G'T,Op/
e
/_
f n
'"Y( /
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7, j :.
j
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p<'
on
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.y %
jy
+
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o ac t
sw.. \\[
J b
'U
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L 5iN BO R
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gi 4
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\\
V k
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\\ "Q {
\\
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a' V
p,,,.,...
' d,,
x%r 4
=, \\,
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LOW E R o
^
R'fE,J
% g_,;y),, \\ ;
A.
O Y$
V
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1
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~
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- y
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o
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~
1520 ley Salem - Unit 1
LU J
a
_ TABLE 4.12-1 (Centinued)
TABLE !!OTATIO!!
a The LLD is the smallest concentration df radioactive material in a sampie that wil1 be detacted with 955 probability with 55 probacility of falsely concluding that a blank cbservation represents a "real' signal.
For a ; articular measurement system (which may include radic-chemical separation):
LLO =
4.66 s b E. V
- 2. 2 2. f. ex p t -A.:.c l where LLD is the icwer limit of detection as defined accve (as pCi per unit mass or volume) is the standard deviation of the background ccunting rate s3 or of the counting rata of a blank sample as appropria a (as ccunts per minute)
E is the counting efficiency (as courts per transfomatien) l V is the sample size (in units of mass er c:!'ce) 2.22 is the number of transfomation per minute per pic: curie Y is the fractional radiochemical yield (when applicable)
Ais the radioactive decay constant for tne particular radionuclide A is the elacsed time se04een sample ecliection (or end of the sameld collection period) and time of counting The value of s used in the calculation of the LLD for a de sc-i 3
tion system shall be base 2 cn the actuai coserved varianca of the background counting rate or of the counting rate of the blank samples (as approp"iate) rather than on an unverified I
theoretically predicted <ariance. In calculating the LL3 for a radionuclide detemined by gamma-ray spectrcmetry, the back-j ground shall include the typical contributions of other radic-nuclides nomally present in the sampl es (e.g., po ta s,iun 20 in
,9 milk sampl es).
1520 1"
Salem - Unit 1 3 M 12-3
TABLE 4.121 (Continuec)
_ TABLE '!OTATICM i
j Analyses shall be performed in such a manner that the stated LL0s will be achieved.under routine concitions.
background fluctuations, unavoidacly small sampl eOccasionally si:es, the presence of intarferring nuclides, or other uncontrollable cir-
~..I cumstances may render these LL0s unachievable.
In such cases, Annual Radiolcgical Environmental Cperating Repo b
L'LO for drinking wa ter.
c LLD for leafy veget:bles.
I i
Salem - Unit 1 3/4 12 9 n
s RADIOLOGICAL E!!vtPCMPENTAL MCHITORIMG 3/4.12.2 LAND USE CENSUS LIMITING COHOITICH FCR CPERATICH 3.12.2 tion of the nearest milk animal, the nearest residence a e
I garden
- of greater than 500 square feet producing fresh leafy vegetaoles
{ in each of the 15 metacrological sectors within a vf :ence of five ciles.
APPLICABILITY: At all times.
ACTION:
With a land use cer. sus identifying a location (s) which yleids a.
a calculated cosa or dose cc:ait:ent greater than the values currently oeing calculated in Specification 4.11.2.3.1, pre-pare and tubmit co the Ccmmission within 30 days, pursuant to l
Specificatica 6.9.2, a Special Report which identifies the new I
location ( s).
b.
With a land use census identifying a location (s) which yi a calcula ted dose or dose commitment (via the same exposure elds pathway) gretter than at a location from which samples arc currently being obtained in accordance with Specification 3 12 1 prepare and subnit to the Specification 6.9.2, Consission within 3o days, pursuant to lo:ation.
a Special Report which identifies the new environmental nonitoring procram within 30 days,The new lo The sampling location having the lowest if possible.
via the calculated dose or dose conmitnant station may(be deleted from this monitoring program ber 31) of the year in which this land use census was conduct d-e.
The provisions of specifications c.
3.0 3 and'3 0.h are not appli-cable.
SURVEILLAMCE RECUIREFTNTS 1520 152 4.12.2.1 The land use census shall be conducted at least once cer 12 months betwean aerial survey, or of consul ting local agricui ture authorities.the 4.12.2.2 in the Annual Raciological Environmental Cperating Report
- sroac seat Salen direction sactor wi th the hichett n/n (avegetition samoling may be performed at the Un i t.
1 14--
i!?;DIOLCGIC L Et:VIR0!!!E?:TAL tC:ITC?.It:G 3 /a.12.3 It:7E?.LA30RATORY CC!' PAR!S0t! PROGRAM
,!L!!4!TitJG CC'0ITI0t: FOP GPERATIC!J I
+
3.12.3 Ana'.;'ses shall be cerfomed on radicactive c.aterials suppliec as part of an !n.erlaboracoratory Ccaparison Progrr: -hicn has been approved by flRC.
l AP.oL ICA3ILITY:At all tines.
ACTI0ti:
i 1
a.
With analyses not being perfomed as required above, report the corrective actions taken to prevent a recurrence to the
,j Cec-ission in tne Annual Radiological Environ = ental Operating j
Re;crt.
b.
The provisions of Specification 3.0.3 and 3.0.4 are not app'icaole.
L!,50RVEILLAt:CE ?ECUIREt'ENTS 4.12.3 The results of analyses perfomed as part of the above required Interlaboratory Cceparison Progra:n shall b4 included in the Annual Radio-logical Enviror. mental Opera ting Report pursuant to Saecification 6.9.1.6.
I L-1 i
i I
1 I
li Salem - Unit 1 1520 15,:
~
i l
INSTRUMENTATION BASES 3/4.3.3. 7 RADI0 ACTIVE LIOUID EFFLUEitT INSTRUME?:TATIO.'t l
The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm / trip
. setpoints for these instruments ' hall be calculated in accordanca with s
l NRC approved methods in the 00C:1 to ensure that the alarm / trip will
- occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY
'and use of this instrumentation is consistent with the requirecents of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.3. 7 RADIOACTIVE GASECUS EFFLUE.';T INSTRUMEFAtICN The radioactive gaseous effluent instrumentaticn is provided to
, monitor and control, as applicable, the releases of radioactive materials
'in ga;eous effluents during actual or potential release.s. The a! arm / trip
'setpoints for these instruments shall be calculated in accordance wi:h NRC approved methods in the CDC:4 to ensure that the alarm / trip will
. occur prior to exceeding the limits of 10 CFR, Part 20. This instrumen-tation also includes provisions for monitoring (and controlling) the lconcentrationsofpotentiallyexplosivegasmixturesinthewastegas holdup systen. The OPERABILITY ard use of this instr': mentation is con-sistent with the requirements of daneral Design Criteria 60, 63 and 64 ljofAppendixAto10CFRPart50.
i I
'I 3: : 34
- Salem - Unit 1 1520 154
3/ 11 RADI0 ACTIVE EFFLUENTS IBASES I
!3/4.11.1 LIUUID EFFLUENTS 3/4.11.1.1 C0hCENTRATIcn i-This specification is provided to ensure that the concentration of
. } radioactive materials released in liquid waste effluents frem the site to
' unrestricted areas will be less than the concentration levels scecified i in 10 CFR Part 20, Appendix 9, Table II.
This limitation provides addi-
'tional assurance that the levels of radioactive materials in bocies of
(,wa ter outside the site will not resul t in exposures wi thin (1) the Section II. A design objectives of Apoendix I,10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the popul ation.
,"Xe-135 is the contr 41ing radioisotope and its MPC in air (su was converted to an equivalent concentration in water using the methods described in International Ccemission on Radiological Protection (ICRP)
Publication 2.
3/4.11.1.2 00SE This specification is provided to implement the retuirements of Sec-ions II. A, III. A and IV. A of Appendix I,10 CFR Part 50.
The Limiting Condition for Operation implements the guides set forth in Section II. A of Appendix I.
The ACTION statenents provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix I' to assure that the releases of radioactive material in liquid effluents will ba kept "as icw as is reasonably achievable".
Also, for fresh water sites with drinking water j supplies which can be potentially affected by plant operationo chere is
- reasonable assurance that the operation of the facility will i. ; resul t i in radionuclide concentrations in the finished drinking water
- in excess of the requirements of 40 CFR 141.
tat are The dose calculat 'ons in the 00CM implement the requirements in Section III. A of Appendi>
I
. that conformance with the guides of Appendix ! is to be shown by s:1-culational procedures based on models and data such that the actual
' to be substantially underestimated... exposure of an individual through appropria The equatio,s specified in the 00CM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent. with the
', methodology provided in Regul atory Guide 1.109, "Calcul ation of Annual hof Evaluating Ccmpliance with 10 CFR Part 50, Appendix I," Revision, Doses to Man from Routine Releases of Reactor
.1, October 1977, and Regul a tory Guide 1.113, " Estimating Aoua tic Di s-persion of Effluents trom Accidental and Routine Reactor Releases for the surpose of Implementing Appendix I," April 1977.- NUREG-0133 provides meticds for dose calculations consistent with Regulatory Guides 1.109 ano 1.113.
B 3/4 11-1520 155 Salem - Unit 1
il:
- l O CACTIVE E
- FLUENTS
}
EASES l
IfeacnreacteratThis speci fication applies to the relcase df !!culd effluents fecm l
the site. Fcr units with shared radweste
- eatment systems, the liculd ef fluents fecm t'ie shared system are pecportioned gecong tne units snaring that system.
Il q3/a.11.1.3 LIOU., WASTE TREATMENT l
The CPERASILITY cf the liquid radweste -rea* ment system ensures that this system will ce avasiable for use wher.ever licuid affluents recuire treat ent price to re' ease to the environment. The requiremeets that tne apercpriate portions 3f this system be used wnen specified provides assur-anc3 that the release s of radicactive materials in IIquid ef fluents will be kept "as icw as is reasonably achievable." inis spec!fication imple-ments the require ent i of 10 CFR Part 50.35a, Ge.e si Oesign Cr!?erien 60 of Appendix A to 10 C: R = art 50 anc design cejectIve Sec*;cn iI.0 of Ap:endix A tc 10 CFR fart 50.
The specifled limits gcverning -he use of apercpriate scrtions af the liculd radwaste trea-en? system <ere spect-fled as a suitable fraction of the guide set fortn in Sectica ll.A of Appendix 1,10 CFR '-art 30, for !! quid ef fluents.
3/a.11.1. a l UID HCLOUP TANKS Restrleting the quantity of radicactive material centained 'n *he specified tanks provides assurance that the event of an uncentrollec release of the tanks' contents, the resulting concentrations -culd be less than the limits of 10 CFR Part 20, Appendix A, Table !!, Cciemn 2, at the nearest potable water supply and the nearest surf ace water
! supply In an unreetricted area.
l 3/a.1I.2 "ASECUS EFFLUENTS 3/4.11.2 1 00SE RATE This scecification is previcec to ansure that the dose rate at time at the exclusicn area beundary fron gasecus ef fluents fecm a:I units any-
.cn the site will be within the annual dose limits of to CFR Per-20 for unrestricted areas. The annual dose !!mits are the deses asscciated with the concentraticns of 10 CFR Part 20, Appendlx B, Taole iI.
These Iimits previde reascamb le assurance that radicactive a:ater t al discharged in gasecus ef fluents wil! not result in the exposure cf an Indivicual in an unrestricted crea, either within cr cutside the exclusion area Scundary, to annual average concentrations v.xceeding the limits specified in
' Appendix 8, Tab le 11 of 10 CFR Part 20 (10 CFR Part 20.106(b)).
For individuals who may at times be within the axclusien area beundary, the cccupancy of the Individual will be sufficiently icw to compensate for 1520 L56 Srlem - Unit 1 B-3/4 11-2
lRADICACTIVEEF:..!'q l
EASES an., increase in :ne atmospheric diffusion factor,above that for the ex-clusion area bouncary.
The specified release rate limits restrict, at j,all times, the corresponding gamma and beta dose rates above backgroun to an individual at or beyond the exclusion area boundary to j (SCO)
,mre:/ year to the total body or to j (3000) arem/ year to the sxin.
These j release rate limits al so restrict, at all times, the correspor.cing thyroic
!to $ 1500 mrem / year for the nearest cow to the plant.' dose rate This specification applfes to the release of gaseous effluents fren all reactors at the site.
For units with shared radwaste treatnent l among tne units sharing that system. systems, the gasecus effluents frcm th
!3/4.11.2.2 DOSE, NOBLE GASE3 This specification is provided to implement the retuirements of Sections II.S, I!!. A and IV. A of Appendix I,10 CFR Part 50.
The
{ Section 11.8 of A; cendix' Limiting Condition for Oceration implements the guide I.
The ACT10tl statements provide the recuired
- operating flexibility and at the same time implement the guides set i forth in Section IV.A of Aopendix I assure that the releases of radio-
, active material in gaseous effluents will be kept "as low as is reasonably jachievable."
The Surveillance Requirements implement the requirements in
'Section III. A of Appendix I that conforn with the guides of Appendix I
to be shown by. calculational procedures based on medels and data such that the actual exposure of an individual through the appropriate path-tways is unlikely to be suestantially underestimated.
The dose calcul a-ltions established in tne CCOM for calculating the doses due to the actual t re1aase rates of radioactive noble gases in gaseous effluents will be
! consistent with the metnodology provided in Regulatory Guide 1.109,
" Calculation of Annuai Ooses to f*.an from Routine Releases of Reactor
- Effluc..ts for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I," Revision 1, Cctober 19}7 and Regulatory Guide 1.111. " Methods
,for Estimating Atmospneric Transport and Dispersion of Gaseous Ef fluents in Routine Releases from Light-Wa ter-Cooled Reactors," Revision 1, July 1977.
The 00CM equations provided for determining the air doses at the
. exclusion area bcundary vill be based upon the historical average atmos-
{ pheric conditions.
titREG-0133 provides methods for dose ca.lculations
! consistent wi th Regul atory Guides 1.109 and 1.111.
i 13/4.11.2.3 00SE, RADIOI00!MES. RADI0 ACTIVE MATERIAL IN PARTICULATE FORM MNO RA010NUCL10ES OTHER THAt: NOBLE GASES
'his specification is previded to implement the requi.*ements of Sections II.C, III. A and IV. A o f Appendix I,10 CFR Part 50.
The Limiting Salem - Unit 1 8-3/4 11-3 1523
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RADICACT'VI EFFLUENTS lSASES i
I
': Conditions for Operation are the guides set forth in Ie: tion !!.C of l
The ACTION statements provide the recuired Operating flexi-lApcendix1.
> bility ano at the same time implement the guides set forta in Section "IV.A cf Actendix ! to assure that the releases of radioactive materials pin gaseous effluents will be kept "as low as is reascnably achievable."
pThe OCCM calculational methods specified in the surveillarce recuirements
- implement tne recuirements in Section III. A of Appendix ! that conform-
[ance with the guides of Appendix I be shown by calculational procedures
' basec cn models and data such that the actual exposure of an individual i
/ through ac;ropriate pathways is unlikely to be substantially under-The
' estimated.
the deses cue to the actual release rates of the subject materials it:are required to be consistent with the methodology provided in Regulatory
' Guide 1.109, " Calculating of Annual Doses to Man frem Routine Releases of Reactor Ef fluents for the Purpose of Evaluating Compliance with
- 10 CR Part 53, Ap endix I," Revision I, October 1977 and Regul atory
! Guide 1.111, ""ethods for Estimating Atmospheric Transport and Discersion E#fluents in Routine Releases from Light-Water-Cooled Reacters,"
dof Gasecu:
These equations also provide for determining
.! Revision i, July 1977.
!!the actual doses based upon the historical average atmospheric conditions.
,{The release rate s;ecifications for radiciodines, radioactive material
- f n particulate fc
- . and radionuclides other than noble gases are decendent ion the existing radionuclide pathways to man, in the unrestricted area.
- Tne pathways which are examined in the develoceent of these calculations
'are: 1) individual inhalation of airborne radionuclides, 2) deposition
- of radionuclides onto green leafy vegetation with subsecuent consumotion
- by man, 3) deposition onto grassy areas wilere milk animals and meat j producing animals gra
- e with consunption of the milk and meat by man, and 4) de:osition on the ground with subsequent exposure of man.
3 33 /4.ll.2.a GASEOUS WASTE TREATMEF
.t jThe OPERASILITY of the gaseous radwaste treatment system and the ventila-l tion exhaust treat.ent systems ensures that the systems will be available gfor use whenever gaseo'IIs effluents require treat.;cnt prior to relea the envircreant.
] systems be used when specified provides reasonable assuran
.i Thi s specification impl ements the
- low as is reasonably achievable."
' requirements of M CFR Part 50.36a, General Design Criterion 60 of Aopen-
' dix A to 10 CFR Part 50, and design objective Section II0 of Appendix I eto 10 CFR Part 50. The specified limits governing the use of appropriate
- portions of the syste-s were specified as a suitable fraction of the
.; guide set for ih in Sections II.B and II.C of Appendix I,10 CFR Part 50, i.for gasecus effluents.
3 3/4 11-4 g
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31 11.2.5 OOSE This seccification is provided to ceet the recorting requirements i of 40 CFR 190.
1 3/4.11.2.6 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration f of potentially explosive gas mixtures containea in the waste gas treat-iment system is naintained below the f1ammability 1imits of hydrogen j and oxygen. ( Autenatic control features are included in the system
! to prevent the hydrogen and oxygen concentrations frce reaching these
' fl ammabil i ty l imi ts.
These automatic control features include isolation lof the source of hydrcgen and/or oxygen, automatic diversion to re-l combiners, or injection of dilutants to reduce the cor::entration belcw i the fl ammabili ty limits.) Maintaining the contentratica of hydr:g n
'and oxygen below their fla cability limits prcvides assurance tnat i tne releases of radioactive materials will be controlled in conformance
!with the recuirments cf Gens al Design Criterion 60 of Appendix A lto 10 CFR Part 50.
- , 3 /.4.11.2.7 GAS STORAGE TAMKS Dj, Restricting the cuantity of radioactivity contained in each gas
- s*wrage tank provides assurance that in the event of an uncontrolled i release of the tanks contents, the resul ting total body exposure to
> an individual at the nearest exclusion area boundary will not excesc I 1.5 re. This is consistent with Standard Review P1an 15.7.1, "uste
- Cas System Failure."
3/4.11.3 SOLID RADIOACTIVE WASTE The OPERA 8!LITY of the solid radwaste system ensures that the system
'will be available for use whenever solid radwastes recuire processing and
' packaging prior to being shipped offsite. This specification implenents the requirements of 10 CFR Part 50.36a and General Design Criteria 60 of Appendix A to 10 CFR Part 50.
The process parameters used in estabi t sh-ing the PROCESS CCHTROL PROGRMt may include, but are not limited to waste type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing l tine s.
Salem - Unit 1 B 3/4 11-5 1520 159
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a I 3/2.12 RADIOLOGIC;_ I%IRONf'EHTAL 110h' ORING BA3ES 3/4.12.1 l'C':ITORI?:G pq0GRArt The radiologi;al canitoring program required by this specification
'provides ceastrements of radiation and of radioactive materiais in ithese exposure pathways and for those radionuclides which lead to the ihighest potential radiation expsures of individuals resulting from lthe station operation. This monitoring program thereby supplements the iradiological effluent monitoring program by verifying that the measur-table concentrations of radioactive materials and levels of radiation are
- not higher than expected on the basis of the effluent measurements and
- moceling of the environmental exposure pathways. The initially specified l monitoring program will be effective for at least the first three years
'of ccmmercial operation. Following this period, program changes may be
- initiated based on operational experience.
The detection cc:acilities required by Table 4.12.-l are state-o Hof-the-art for routine environmental measurenents in industrial labora-
- tories. The LLD's for drinking water meet the requirenents of 40 CFR 141.
i.3/4.12.2 LAND USE CEMSUS This specification is provided to ensure that
- cnanges in tne use of unrestricted areas are identified and that modifi-icaticns to the monitoring program are made if required by the resul ts of
.this census. This census satisfies the requirements of Section IV.E.3 of iAppendix I to 10 CFR Part 50. Restricting the census to gardens of greater
- than 500 square feet provides assurance that significant exposure pathways livia leafy vegetables will be identified and monitored since a garden of i; leafy vegetables assumed in Regulatory Guide 1 109 for consumptio j
jchild. To determine this minimum garden size, the following assunptions
.were used,1) that 20t of the garden was used for growing broad leaf ivegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.
3/4.12.3 INTERLABCRATONT COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison program is provided to ensure that independent checks on the precision ard accuracy of the measurements of radioactive material in env4ronnmental sample matrices are performed as part of a cuality assurance program for ervironmental monitoring in order to demonstrate that the resul ts are reasonably valid.
S 3/4 12-1 r^n Salem - Unit 1 l34U 1iGU
r AC:f!.';IFTRATIVE CC:rrROLS AUDIT 5 6.5.2.8 cogni:ance of the HRB. Audits of facility activities shall be perfomed under the These audits shall ence pass:
The conformance of facility operation to provisions contained a.
within the Technical Specifications and applicable license conditions at leact once per 12 i.cnths.
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b.
The performance, training and qualific tions of the entire facility staff at least once per 12 naths.
The results of actions taken to ec. ect deficiencies occurring c.
in facility equipment, tion that affect nuclear safety at leas. cace per 6 :sn:hsstructu d.
Assurance Program to meet the criteria cf A;;:e 50, at least cnce per 24 cenths, least cnce ;2r 24 months.The Facility 62rgency Plan and i=clem e.
at f.
The Facility Security Plan and implementing ;rececures at least cnce par 2: conths.
Any other trea of facility cceration censidared appre.riate by g,
the NRS or tne Vice Presicent-Freducticn.
h.
at least once per 24 m:nths.The Facility Fire Protection Pregra i.
An independent fire protecticn and loss :reventien pr:rm inspection and aucit shall be perfomec a: least once nr 12 anonths utili:ing either qualified offsite licensee perscnnel or an outside fire protection firm, j.
An inspection and audit of the fire protecticn and loss :reven-tion program shall be ;;erfor ad by a cualifisc outside fies consultant at least ence per 26 :onths, 1.
The radiological environmental monitoring program and the results thereof at least once per 24 months.
t The CFFEITE COSE CALCULAT!0:
m.
at least once per 24 months.1 iw:'. AL and impi enenting precedurcs The FROCESS C0!!MCL FR0 Call for the 50LIDITICA7!C:
n.
1 o f r.tiiNc tive wastes frca liquid systems at least once cer :'4 months AUTHORITY 6.5.2.9 Production on those areas of responsibility specified 1520 161 6.5.2,7 and 6.5.2.8.
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- 6. 7 SAPETY LIMIT VICLATICN 6.7.1 The following actions shall ta taken in the eveni a Safety Limit is violated:
a.
The unit shall be placed in at least HOT STANCBY within one
- hour, b.
The Safety Limit violation shall be reported t: the Cc =ission, the General Manacer-Electric Production and to the NRS within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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c.
A Safety Limit Violation Re ort shall be :re:ared.
The accet shall be reviewed by the SCRC. This rescrt :nall describe 01 applicable circumstances prececing the viciatien, (2) effects of the violation upcn facility ccm:.cnan s, systams er structures, and (.31 corrective action taken :: prevent recurrence.
d.
The Safety Limit Violation Re:cr: shall be submittad to the Cc.=tission, the NRS and tae General Manager-Electric Precuttien within 14 days of the violation.
6.8 PROCEDURES i 5. 3.1 'dritten procedures shall be established, implementad and main-
- .ined covering the activities referenced belcw:
a.
The applicable procedures rec:c ended in Accendix "A" of Regulatory Guide 1.33, Revisien 2, Febraar/ 19~1.
b.
Refueling operations.
- c..
Surieillance and test activities of safety related equipment.
d.
Security Plan implementation, e.
Emergency Plan implementation, f.
Fire Pr tection Program imolementatien.
C Offsite releases of gaseous and ifquid effluents c:ntaining radioactive materials.
h The PRCCESS CONTROL PROGRhi for solidification of radioactive waste.
6.3.2 Each procedure and administrative policy of 6.8.1 above, and enanges thereto, snall be reviewed by the 50RC and approved by the 5:ation f*anager prior to implementation and reviewed periodically as set forth in administrative procedures.
1520 ic>-z Salem - Unit 1 6-12 JAN p 979
ACHINISTRATIVE CONTROLS 1I ANNUAL RADIOLOGICAL ENVIRCNMENTAL OPERATING REPORT 6.9.11o Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submittad prior to May 1 of the year following initial criticality.
6.9.1.11The annual radiological environmental operating reports shall include surnaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities fo-the report period, including a comoarison with preoperational studies, operational controls (as appropriate), and previous environmental surveil-lance reports and an assassment of the observed imcacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
The annual radiological environmental operating recorts shall include sur:narized and tabulated results in the femat of Table 6.9-1 of all radiological environmental samples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
The reports shall also include'the following: a sunmary description of the radiological environmental monitoring program including sampling methods for each samole type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equip-ment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; the results of land use censuses required by the Specification 3.12.2; and the results of licensee participation in the Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program recuired by Specification 3.12.3.
E SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REFORT 6.9.112 Routine radioactive effluent release reports covering the 6 months of operation shall be operation of the unit during the previou c
submitted within 90 days after January and July 1 of each year. The period of the first report shall begin with the data of initial criticality.
3/
A single sucmittal may be made for a multiple unit station. The submittal should combine those sections that are connon to all
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units at the station; however, for units with separate radwaste systems, the submittal s' hall specify the releases of radioactive material from each unit.
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'. 9.1.13 The radioactive ef fluent releos : reports shall include a summary c f the quantities of radioactive liquid and <;ascous ef fluent-and solid waste released from the unit as outlincd in Regulatory Guic 1.21,
" Measuring, Evaluating, and Reporting Radio.ctivi ty in Solid i istes and Releases of Radioactiva Ma terials in Lir,ain cnd Gascous Ef fluents from Light-Water-Cooled fluclw Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.
The radioactive ef fluent release reports shall include a su mary of the n.eteorological conditions concurrent with the release of gaseous effl uents during each quarter as outlined in Regulatory Guide 1.21, with data summarized on a quarterly basis following the femat of Appendix B thereof.
The radioactive effluent release reports shi,ll include an assessment of the radiation doses from radioactise effluents to individuals due to their activities inside the unrestricted area boundary (Figure 5.1-1) dQring the report period. All assumptions used in making these assesc1 ents (e.a.,
specific activity, exposure time and location) shall be included in these r ept, rt s.
Tbc radioactive effluent release reports shall include the follcaing i:Jomation for all unplanned releases to unrestricted areas of racio-active materials in gaseous and liquid effluents:
a.
A description of the event and ecuipment involved.
b.
Cause(s) for the unp1anned release.
c.
Actions taken to prevent recurrence.
d.
Consequences of the unplanned release.
The radioactive effluent release reports shall include an' assessment of radiation doses from the radioactive liquid and gaseous effluents released frcm the unit during each calendar quarter as outlined in Regul atory Guide 1.21.
In addition, the t.:. restricted area boundary maxinun noble gas gamma air and beta air doses shall be evaluated. The meteorological conditions concurrent with the releases of effluents shall be used for determining the gaseous pathway doses. The assess.nent of radiation doses shall be perfomed in accordance wi th the Of fsite Dose Calculation Manual (00CM).
The radioactive effluent release reports shall include an-changes to the Offsite Dose Calculation Manual (CDCM) made during the reporting period, as provided in Specification.
6.14 6-16 Salem - Unit 1 1520 105
I ACMINISTRATIVE CONTROLS I
MONTHLY OPERATING REPORT 6.9.16 Routine reports of ocerating statistics and shutdewn ex;erience shall te submitted en a monthly basis. to the Directar, Office of Management Information and Program Analysis, U.S. Nuclear Regulatory Commise cn, Washington, D.C.
20555, with a c:r/ to the Regicnal Office of O'1E, no later than the 15th of each ment., following the calendar month c:vered by the report.
RCPORTABLE OCC'JRRENCES 6.3.1. 7. The RE:0RTAELE GCCURRENCE5 of Specifications 6.9.1.8 and 5.9.1.9 below, including corrective actions and measures to prevent recurrence, shall be re;orted to the NRC.
Supclemental reports may be required to fully describe final rescitt icn of cccurrence.
In case of c:rrected or supolemental rescrt:, a licenses event rsport shall be c:mpleted and reference shall be made to the original report da a.
PROMPT NOTIFICATION WITH WRITTEN FOLLCVUP 6.9.1. 8. The types of events listed belcw shall be reported within 2a hours by telephone and confir:ed by telegracn, mailgram, or facsmile transmission to the Director of the Regional Office, or his desicnate no later than the first working day following the event, with a Eritten followuo recort within 14 days.
The written folicwuo report shall include, as a minimum, a completed copy of a licensee event report form.
Information provided en the licensee event reper fem shall be supple-mented, as needed, by additional narrative material to provide comalete explanation of the circumstances surrounding the event.
a.
Failure of the reacter protection sys:aa or other systems subject to limiting safety system settings to initiate the required protective function by the time a =cnitored para-meter reaches the setpoint s ecified as the limiting safe y system setting in the technical specificatiens or failure to c mplete the required protective function.
b.
Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for coeration is less conservative than the least conservative aspect of the limiting condition for operation establisned in the technical scecifications.
Abncmal degradation discovered in fuel cladding, reacter c.
coolant pressure boundary, or primary centainment.
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Reactivity an:malies involving disagreement with the predicted value of reactivity balance under s:aady state candition:
during pwar operation grea er thcn or equal to l'; ak/k; a calculated recc:ivity balance indicating a SHUTCC'.G MARGIti less conscevani 2 than specified in the technical specifica-tions; shcr:-term mactivity incenses that corresp:nd to a reac:cr period of less thca 5 sec:nds cc, if subcritical, an uncianned reactivity insertien of ecre than 0.5" ak/k; or cccurrence of any unplannec criticality.
e.
railure or malfunction of one or mere ccm:enen s which prevents or could prevent, by itself, the fulfillment cf the func:icnal requirements of system (s) used to cope with accidents analy:2d in the SAR.
f.
Personnel error or precedural inadequacy which prevents or c:uld prevent, by itself, the fu~.filmen: of -he func:icnal recuire-ments of systams required to c:pe with accidents analy:ed in the DR.
g.
Ccnditions arising fr:c natural or man-made events that, as a direct result of the event recuire uni: shutd:wn, c;eratien of safety sys: ms, or c ntr rotic.ive.aasures raquir2d by technical pecificaticns.
h.
Errors discovered in the transien: or ac:ident analyses er in the meth:ds usec for such analyse: as cescribed in the safety analysis re;cr: or in the basas for the tecnnical specific: icns that have er c:uld have :2mittec react:r c:aratien in a ranr.er less censarvative than assu ed in :he analyses.
i.
Per'omance of structures, systems, or ccm:enents that recuires remedial action or c:rrec:ive measures :: preven c:eraticn in a manner less c:nserva::ve :han :ssumed in ::a ac:1 dan:
analyses in the safe y analysis re ce: cr technical s:ecifica-tions bases; or d.scovery curing uit life of c:ncitions no:
specifically c:nsidered in the safety. analysis raper ce technical s:ecifications tha: recuire remecial ac-icn or c:r-rective reasures to preven: the existance ce davelopment of an unsafe conc 1:icn.
k.
Occurrence of radicactive caterial centained in liquid er casecus heldup tanks in exccss of tha: : emitted by the limiting c:ndi-tien for operation estr'iished in the technical specificaticns.
THIRTY CAY 'iRIT D RE:CRT3 6.9.1.9 The types of events listed balcw snall be the subject of writtan reports :s the Director of the Regicnal Office within :nirty days cf 1""
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T 10**D *D'S N we, e
m AC'II.!IITr *T'VE CONTECL5 cecurrence of the event.
The writ:29 ree:,r shall include, as a minimum, a c: mole:sc copy cf a licensee ever recer-fccm.
Infomation provided on the l'::.nsee event rt::rt form snali ba Iu::alemented, as needed, by additicn.i
.crative m..; rial to provice c:m;1ete explanation of the circumste :ss surrounding the event.
Reactor protecticn systam or engincered safety feature instru-a.
m2nt settings..nich are f:.nd be less conservative than tn:se establist.2d by the technical specificatiens but which do not prevent the fulfillment of - 2 functicnal requirements of affected systams, b.
C:nditiens leading to cperation in a degraded mode pemitted by i: '.imiting c:r.dition for c:: era-icn or plant shutdown re-quired by a li... ting conditicn f:r c:eration.
c.
Obsdeved ir.acs-.acies in the im:1. +n ation of ad=inistrative or procecurai ::ntrols which tars an :: cause reduction of degree of recun:ancy pr0 Viced in sac::P protection systems or engineerec safe y feature sys ams.
d.
Abncreal degraca-icn of systars : ner than these specified in 6.9 l.3.c a:cve cesigned :: c:n sin radioactive material resulting f: a :ne fission process, An unplanned offsite release of 1) more than 1 curie of e.
radicactive :: rial in liquid efflu:nts, 2) more than 150 curies of :ble gas in case:us ef'luents, or 3) moreThe than 0.05 curies of radiciocine in gasecus effluents.
recert of an unplanned offsite release Of radioactive 1
material shall include the foll: wing information:
1.
A description of the even: and equipment involved.
l 2.
Cause(s) f:r the unplanned release.
f 3.
Actions taken to prevent re:urrence.
4 Consecucnces of the unplannad release.
Salem - Unit 1 6-19 1520 108
e AC" B.3TRATIVE CONTROLS Measured levels of radioactivity in an environnental sampilng f.
medium determined to exceed the reporting level values of Taole 6.9-2 when averaged over any calendar quarter sanpling When more than one of the radionuclides in Table 6.9-2 period.
are detected in the sampling medium, this report shall be submitted if:
concentration (11,
concentratjen (2)- + * * * * > 1. 0 limit level (1) limit level (2)
When radionuclides other than those in Table 6.9-2 are dete and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is ecual to or greater than the calendar year limits of Specifica-This report is not tions 3.11.1. 2, 3.11. 2.2 and 3.11. 2.3.
required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
l Salem Unit 1 6-22 1520 1c9
N e
TABLE 6.9-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 3
Reporting Levels c'
S Airborne Particulate Fish Hilk Vegetables
<+
Analysis Water or Gases (pC1/m )
(pC1/Kg, wet)
(pCl/1)
(pCl/Kg, wet) 3 e
4 11-3 3 x 10 3
Hn-54 1 x 10 4
3 x 10 2
Fe-59 4 x 10 4
1 x 10 Co-58 1 x 10 4
3 x 10 2
?
Co-60 3 x 10 4
1 x 10 2
Zn-65 3 x 10 4
2 x 10 2
Zr-Nb-95 4 x 10 1-131 2
0.9 2
3 1 x 10 Cs-134 30 10 1 x 10 60 1 x 10 3
3 Cs-137 50 20 2 x 10 70 2 x 10 3
3
}
Ba-La-140,
2 x 10 2
2 o
3 x 10 C
\\N
.s ADMINISTRATIVE CONTROLS 6.1h PROCESS CONTROL PROGRAM (PCP) 6.14.1 The PCP shall be approved by the Commission prior to implamentation.
6.14.2 Licensee initiated changes to the PCP:
1.
Shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change (s) was made.
This submittal shall contain:
a.
sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; b.
a determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.
documentation of the fact that the change has been reviewed and found acceptable by the SORC.
2.
Shall become effective upon review and acceptance by the SORC.
t 6.15 0FFSITE DOSE. CALCULATION MANUAL (0DCM)
I' 6.15.1 The ODCM shall be approved by the Commission prior to implementation.
6.15.2 Licensee initiated changes to the 0001:
1.
Shall be submitted to the Commission in the Monthly Operating Report within 90 days of the date d.2 change (s) was made effective.
This submittal shall contain:
a.
sufficiently detailed information to totally support the.ationale for.the change without benefit of additional or supplemental information.
Information submitted should consist of a package of those pages of the 00CM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
b.
a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.
documentation of the fact that the change has been reviewed and found acceptable by the SORC.
2.
Shall become ef fective upon review and acceptance by the SORC.
i90 171 S,.1-.~"" "
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