ML20006C205
| ML20006C205 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 01/26/1990 |
| From: | ILLINOIS POWER CO. |
| To: | |
| Shared Package | |
| ML20006C199 | List: |
| References | |
| GL-89-01, GL-89-1, NUDOCS 9002070098 | |
| Download: ML20006C205 (128) | |
Text
{{#Wiki_filter:<$- '
,; s ,
, 4 i- ,
. i'y
-p') '
t
'/~ ,
w A n f 1 l 1 t Attachment 2 to U-601592 Proposed Changes to CPS Technical Specifications (No. LS-89-006) 4 k
.+.
4 900207009s 900126 p DR ADOCK 05000461 PDC h
LS 89 006' Page 1 of 127 Descriotion of-Pronosed Channes i
. Illinois Power.(IP) is proposing changes to the Clinton Power Station (CPS)
Technical Specifications to incorporate the guidance provided in Generic Letter (GL) 89 01, " IMPLEMENTATION OF PROGRAMMATIC CONTROLS FOR RADIO 1DGICAL EFFLUENT TECHNICAL SPECIFICATIONS IN THE ADMINISTRATIVE CONTROLS SECTION OF THE TECHNICAL SPECIFICATIONS AND THE RELOCATION OF PROCEDURAL DETAILS OF RETS TO THE OFFSITE DOSE CALCULATION MANUAL OR TO THE PROCESS CONTROL PROGRAM." Additionally, the revisions to the Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP) proposed by GL 89-01 are enclosed for review. The specific changes to the CPS l = Technical Specifications are described as follows: Technical Soccification Title Description of Chance INDEX VARIOUS Various changes are proposed for the Index to reflect, as applicable, changes made to the Technical Specifications. 1.18 GASEOUS RADWASTE This definition will be deleted TREATMENT SYSTEM from the Technical Specifications because after the implementation of GL 89-01, it will no longer be used in the Technical Specifications. 1.26 0FFSITE DOSE CALCULATION This definition is being revised MANUAL (ODCM) in accordance with GL 89-01. 1.42 SOLIDIFICATION This definition will be relocated to the PCP in accordance with GL 89 01. 1.43 SOURCE CHECK This definition will be doloted from the Technical Specifications because after implementation of GL 89-01, it will no longer be used in the Technical Specifications. 1.49 VENTILATION EXHAUST This definition will be deleted TREATMENT SYSTEM from the Technical Specifications because after-implementation of GL 89-01, it will no longer be used in the Technical Specifications. 3/4.3.7.1 RADIATION MONITORING In accordance with GL 89-01, the INSTRUMENTATION requirements of this specification which are related to the off-gas pre-treatment and post treatment process radiation monitors will be deleted as ; equivalent requirements have l
. RFP2:GSL8
[( ~ TC 1 V h ,
' i!)
. LS 89 006'- t
, :n . Page'2 of 127 y ., ' Technical! ,
.Soecification 1111g Descriotion of Chance 3/4.3.7.1' been incorporated into the ODCM.-
'(Cont'd); Additionally, since a SOURCE
,. CHECK is . not. applicable to the instruments remaining in Table 4.3.7.1-1, the SOURCE > CHECK
' column is being removed ~fron the
+
table. 4
; L3/4.3;7.11' RADIOACTIVE LIQUID EFFLUENT. In accordance with GL 89-01, all
' MONITORING INSTRUMENTATION of the current' requirements of. 1 this specification which are related to radioactivity mon-itors providing alarm and. auto-matic termination of release, radioactivity monitors providing -j O alarm but not providing auto- 4 matic termination of release, d flow rate measurement devices, and liquid storage tank: level indicating devices.will be-deleted-as equivalent requirements have been t
= incorporated into the ODCM, s 3/4.3;7.12 RADIOACTIVE GASEOUS EFFLUENT In accordance-with.GL 89 01,-tne-MONITORING INSTRUMENTATION requirements of this
, specification which are- related .
to the' station HVAC exhaust'PRM ; and the standby ~ gas treatment system exhaust PRM will be-deleted as equivalent require-ments have been incorporated into the 0DCM. Since-the only ! instrument (s) remaining to 'I be addressed by thi's .
-specification:is the main condenser off-gas treatment system explosive gas' monitor (s), i the specification will be-retitled, " MAIN CONDENSER OFFCAS'.
TREATMENT. SYSTEM EXPLOSIVE CAS R MONITORING INSTRUMENTATION." , 1 L ' t l - l-b 1' i RFP2:GSL8 f
~
(% - s LS.89 006 . ; Page 3 of 127. " ay , Technica1L i
'Snecification Title Descriution of Channe ;
x . t 3/4.3.7.12~- The associatad tables
- (Cont'd) (3.3.7.12-1 and 4.3.7.12-1) 1 .will be. deleted'as all of the 5'
applicable requirements'for this-4' monitor (s) can be specified . within the text of:the revised j gr
~
Specification (on one page). l e without the use of any tables.-- ' Additionally, since the explosive gas. monitor (s) does: l '1 . not require a, SOURCE CHECK, this i requirement is being removed.- 1
- j. Because the SpecificationL ,
addressing liquid effluent . . . monitoring instrumentation will. : be deleted (as described- M , previously), a change.to thel L Specification number for:the ,
?
main condenser'offgas treatment { L system explosive gas ~ monitoring l ll t instrumentation is proposed. That is,--the requirements for.
-this instrumentation will appear under Technical- '
'q
. Specification number 3/4 . 3 . 7.11'.
+ (Technical; Specification number. ,
, 3/4.3'.7.12 will no longer -
exist.)'
~
3/4.3.8 VARIOUS Because several pages will be through'_ deleted when Specifications-
-3/4.3.10 3/4.3.7.11 and 3/4.3.7.12 are
~ deleted or revised, the:page numbeis for Specific'ations
'3/4.3.8 through 3/4.3.10'will ,
be. revised.
.3/4.11.1.1, LIQUID EFFLUENTS: In~accordance with GL 89-01, CONCENTRATION this specification will be deleted as equivalent requirements have been L incorporated into the ODCM. *
= 3/4.11.1. 2 LIQUID EFFLUENTS: DOSE In accordance with GL 89-01, this specification will be 7 deleted as equivalent ,;
requirements have been incorporated into the ODCM.
'RFP2iGSL8
, i
. LS.89 006 ;
J,',, Page 4 of 127 ' Technical l Soecification I,id,g, Descrietion of Channa 3/4.11.1.3 LIQUID EFFLUENT;: LIQUID In accordance with GL 89 01 1 RADVASTE TREATMENT SYSTEta this specification will be
"~ deleted as equivalent !
requirements hava been f incorporated into the ODCM. ! 3/4.11.1.4 LIQUID EFFLUENTS: LIQUID specification 3/4.11.1.4 will ! HOLDUP TANKS be relocated to Section 3/4.7 i (Plant Systems) of the i Technical Specifications *. It I will thus be renumbered as !' Specification 3/4.7.7 , l, .. (p. 3/4 7 18). The title will i be slightly changed to " LIQUID STORAGE TANKS". ; 3/4.11.2.1~ GASEOUS EFFLUENTS: DOSE In accordance with GL 89 01, f RATE this specification will be i deleten as equivalent j requirements have been ' incorporated into the ODCM. 13/4'11.2.2 GASEOUS EFFLUENTS: DOSE - In accordance with GL 89 01, .f NOBLE CASES this specification will be ; deleted as equivalent , requirements have been : incorporated into the ODCM. j 3/4.11.2.3 CASEOUS EFFLUENTS: DOSE - In accordance with GL 89 01,
, s 10 DINE 131, 10DIFF, 133, this specification will be
, TRITIUM, AND RADIS1UCLIDES deleted as equivalent -
n reqCrements have been incorporated into the ODCM. o., ? !
. *This will facilitate the complete elimination of Technical Specification Section i 3/4.11 as most of the associated requirements have been removed and relocated to the '
i !j ODCM or PCF and the remaining requirements are relocated to Section 3/4.7 of the lN Technical Specifications. 1 i 1 g RFP2:CSL8
3 i i t I.S.89 006 j
- l. Page 5 of 127 ;
1 L Technical { l .Soecification Iltig Descrietion of Channe l l 3/4.11.2.4 CASEOUS EFFLUENTS: CASEOUS In accordance with CL 89 01, L RADVASTE (OFFCAS) TREATMENT this specification will be = l deleted as equivalent 3 requirements have been t incorporated into the ODCM. l t (l 3/4.11.2.5 CASEOUS EFFLUENTS: In accordance with CL 89 01, j l VENTIIATION EXHAUST TREATMENT this specification will be i deleted as equivalent ! requirements have been incorporated into the ODCM. j i' 3/4.11.2.6 CASEOUS EFFLUENTS: Since Specifications 3/4.11.2.6- , and EXP!4SIVE CAS MIXTURE and 3/4.11.2.7 both concern > 3/4.11.2.7 AND monitoring of the main condenser ; CASEOUS EFFLUENTS: MAIN offgas (either at the recombine ; CONDENSER effluent point or in the holdup / ! treatment system), these Specif.
- ications will be relocated to Section 3/4.7 (Plant Systems) of ;
the Technical Specifications
~
where.they will be retained under new Specification number 3/4.7.8 (MAIN CONDENSER OFFCAS , MONITORINC).* Specification 3/4.11.2.6 will be renumbered as ! Specification 3/4.7.8.1, and {' Specification 3/4.11.2.7 will be renumbered as Specification 3/4.7.8.2. These will be , respectively entitled as "0FFCAS EXPL9SIVE CAS MIXTURE" and "0FFCAS NOBLE CAS RADIOACTIVITY RATE." { 3/4.11.3 SOLID RADIOACTIVE WASTE In accordance with'CL 89 01, : this specification will be : deleted as equivalent requirements have been incorporated into the PCP. P
*This will facilitate the complete elimination of Technical Specification Section '
3/4.11 as most of the associated requirements have been removed and relocated to the ODCM or PCP and the remaining requirements are relocated to Section 3/4.7 of the , Technical Specifications.
,RTP2:CSL8
j' t LS.89 006 j Page 6 of 127' Technical Seceification Iltig Descrietion of Channe 3/4.11.4 RADIOACTIVE EFFLUENTS: In accordance with GL 89 01 I TOTAL DOSE this specification will be j deleted as equivalent ' requirements have been incorporated into the ODCM. ;
.I 3/4.12.1 RADIOLOGICAL ENVIRONMENTAL In accordance with GL 89 01, MONITORING: MONITORING this specification will be , ,. PROGRAM deleted as equivalent r requirements have been incorporated into the ODCM. '
3/4.12.2 RADIOlhGICAL ENVIRONMENTAL In accordance with GL 89 01, , MONITORING: IAND USE CENSUS this specification will be deleted as equivalent F requirements have been i i m orporated into the ODCM. i 3/4.12.3 RADIOLOGICAL ENVIRONMENTAL in accordance with GL 89 01, , MONITORING: INTERIABORATORY this specification will be ! COMPARISON PROGRAM deleted as equivalent ' requirements have been incorporated into the ODCM. Due to the relocation of the requirements associated with Specifications 3/4.12.1, 3/4.12.2, and 3/4.12.3 as described above, the CPS Technical Specifications will no longer include a section numbered "3/4.12" and entitled " RADIOLOGICAL ENVIRONMENTAL i MONITORING." ; j B'3/4.3.7.1 RADIATION MONITORING Although certain portions of f INSTRUMENTATION Specification 3/4.3.7.1 will be deleted, these changes require ; no changes to the BASES. That is, this BASES section is still , applicable to the remaining i
, portion of Specification 3/4.3.7.1. r B 3/4.3.7.11 RADIOACTIVE LIQUID EFFLUENT In accordance with the changes MONITORING INSTRUMENTATION proposed for the corresponding Technical Specification (3/4.3.7.11), this Bases section is being deleted as all of the requirements associated with Specification 3/4.3.7.11 are ,
being relocated to the ODCM. I RFP2:GSL8
i LS.89 006 Page-7 of 127 1 Technical Specification 1111g Descrintion of Chance B 3/4.3.7.12 RADI0 ACTIVE CASEOUS EFFUDENT In accordance with the changes MONITORING INSTRUMENTATION proposed for the corresponding Technical Specification (3/4.3.7.12), the portions of this Bases section which are related to the station HVAC exhaust PRM and the standby gas treatment system exhaust PRM will be relocated to the ODCM. This BASES section is therefore being-revised such that only the main condenser offgas treatment system explosive gas monitoring instrumentation is addressed. More specific wording to address the requirements for this instrumentation is proposed. The title of this BASES section is also being revised accordingly to match the new title for Specification 3/4.3.7.12 (MAIN CONDENSER OFFCAS TREATMENT SYSTEM EXPLOSIVE GAS MONITORING INSTRUMENTATION). This BASES section is also being renumbered as the associated Technical Specification number will be 3/4.3.7.11 due to deletion of the Technical Specification currently identified with that number. 1 l B 3/4.11.1.1 LIQUID EFFLUENTS: This Bases section is being CONCENTRATION relocated to the ODCM. l L' B 3/4.11.1.2 LIQUID EFFLUENTS: DOSE This Bases section is being l relocated to the ODCM. B 3/4.11.1.3 LIQUID EFFLUENTS: LIQUID This Bases section is being RADWASTE TREATMENT SYSTEM relocated to the ODCM. l-l L l l 1 b l RFP2:CSL8
n I-r LS.89 006
' Page 8 of 127 Technical ; Specification litig Descrintion of channe i
B 3/4.11.1.4 In accordance with the changes LIQUID EFFUDENTS: LIQUID HOLDUP TANKS proposed for the corresponding Technical Specification, this BASES section will be
' relocated and renumbered as 3/4.7.7 (a new number).
It will also be retitled L slightly (LIQUID STORACE TANKS) to match the e corresponding retitled Technical Specification. L B 3/4.11.2.1 CASEOUS EFFLUENTS: DOSE RATE This Bases section is being relocated to the ODCM. L B 3/4.11.2.2 CASE 0VS EFFUDENTS: DOSE - This Bases section is being NOBLE CASES relocated to the ODCM B 3/4.11.2.3 CASEOUS EFFLUENTS: DOSE - This Bases section is bul 3 10 DINE 131, 10 DINE 133, relocated to the ODCM. TRITIUM, AND P.ADIONUCLIDES IN PARTICULATE FORM B 3/4.11.2.4 CASEOUS EFFLUENTS: CASEOUS This Bases section is being RADWASTE (OFFCAS) TREATMENT relocated to the ODCM. B 3/4.11.2.5 CASEOUS EFFLUENTS: This Bases section is being VENTIIATION EXHAUST TREATMENT relocated to the ODCM.. B 3/4.11.2.6 EXPLOSIVE CAS MIXTURE In accordance with the and changes proposed for the
- - B 3/4.11.2.7 MAIN CONDENSER corresponding Technical Specifications, these BASES sections will be relocated, renumbered and retitled as "3/4.7.8.1 OFFCAS EXPLOSIVE CAS MIXTURE," and "3/4.7.8.2 0FFCAS.
NOBLE CAS RADIOACTIVITY RATE " respecti'vely within the BASES section. They will appear under "3/4.7.8 MAIN CONDENSER OFFCAS MONITORINC."*
- Note that the text of the BASES for the new proposed Specification 3/4.7.8.1 has been revised relative to the current BASES for Specification 3.11.2.6. The Standard Technical Specification description of automatic features ' associated with the explosive gas monitoring system is not applicable to the system design for Clinton. I 4
RFP2:CSL8
13 89 006 Page 9 of 127 Technical Specification h Dg.g,gyiotion of Chance B 3/4.11.3 SOLID RADIOACTIVE WASTE This Bases section is being relocated to the PCP. B 3/4.11.4 RADI0 ACTIVE EFFLUENTS: This Bases section is being TOTAL DOSE relocated to the ODCM. liq.TI Due to the relocation of the BASES sections as described above, the BASES will no longer include a section numbered "3/4.11" and entitled "RADI0 ACTIVE EFFLUENTS." B 3/4.12.1 RADIOLOGICAL ENVIEONMENTAL This Bases section is being MONITORING: MONITORING relocated to the ODCM. PROGRAM . B 3/4.12.2 RADIOLOGICAL ENVIRONMENTAL This Bases section is being MONITORING: LAND USE CENSUS relocated to the ODCM. B 3/4.12.3 RADIOLOGICAL ENVIRONMENTAL This Bases section is being MONITORING: INTERLABORATORY relocated to the ODCM. COMPARISON PROGRAM li2IE Due to the relocation of.the BASES sections as described above, the BASES will no longer include a section numbered "3/4.12" and entitled " RADIOLOGICAL ENVIRONMENTAL MONITORING.", 6.8.4.f (new) PROCEDURES AND PROGRAMS: In accordance with CL 89 01, Radioactive Effluent this specification is being Controls Program added te provide additional programmatic controls for the ODCM. 6.8.4.g (new) PROCEDURES AND PROGRAMS: In accordance with GL 89 01, Radiological Environmental this specification is being Monitoring Program added to provide additional programmatic controls for the ODCM. l l 6.9.1.6 REPORTING REQUIREMENTS: In accordance with GL 89 01, ANNUAL RADIOLOGICAL this specification is being ENVIRONMENTAL OPERATING revised to simplify and condense REPORT the overall requirement as certain details have been relocated to the ODCM. l l l , l l l l RFP2:CSL8
LS.89 006 Page 10 of 127 l W Technical' !
'Soecification I111g Descrintion of Chance 6.9.1.7 REPORTING REQUIREMENTS: In accordance with GL 89 01, ,
SEMIANNUAL RADIDACTIVE this specification is being : EFTLUENT RELEASE REPORT revised to simplify and condense 5 the overall requirement as - certain details have been relocated to the ODCM. 6.10.3.n (new) RECORD RETENTION In accordance with GL A9 01, 4 this specification is being incorporated into the Technical - Specifications to add record retention requirements for revisions to the ODCM and PCP. l 6.13 PROCESS CONTROL PROGRAM This specification is being (PCP) revised in accordance with GL 89 01 to describe the administrative requirements for the PCP. 6.14 0FFSITE DOSE CALCULATION This. specification is being MANUAL (ODCM) revised in accordance with GL ' 89 01 to describe the - administrative. requirements for t the ODCM. , 6.15 MAJOR CHANGES TO RADIOACTIVE In accordance with GL 89 01, LIQUID, CASEOUS AND SOLID this specification will be WASTE TREATMENT SYSTEMS deleted. The requirements ' of the existing specification have been relocated to the ODCM and PCP as appropriste. 4 The marked up Technical Specification pages which reflect these changes are enclosed with this submittal. i Generic Letter 89 01 Actions (1) . Generic Letter 89 01 requires the incorporat!an of programmatic controls'in the Administrative. Controls section of the Trchnical Specifications that satisfy the requirements of 10CTR20.106, 10CFR50 Appendix I, 10CFR50.36a and 40CFR190. Enclosure 3 of Generic Letter 89 01 provides model Technical Specifications for the A&ninistrative Controls section that satisfy these requirements. As shown in the marked up Administrative Controls section of the CPS Technical Specifications included in this submittal, these model specifications are being incorporated into the CPS Technical Specifications without any significant differences. (2) Generic Letter.89 01 requires the relocation of the existing requirements in the current specifications involving radioactive effluent monitoring instrumentation, the control of liquid and gaseous effluents, radiological environmental monitoring and radiological reporting details from the Technical
. RFP2:GSL8
F , LSo89 006 t i Page 11 of 127 ; i Specifications to the ODCM. The enclosed copy of the revised CPS ODCM contains the applicable equivalent requirements which are being removed from i the Technical Specifications. l (3) Generic Letter 89 01 requires the relocation of the definition of l solidification and the existing requirements in the current specifications i involving solid radioactive vastes to the PCP. The enclosed copy of the ! revised CPS PCP contains the definition of solidification and the applicable ! requirements regarding solid radioactive wastes. l (4) Generic Letter 89 01 provides simplified reporting requirements. The f simplified reporting requirements specified in the Model Technical Specifications provided in Enclosure 3 of Generic Letter 89 01 are being incorporated into section 6.0 of the CPS Technical Specifications. (5) Generic Latter 89-01 provides simplified Administrative Controls for changes to the ODCM and PCP. The simplified Administrative Controls specified in the Model Technical Specifications provided in Enclosure 3 of Generic Letter 89-01 are being incorporated into the CPS Technical Specifications.
'(6) Generic Letter 89 01 requires the addition of record retention requirements for changes to the ODCM and PCP. Technical Specification 6.10.3.n is being added to specify the record retention requirements for changes to the ODCM and PCP.
(7) Generic Letter 89 01 requires updated definitions of the ODCM and PCP to ensure consistency with the other changes associated with the Generic Letter. - A revised definition of the ODCM is included with this Technical Specification t change request. The definition of the PCP is not being revised since the , current definition is equivalent to the proposed definition. ; Justif f ention for Prooosed Chanste l This proposed change involves the relocation of portions of the Radiological Effluent Technical Specification (RETS) identified by the NRC in CL 89 01. The L specific requirements are not being changed. Therefore, there will be no resultant l reduction in the level of radiological effluent control at CPS. l The proposed change also inserts additional Administrative Controls into the Technical Specifications to ensure that the requirements of 10CFR20.106, 10CFR50.36a, 10CFR50 Appendix I and 40CFR190 are satisfied by the CPS Technical . Other Administrative Controls =are being added to the Technical Specifications. Specifications to control future changes to the ODCM and PCP and simplify the reporting requirements regarding radiological effluent releases. As the requirements and recommendations of CL 89 01 were utilized to prepare this proposed amendment, additional changes were identified that were not specifically ; identified in CL 89-01 but are desired due to related changes that are specifically ' recommended by the generic letter. These additional changes are minor and are described and justified in the following section. Additionni Chances l Technical Specification 1.18, CASEOUS RADWASTE TREATMENT SYSTEM, will be deleted, o Deleting this definition is not addressed in CL 89 01. However, CL 89-01 does 1
, RFP2:CSL8-
LS 89 006 l Page 12 of 127 i delete / relocate Technical Specification 3/4.11.2.4, which is the only specification l in the current CPS Technical Specilications that uses the term " GASEOUS RADWASTE TREATMENT SYSTEM". , Technical Specification 1.43, SOURCE CHECK, will be dt.leted. Deleting this definition is not addressed in GL 89 01. However, CL 89 01 does delete / relocate all of the Section 3/4 CPS Technical Specification requirements which use the term
" SOURCE CHECK". , ! Technical Specification 1.49, VENTILATION EKHAUST TREATMENT SYSTEM, will be deleted.
Deleting this definition is not addressed by GL 89 01. However, CL 89-01 does , delete / relocate all of the section 3/4 CPS Technical Specification requirements which use the term " VENTILATION EXHAUST TREATMENT SYSTEM". , It should be noted that all of the above definitions being removed from the ! Technical Specifications appear in the ODCM. It should also be noted that GL 89 01 i proposes a revision to Technical Specification 1.32, PROCESS CONTROL PROGRAM. Because the existing CPS Technical Specification is almost identical to the proposed specification and satisfies the intent of the proposed definition, IP is not proposing to revise Specification 1.32. , Basis For No Sinnificant Hazards Consideration According to 10CFR50.92, a proposed change to the license (Technical Specifications) involves no significant hazards consideration if operation of the facility in accordance with the proposed change would not (1) involve a significant increase in - the probability or consequences of an accident previously evaluated, or (2) create
-the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.
(1) The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed changes involve the relocation of the existing requirements of the current Technical Specifications for radioactive effluents, radiological environmental monitoring and solid radioactive vastes to the ODCM or PCP as appropriate, and I the addition of new adminstrative requirements to the Technical l' Specifications. This will result in no reduction in the requirements I associated with the existing Technical Specifications. (2) The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed changes do not involve a change to the plant's physical configuration nor do they change the operation or testing of any of the plant's systems or components. L (3) The proposed changes do not involve a significant reduction in a margin of safety. The proposed changes do not change any existing radiological limits. The proposed changes relocate these limits to the ODCM or PCP as appropriate. Additionally, administrative controls are being added to the Technical l Specifications to ensure that future changes to the ODCM and PCP do not result I in reduction to a margin of safety with regard to these limits. l .--
-RFP2:GSL8
g -- LS-89-006 ~ f P0g3 13 of 127 ! J I'40EX
- 1. 0 DEFINITIONS l i
SECTION PAGE 'l AClI0N......................................................... 1 L 1.1 1-1 1 L '1.2 3VERAGE PLANAR EXPOSURE........................................ 1-1 ! 1.31 AVERAGE PLANAR LINEAR HEAT GENERATION RATE..................... 1-1 1
, 1. 4 C H ANN E L C A L I B R AT I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 l
- 1. 5 : CHANNEL CHECK.................................................. 1-1 l
- 1. 6 CHANNEL FUNCTIONAL TEST........................................ 1-1 !
- 1. 7 CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM I RESPONSE TIME.........-........................................ 1-2 ;
- 1. 8 CORE ALTERATION................................................ 1-2
- 1. 9 CRITICAL POWER RATI0........................................... 1-2 - I 1 10 DOSE EQUIVALENT I-131.......................................... 1.2 .
1.11 DRYWELL INTEGRITY............................................., 1-2 1.12 E - AVERAGE DISINTEGRATION ENERGY.............................. 1-3 1
- 1.13 EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME............. 1-3 1.14 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME. . . . . . 1-3 1.15 DELETE 0........................................................ 1-3 1.16 DELETED........................................................ .
1-3 1.17' FREQUENCY N0TATION............................................. 1-4 af>LLLTED 1.181 GASEOUS RA0 WASTE TREATMENT SYSTERfI........................... 1-4 1.19 IDENTIFIED LEAKAGE............................................. 1-4 1.20 LIMITING CONTROL ROD PATTERN................................... 1-4 1.21 LINEAR HEAT GENERATION' RATE.................................... 1-4 - 1.22 LOGIC SYSTEM FUNCTIONAL TEST................................... 1-4 1.23 DELETED........................................................ 1-4 9 I CLINTON'- UNIT 1 i M
LS-89-006 ! fD Pag 2 14 of 127 i
}= ,
. 'INDEX j i
h: . J i DEFINITIONS t
)
SECTION PAGE - 1.24 MEMBER (S) 0F THE PUBLIC........................................ 1-4 'I 1.25 MINIMUM CRITICAL POWER RAT 10................................... 1-5 i 1.26 0FFSITE DOSE CALCULATION MANUAL (0DCM)......................... 1-5 ;
- 1. 27 O P E RAB LE - O P E RAB I LITY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 l
- 1. 28 OPERATIONAL CONDITION - CONDITION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 i
1.29 PHYSICS TESTS.................................................. 1-5 l 1.30 PRESSURE BOUNDARY LEAKAGE...................................... 1-5 s 1.31 PRIMARY CONTAINMENT INTEGRITY.................................. 1-5
~ 1. 32 PROCESS CONTROL PROGRAM (PCP). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 _
1.33 PURGE - PURGING................................................ 1-6 ; 1.34 RATED THERMAL P0WER............................................ 1-6 1.35 REACTOR, PROTECTION SYSTEM RESPONSE TIME........................ 1-6
^
~ 1.36 REPORTABLE EVENT............................................... 1-6 1.37 ROD DENSITY.................................................... 1-7 ,
1.38 SECONDARY CONTAINMENT INTEGRITY................................ 1-7 1,39 SELF TEST SYSTEM................................................ 1-7 1.40 SHUTDOWN MARGIN................................................ 1-8 ! 1.41 SITE B0VNDARY.................................................. 1-8 > L- Dr.LETE D -. c 1,42{50LIDIFICATIONT................................................ 1-8 L 1.43J50VRCE CHECKTf*................................................ 1-8 C 6 LLtrt O 1.44 STAGGERED TEST BASIS......................................... . 1-8 1.45 THERMAL P0WER.......'........................................... 1-8 1.46 TURBINE BYPASS SYSTEM RESPONSE TIME............................ 1-8 > p 1.47 UNIDENTIFIED LEAKAGE........................................... 1-8 t '- 'CLINTON - UNIT 1 11 L
LS-89-006 ! Peg 2 15 of 127 l A -, INDEX { DEFINITIONS SECTION PAGE 1 1 1.48 UNRESTRICTED AREA.............................................. 1-9 (D EL2.TED ) 2 1.491VfNTILAT10N EXHAUST TREATMENT SYSTE .......................... 1-9 j 1.50 VENTING.............................. ......................... 1-9 Table 1.1 Surveillance Frequency Notation.......................... 1-10
+
J Table 1.2 Operational Concitions................................... 1-11 I l L 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS __
'1 2.1 SAFETY LIMITS THERMAL POWER, Low Pressure or Low F10w........................ 2-1 THERMAL POWER, High Pressure and High Flow..................... 2-1
~
~
Reactor Coolant System Pressure................................ 2-1 > Re acto r Ve s s e l Wate r Leve l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 . 2.2 LIMITING SAFETY SYSTEM SETTINGS _ Reactor Protection System Instrumentation Setpoints. . . . . . . . . . . . '2-2 - l Table 2.2.1-1 Reactor Protection System Instrumentation Setpoints.. 2-3 BASES , 2.1 SAFETY LIMITS - Introduction................................................... B 2-1 THERMAL POWER, Low Pressure or Low F1ow........................ B 2-1 THERMAL POWER, High Pressure and High Flow..................... B 2-2
- Reacto r Cool ant System P res s ure. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 2-2
' DELETED........................................................ 8 2-3 CLINTON - UNIT 1 iii t
$ LS-89-006 . y
'; . Peg 2 16 of 127 '~ {
j INDEX
. 1 i
LIMITING CONDITIONS FOR OPERATION'AND SURVEILLANCE REQUIREMENTS i SECTION . PAGE
. i INSTRUMENTATION (Continuejd,l ,
l Tcble 3.3.7.4-1 RemoteShdtdownMonitoringInstrumentation......... 3/4 3-82 f Table 3.3.7.4-2 Remote Shutdown System Controls.................... 3/4 3 83 Tcble 4.3.7.4-1 Remote Shutdown Monitoring Instrumentation ! Surveillance Requirements................................. 3/4 3-85 i Accident Monitoring Instrumentation....................... 3/4 3-86 1 Table 3.3.7.5-1 Accident Monitoring Instrumentation. . . . . . . . . . . . . . . . 3/4 3-87 ; Table 4.3.7.5-1 Accident Manitoring Instrumentation Surveillance ; i Requirements.............................................. 3/4 3d9 , Source-Range Monitors..................................... 3/4 3-90 : Traversing In-Core Probe System.....................,...... 3/4 3-91 : Chlorine Detection System................................. 3/4 3-92 Fire Detection Instrumentation (deleted).................. 3/4 3-93 i Loose-Part Detection System............................... 3/4'3-94 V [ Radioactive Licuid Effluent Monitoring Instrumentation.... 3/4 3-95-)
~
^
fTable 3.3.7.11-1 Radioactive Liquid Effluent Monitoring #- Instrumentation........................................... 3/4 3-96 r { Table 4.3.'I.11 Radioactive Li. quid Effluent Monitoring (- Instrumentation Surveillance Reavirements................. Main Condenser,oggaa Treatment Syshm Explosive 3/4 3-98) (RadioactivM GasEcus Ef fluent 7Fionitoring Instrumentation. . . 3/4 3 01 7able.3.3.7.12-1 Radioactive Gaseous Effluent Monitoring ' - Instrumentation........................................... 3/4 3-102 ; i Table 4.3.7.12 Radioactive Gaseous Effluent Monitoring - Instrumentation Surveillance Requirements...............s. 3/4 3-105 ( l3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM........................ 3/4 3 @ ' ' 3/4.3.9 PLANT SYSTEMS ACTUATION INSTRUMENTATION.................... 3/4 3 -
=
CLINTON - UNIT 1 viii .
i LS-89-006
- Pago 17 of 137 l INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS _.
SECTION PAGE -
;[ .
l INSTRUMENTATION (Continued) . 99 Table 3.3.9-1 Plant Systems Actuation Instrumentation.............. 3/4 3 i Table 3.3.9-2 Plant Systems Actuation Instrumentation Setpoints.... 3/4 3- h tol Table 4.3.9.1-1 Plant Systems Actuation Instrumentation 30 2 Surveillance Requirements................................. 3/4 3 @ 3/4.3.10 NUCLEAR SYSTEM PROTECTION SYSTEM - SELF TEST SYSTEM........ 3/4 3 3/4.4 REACTOR COOLANT SYSTEM - 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops....................................... 3/4 4-1 , I Figure 3.4.1.1-1 Thermal Power Versus Core F1ow.................... 3/4 4-5 - Jet Pumps............................ .................... 3/4 4-6 : l- Recirculation Loop F1ow................................... 3/4 4-7 l Idle Recirculation Loop Startup........................... 3/4 4-8 3/4.4.2 SAFETY VALVES h Safety / Relief Va1ves....... .............................. 3/4 4-9 Safety / Relief Valves Low-Low Set Function................. 3/4 4-11 l 3/4 4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems................................. 3/4 4-12 i j Operational Leakage..............................'......... 3/4 4-13 Table 3.4.3.2-1 Reactor Coolant System Pressure Isolation Valves... 3/4 4-15 - 3/4.4.4 CHEMISTRY.............................................:... 3/4 4-16 Table 3.4.4-1 Reactor Coolant System Chemistry Limits. . . . . . . . . . . .'. . 3/4 4-18 l l 3/4.4.5 SPECIFIC ACTIVITY......................................... 3/4 4-19 - 1 Table 4.4.5-1 Primary Coolant Specific Activity Sample and Analysis Program.......................................... 3/4 4-21
! CLINTON - UNIT 1 ix
l.
' LS-89-006. 1
. Pags 18 of 127 .) .
m
- f.
- l
! . INDEX- -
- p. .
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS i
'SECTION PAGE-CONTAINMENT SYSTEMS (Continued) *
~
Table 3.6.6.2-1 secondary Containment Ventilation System Automatic Isolation 0ampers............................... 3/4 6-69 t Standby Gas Treatment System.............................. 3/4 6 70 ; 3/4.6.7 ATH0 SPHERE CONTROL Containment Hydrogen Recombiner Systems................... 3/4 6-73 Containment /Drywell Hydrogen Mixing System................ 3/4 6-75 Primary Containment /Drywell Hydrogen Ignition System...... 3/4 6-76 .; i 3/4.7 PLANT SYSTEMS . 3/4.7.1 SERVICE WATER SYSTEMS Shutdown Service Water System (Loops A, B, C). . . . . . . . . . . . . 3/4 7-1 - Ultimate Heat Sink........................................ 3/4 7-2 ; i 3/4.7.2. CONTROL ROOM VENTILATION SY3 TEM........................... 3/4.7-3 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM..................... 3/4 7-7 3/4.7.4 SNUBBERS.................................................. 3/4 7-9 *' ~~ Figure 4.7.4-1 Sample Plan for Snubber Functional Test. . . . . . . . . . . . . 3/4 7-14 7 3/4.7.5 SEALED SOURCE CONTAMINATION............................... 3/4 7-15 F 3/4.7.6 MAIN TURBINE BYPASS SYSTEM................................ 3/4 7-17 4 %.r t l L3/4.8 ELECTRICAL POWER SYSTEMS S/4.8.1 'AC SOURCES AC Sources - Operating.................................... 3/4 8-1 Table 4.8.1.1.2-1 Diesel Generator Test Schedule................... 3/4 8-10
~
. AC~ Sources - Shutdown..................................... 3/4 8-11 3/4.8.2 DC SOURCES DC Source's - Operating.................................... 3/4 8-12 CLINTCN - UNIT 1 -
xii
e a- , y ,
, ')_ -4
.k l
1 , . j
,I \< ,'
y . !l . t t,I LS 89 006 a Page 19 of 127 ! i 4 ( -$ . .- e
" ' - Innert for'emen vii fu 4 g
f
' )
3/4. 7. 7 = LIQUID STORAGE TANKS . . . -. . . . . . . . . . . . . . . . '. . . . . . . . 3/4 7 18 ' j w ' 3/4.7.8' MAIN CONDENSER OFFCAS MONITORING l Offgas'- Explosive cas Mixture .................-3/4 7 19 E . .
;offgas'- Noble Cas-Radioactivity Rate ......... 3/4 7 20- i i- r P ,h,-
i 4 1 , l,
.- t l- ! '. j i' .
8
-t
;)
., b g
.'s q
JlNb J i- 5 a . , 4 <2-- .
.(
- j 1i i
1 -
?
?
1 '.I -> l i i . .! l-RFP2:CSL8 . 1 r
- - -.+,e- -n ,-.-- ~ + ,-ww, - ,,==. . , <,,w -
t
,i LS-89-006 ,
;lm ..
Pasi 20 of 127 l
(' o. , y, s . t F. < . Ii ' s .- INDEX i LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCt REOUIREMENTS
); !
- PAGE SECTION i ,
3/4.9 REFUELING OPERA 1 IONS (Continued) .
~
L 3/4.9,9' WATER LEVEL - SPENT FUEL STORAGE AND UPPER CONTAINMENT8/4 9-12 k . FUEL P00LS................................................ ; n .. p 3/4.'9.10 CONTROL ROD REMOVAL
"; 3/4 9-13 l Single Control Rod Remova1................................
Remova1.................... ......... 3/4 9-15 Multiple Control Rod 3/4.9.11 RESIDUAL MEAT REMOVAL AND COOLANT CIRCULATION 3/4 9-17 [ Hi g h Wa te r Le v e1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-18 l Low Water Leve1........................................... 3/4 9-19 3/4.9.12 INCLINED FUEL TRANSFER SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . t 3/4.10 SPECIAL TEST EXCEPTIONS i
+ 3/4 10-1 ;
3/4.10.1 PRIMARY CONTAINMtNT INTEGRITY /0RYWELL INTEGRITY........... I 3/4 10-2 3/4.10.2 ROD P ATTERN CONTROL SYST EM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-3 l 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS. . . . . . . . . . . . . . . . . . . . . . . . . . . . ~" 3/4104*" . 3/4.10.4 RE C I RCU LAT I O N L00 P S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-5 . 3/4.10.5 T RAI NI NG ST ARTU P S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10 6 i 3/4.10.6 -SPECIAL INSTRUMENTATION - INITIAL CORE LOADING............ _ _ N
/4.11 RADIDACTIVE EFFLUENTS ,
-3/4.11.1 LIQUID EFFLUENTS 3/4 11-1 Concentration.............................................
Table 4.11-1_ Radioactive Liquid Waste Sampling and Analysis 3/4 11-2 . Program.................................................,.. . 3/4 11-5 Dose...................................................... 3/4 11*6 Liquid Radwaste Treatment System. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 11 ' Li qui d Hol dup Tanks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Y CLINTON - UNIT 1 xiv .
' - LS-89-006 !
Paga 21 of 127 [ {L < 1 e l INDEX t LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS I
- PAGE I I SECTION' f 3/4.11.2 GASEOUS EFFLUENTS ' 5fL" '
Dose Rate.............'..............................:..... 3/4 11-8 Table 4.11.2-1 Radioactive Gaseous Waste Sampling and Analysis Program................................................... 3/4 11-9 g , i
)
! Dose - Noble Gases........................................ 3/4 11-12 :
; i Dose Iodine-131, lodine-133 Tritium, and Radionuclides l' 4
4 in Particulate Form........................................ 3/41}-13 I Gaseous Radwaste (Offgas) Treatment....................... 3/4 11-14
~
Ventilation Exhaust Treatment............................. 3/4 11-15 Explosive Gas Mixture..................................... 3/4 11-16 , Main Condenser............................................ 3/4 11-17 3 l ? 1 3/4.11.3 SO LI D RAD I 0 ACT IVE WAST E. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 11-18 : s I '
'i '
3/4.11.4. TOTAL 00SE................................................ 3/4 11 f I 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING . 3/4.12.1 MONITORING PR0 GRAM........................................ , 3/4 12-1 u' Table 3.12-1 Radiological Environmental Monitoring Program......... 3/4 12-3 l 4 Table 3.12-2 Reporting' Levels for Radioactivity Concentrations in E,nvironmental Samples.................................. 3/4 12 9 l
) Table 4.12-1 Detection Capabilities for Environmental Sample ;
j Analysis Lower Limit of Detection......................... 3/4'12-10 l_ li 3/4.12.2 LAND USE CENSUS...........................................- 3/4 12-13^ ; i, 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM........................ . 3/412-15) a - - .
- _ . _s .
CLINTON - UNIT 1 xv
# '"'"""" = * - *- -- --- _ __ ___ . _ _ , _ _ _ _ _ _ _ , _ , , . _ _ _
8'M +- - .w 2_ ts.89-006 C ,- Pcg2 22 ef 127-o i t
~
.i INDEX
' BASES .*
SECTION ., PAGE . I L ) INSTRUMENTATION-(Continued) , Gadioactive Liauid Effluent Monitorino Instrumentation.... B 3/4 3-8) f Mein Cavidenser gges Treatinent Qatem E.xplosive h (Radioactivr GasFous Effluent 7 Monitoring Instrumentation... B 3/4 3-8 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM...........'............ B 3/4 3-8 . 3/4.3.9 PLANT SYSTEMS ACTUATION INSTRUMENTATION................... B 3/4 3-8 3/4 3.10 NUCLEAR SYSTEM PROTECTION SYSTEM - SELF TEST SYSTEM....... B 3/4 3-9
' Bases' Figure.B 3/4.3 1 Reactor Vessel Water Leve1.................. B 3/4 3-10 >
3/4.4 REACTOR COOLANT SYSTEM i 3/4.4.1 RECIRCULATION SYSTEM.........'............................. B 3/4 4-1 3/4.4.2 ' SAFETY / RELIEF VALVES....................................... B 3// 4-3 , 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE
?
( Leakage Detection Systems.....................'............ B 3/4 4-3 ,3 t Operational Leakage....................................... B 3/4 4 3 t 3/4.4.4 CHEMISTRY................................................. B 3/4 4-4 _ _, 3/4.4.5 SPECIFIC ACTIVITY......................................... B 3/4 4-4 3/4.4.6 PRESSURE / TEMPERATURE LIMITS............................... B 3/4 4-5 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES.......................... B 3/4 4-6 , 3/4.4.8 STRUCTURAL INTEGRITY....................................... B 3/4 4-7 < 3/4.4.9 RESIDUAL HEAT REM 0 VAL..................................... B 3/4 4-7 , l Bases. Table B 3/4.4.6-1 Reactor Vessel Toughness Values............ B 3/4 4-8 Bases Figure B 3/4.4.6-1 Fast Neutron Fluence (E>1 Mev) at k T as a Function of Service L1fe................................ B 3/4 4-10 t
' Figure B 3/4.4.6-2 PredictedAdjustmentofReferenceTemperature. -
"A", as a Function of Fluence and Copper Content per NRC Regulatory Guide 1.99..................................... B 3/4 4-11 .
CLINTON - UNIT 1 xviii
4 LS-89-006 ; t Paga 23 cT727 l l i INDEX-i RASES
~
PAGE SECTION , { CONTAINMENT SYSTEMS (Continued) . 3/4.6.6 SECONDARY CONTAINMENT..................................... B 3/4 6-8 j 3/4.6.7 ATMOSPHERE CONTR0L........................................ B 3/4 6-8 3/4.7 PLANT SYSTEMS 3/4.7.1 SHUTDOWN SERVICE WATER SYSTEM............................. B 3/4 7-1 , L - 3/4.7.2 CONTROL ROOM VENTI LATION SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-1 L 1
'3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM..................... B 3/4 7-1 ,
3/4.7.4 SNUBBERS.................................................. B 3/4 7-2 : 3/4.7.5 SEALED SOURCE CONTAMINATION............................... B 3/4 7-3 ! 3/4.7.6' HAIN TURBINE BYPASS SYSTEM................................ B 3/4 7-3 - In,.rt . l '
'3/4.8 ELECTRICAL POWER SYSTEMS .
1 3/4.8.1, e 3/4.8.2, AC SOURCES, DC SOURCES, AND ONSITE POWER and. DISTRIBUTION SYSTEMS...................................... B 3/4 8-1 3/4.8.3 " 3/4.8.4- ELECTRICAL EQUIPMENT PROTECTIVE DEVICES................... B 3/4 8-2
?
3/4.9 REFUELING OPERATIONS i
~ 3/4.9.1 REACTOR MODE SWITCH.......................................
B 3/4 9-1 . 3/4.9.2. INSTRUMENTATION........................................... B 3/4 9-1 3/4.9.3 CONTROL R00 P0SITION....................................... B 3/4 9-1 3/4.9.4 DECAY TIME................................................ B 3/4 9-1 3/4.9.5 COMMUNICATIONS........................................
... B 3/4 9 3/4.9.6 FUEL HANDLING EQUIPMENT................................... B 3/4 9-1 4
}
CLINTON UNIT 1 xx
m , m "
, :. . ,- s ' ' ,.
.s.
~
- t.
< LS.89 006.
Page 24 of 127 l :. insert for nana xx X- :3/4.7.7' LIQUID STORAGE TANKS. ............... ... ........ B 3/4 7 3' a .3/4.7.8 MAIN CONDENSER OFFCAS MONITORING s Offgas .' Explosive. Gas Nixture ................. B 3/4 7 3-
.: s - Offgas,- Noble Gas Radioactivity Rate .......... B-3/4 7-4.L s
L , e l :' ' , d a!
, ~
t L,
.I
- i. . , ;
. .{
.( q
't u .
3 3
'W
),
t q 4
-t
-j
< 1 r
. s i
- 1 I
I r i 1 5 l -. l- . l, - l . 1:
'i ' l j.r! f RFP2:GSL8-
F. _- LS-89-006 --- t
- Pass 25 of 127 INDEX 3
BASES , I PAGE SECTION j i , REFUELING OPERATIONS (Continued) , i I 3/4.9.7 CRANE TRAVEL - SPENT AND NEW FUEL STORAGE AND UPPER B 3/4 9-2 CONTAINMENT FUEL P00LS.................................... 3/4.9.8 WATER LEVEL - REACTOR VESSEL and WATER and LEVEL - SPENT FUEL STORAGE AND UPPER CONTAINMENT 3/4.9.9 FUEL P00LS................................................ B 3/4 9-2 l 3/4.9.10 CONTROL ROD REM 0 VAL....................................... B 3/4 9-2 3/4.9.11 RESIOVAL HEAT REMOVAL AND COOLANT CIRCULATION. . . . . . . . . . . . . B 3/4 9-2 3/4.9.12 INCLINED FUEL TRANSFER SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIKARY CONTAINMENT INTEGRITY /0RYWELL INTEGRITY........... B 3/4 10-1 I j 3/4.10.2 ROD PATTERN CONTROL SYSTEM................'...............
. B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS............................ B 3/4 10-1
! 3/4.10.4 RECIRCULATION L00PS....................................
.. B 3/4 10-1 j
3/4.10.5 T RAI NING ST ARTU P S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4
~ ~'
10-1 I 3/4.10.6 SPECIAL INSTRUMENTATION - INITIAL CORE LOADING............ B3/410-5
--s L-I
/ 3/4.11 RADI0 ACTIVE EFFLUENTS
,3/4.11.1 LIQUID EFFLUENTS Concentration............................................. B 3/4 11-1 l
t 0ose...................................................... B 3/4 11-1 Liquid Radwaste Treatment System.......................... B 3/4 11-2 Liquid Holdup Tanks......................................, B 3/4 11-2 3/4.11.2 GASEOUS EFFLUENTS . Dose Rate................................................. B 3/4 11-3 , Dose - Noble Gases........................................ B 3/4 11-3 l-4 i Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides l in Particulate Form....................................... B 3/4 11-4 } CLINTON - UNIT 1 xxi {
p; s o i h LS-89.006 { f- . Pogs 26 of-127 j i i
)
L . INDEX . BASES , i SECTION PAGE IRADI0ACTIVEEFFLUENTS(Continued) . ; Gaseous Radwaste Treatment System and Ventilation Exhaust Treatment System...................... B 3/4 11-5 , Explosive Gas Mixture..................................... B 3/4 11-5 .; Main Condenser............................................ B 3/4 11-5 3/4;11.3 SOLIO RADICACTIVE WASTE................................... B 3/4 11-6 3/4.11.4 TOTAL 00SE................................................ B 3/4 11-6 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM........................................ B 3/4 12-1
< 3/4.12.2 LAND USE CENSUS...........................................- .
B 3/4 12-1 : 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM........................ B 3/4 12-2 1 l 5.0 DESIGN FEATURES- t 5.1 SITE l Exclur. ion Area................................................. 5-1 u l Low Fopul ati on Zo ne . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 t Map Defining Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents....................... 5-1 5.2 CONTAINMENT l Configuration.................................................. 5-1 l Design Temperature and Pressure................................ 5-1 L Figure.5.1.1-1 Ex c l u s i o n A re a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-2 FICure 5.1.2-1 Low Population Zone................................. 5-3 , L Figure 5.1.3-1 Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Ef fluents. . . . . . . . . . . . . . . . . . 5-4 Seco nda ry C ontai nment. . . . . . . . . . . . . . . : . . . . . . . . . . . . . . . . . . . . . . . . . . 5-5 CLINTON - UNIT 1 xxii
~ --
e , - - -. . - - .
1 I k LS-89-006 ;
~
Peg 2 27 oY~127- i l i I l 1 1 3
- INDEX' 'O ADMINISTRATIVE CONTROLS PAGE SECTION l REPORTING REQUIREMENTS (Continued) -
i' . f 6.9.2 SPECIAL REP 0RTS.............................................. 6-21 6 10 RECORD RETENTION.............................................. 6-21
, i i 6 11' RADI ATION PROTECTION PR0 GRAM. . . . . . . ... . . . . . . . . . . . . . . . . . . . . . . . . . 6-23 :
.)
6-23 !
, 6.12' NIGH RADIATION AREA...........................................
, i l 6.13 PROCESS CONTROL PROGRAM (PCP). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-24 6.14 0FFSITE' DOSE CALCULATION MANUAL (00CM)........................ 6-25 1
p : l 6.15 - MAJOR CHANGES TO RADI0 ACTIVE LIQUID. GASEOUS. AND SOLID '
. WASTE TREATMENT SYSTEM 5....................................... 6-25 -
l -. -.
'1 e
4 I CLINTON - UNIT 1 xxvi
c LS-89-006 Page 28 of.127 l t DEFINITIONS FREQUENCY NOTATION 1.17 The FREQUENCY NOTATION specified for the performance of surveillance I requirements shall correspond to the intervals defined in Table 1.1. i h ASEOUS RADWASTE TREATMENT SYSTEM ( 1.18AGASEOUSRADWASTETREATMENTSYSTEMisanysystemdesignedandinstalled3 ) to reduce radioactive gaseous effluents by collecting primary coolant system \ l offgases from the main condenser evacuation system and providing for delay or l holdupforthepurposeofreducingthetotalradioactivitypriortoreleaseto 1 ( the environment.J l 1.16 [CELETE C3 IDENTIFIED LEAKAGE , 1.19 IDENTIFIED LEAKAGE shall be:
- a. Leakage into collection systems, such as pump seal or valve packing leaks, that is captured and conducted to a sump or collecting tank or
- b. Leakage into the drywell atmosphere from sources that are both specifically located and known either not to interfere with t,he operation of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.
LIMITING CONTROL ROD PATTERN l 1.20 A LIMITING CONTROL ROD PATTERN shall be a pattern which results in the l core being on a thermal hydraulic limit, i.e., operating on a limiting value for APLHGR, LHGR, or MCPR. LINEAR HEAT GENERATION RATE l 1.21 LINEAR HEAT GENERATION RATE (LHGR) shall be the heat generation per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length. LOGIC SYSTEM FUNCTIONAL TEST 1.22 A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components, i.e., all relays and contacts,.all trip units, solid state logic elements, etc., of a logic circuit from sensor through and including the actuated device to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be per-formed by any series of sequential, overlapping or total system steps such that the entire logic system is tested. MAXIMUM FRACTION OF LIMITING POWER DENSITY 1.23 The MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD) shall be the highest value of the FLPD which exists in the core. - MEMBER (S) Of THE PUBLIC 1.24 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors or vendors. Also excluded from this category are CLINTON - UNIT 1 1-4
L I I' LS-89-006 i Pega 29 of 127 , I l DEFINITIONS MEMBER (S) 0F THE PUBLIC (Continued) persons who enter the site to service equipment or to make deliveries. This ; category does include persons who use portions of the site for recreational, l occupational or other purposes not associated with the plant. MINIMUM CRITICAL POWER RATIO 1.25 The 11NIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the core. F 0FFSITEDOSECALCULATIONMANUAL(ODCM1 V J t 1.26 The OFFSITE DOSE CALCULATION MANUAL shall contain the current methodology _7 i and parameters used in the calculation of offsite doses due to radioactive : gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the environmental tradioloaical monitoring program. OPERABLE - OPERABILITY 1.27 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when ' all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for ' the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s). OPERATIONAL CONDITION - CONDITION 1.28 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive com-bination of mode switch position and average reactor coolant temperature as specified in Table 1.2. PHYSICS TESTS 1.29 PHYSICS TESTS shall be those tests performed to measure the fundamental , nuclear characteristics of the reactor core and related instrumentation as 1) described in Chapter 14 of the FSAR, 2) as authorized under the, provisions of - 10 CFR 50.59, or 3) as otherwise approved by the Commission. PRESSURE BOUNDARY LEAKAGE 1.30 PRESSURE BOUNDARY LEAKAGE shall be leakage through a nonisolable fault in a reactor coolant system component body, pipe wall or vessel wall. , PRIMARY CONTAINMENT INTEGRITY 1.31 PRIMARY CONTAINMENT INTEGRITY shall exist when: .
- a. All containment penetrations required to be closed during accident condi-tions are either:
- 1. Capable of being closed by an OPERABLE containment automatic isolation system or
- 2. Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except as provided
.f ,
in Table 3.6.4-1 of Specification 3.6.4. CLINTON - UNIT 1 1-5
LS.89 006 Page 30 of 127 : Insert for page 1-5 , i-OPESITE DOSE CALCULATION MANUAL (ODCM) 1.26 The OFFSITE DOSE CALCULATION WSUAL (ODCM) shall contain the
, methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the
. calculation of gaseous and liquid effluent monitoring Marm/ Trip ,
Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive , Effluent Controls and Radiological Environmental Monitoring Programs i
; required by Section 6.8.4 and (2) descriptions of the information that ;
should be included in the Annual Radiological Environmental Operating i and Semiannual Radicactive Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.7. a I I-T l l l l b RFP1:CSL2
c c LS-89-006' c Paga 31 of 127
- DEFINITIONS SHUTOOWN MARGIN i 1.40 SHUTDOWN MARGIN shall be the amount of reactivity by which the reactor is :
suberitical or would be subcritical assuming all control rods are fully inserted, i except.for the single control rod of highest reactivity worth, which is assumed
- to be fully withdrawn, and the reactor is in the shutdown condition; cold, i.e.,
68'F; and xenon-free. SITE BOUNDARY 1,41 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. kIDIFICATIO p 1.42 SOLIDIFICATION shall be the conversion of wet wastes into a form tha meets shipping and burial ground requirements.f t, +2. c or Lt.rco) SOURCE CHtcK p 1.43 A SOURCE CHECK shall be the qualitative assessment of channel response s I
,'when the channel sensor is exposed to a source of increased radioactivity. l
'1+3CDr.Lcreo] w STAGGERED TEST BASIS '
1.44 A STAGGERED TEST BASIS shall consist of:
- a. A test' schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal L subintervals. ,
l- b. The testing of one system, subsystem, train or other designated component - L at the beginning of each subinterval. THERMAL POWER 1.45 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. TURBINE BYPASS SYSTEM RESPONSE TIME, ! 1.46 The TURBINE BYPASS SYSTEM RESPONSE TIME consists of two separate time intervals: a) time from initial movement of the main turbine stop valve or i i control valve until 80% of turbine bypass capacity is established, and b) the - time from initial movement of the main turbine stop valve or control valve until; initial movement of the turbine bypass valve. Either response time may l; be measured by any series of sequential, overlapping, or tutal steps such that the entire response time is measured. UNIDENTIFIED LEAKAGE 1,47 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE. l h. ' 4' CLINTON - UNIT 1 1-8
~
e. LS-89-006-Pagn 32 of 127 : DEFINITIONS-UNRESTRICTED AREA 1.48 An UNRESTRICTED AREA shall be any area at or beyond the SITE B0UNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residen,tial quarters or for industrial, l commercial, institutional, and/or recreational purposes. ; f'VENTILATIONEXHAUSTTREATMENTSYSTEM \u ps-1,49 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers
.and/or HEPA filters for the purpose of removing fodines or particulates from the l' gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety ,
Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION t EXHAUST TREATMENT SYSTEM components. , > L49 Cos.t.srco] VENTING 1.50 VENTING is the controlled process of discharging air or gas from a con-finement to maintain temperature, pressure, humidity, concentration or other operating' condition, in such a manner that replacement air or gas is not pro-- , vided or required during VENTING. Vent, used in system names, does not imply a VENTING procers. e 9 f. CLINTON - UNIT 1 1-9
e l R _:... Page 33 of 127 !
- INSTRUMENTATION ,
3/4.3.7 MONITbRINGINSTRUMENTATION RADIATION MONITORING INSTRUMENTATION L
" LIMITING CONDITION FOR OPERATION 3.3.7.1 The radiation monitoring instrumentation channels shown in Table 3.3.7.1-1 shall Le OPERABLE, with their alarm / trip setpoints within the specified limits, w..
APPLICABILITY: As shown in Table 3.3.7.1-1. ACTION: With a radiation monitoring instrumentation channel alarm / trip setpoint
, a.
exceeding the value shown in Table 3.3.7.1-1, adjust the setpoint to within the limit within 4 hours or declare the channel inoperable,
- b. With one or more radiation monitoring channels inoperable, take the ACTION required by Table 3.3.7.1-1. _
. c. The provisions of Specificat% ns 3.0.3 and 3.0.4 are not applicable.
i SURVEILLANCE REQUIREMENTS
'4.3.7.1' Each of the above required radiation monitoring instrumentation
' channels shall be deqLonstrated OPERABLE by the performance-of the CHANNEL CHECK,050VRCE CHECK.TCHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations l for the conditions lind at the frequencies shown in Table 4.3.7.1-1. ,
l _.
- l. .
l s, F e i , i . CLINTON - UNIT 1 3/4 3-70
i II Eh .
~
. : N-
- 9 ~
-TABLE 3.3.7.1-1 L
P E- RADIATION MONITORING INSTRUMENTATION 3
- ALARM / TRIP MINIMUM CHANNELS APPLICABLE CONDITIONS SETPOINT~ ~ ' ACTION .
INSTRUMENTATION OPERABLE' -
% 1. Main Control Room 2/ intake (a) 1,'2, 3, 5,-and *' $ 10 mR/hr 701 e ' Air Intake Radiation Monitor
- 2. Area Monitors
# 71
- a. New Fuel l' $ 2.5 mR/hr**
Storage Vault
## 71
- b. Spent Fuel' I -$ 2.5 mR/hr**
Storage Pool At all times .71 R c. Control Room. 1 5 2.5 mR/hr** Direct Radiation Monitor Z Pre-treatment Off gas ID) *** -< 50 pCi/cc**,t 72
- 3. I 52.__
PRM - Noble Gas Activity Monitor
- 4. Post-treatment Off gas PRM 1(b) *** ~< 7.06 pCi/cctt 73
- a. High-Range Noble Gas Activity Monitor
- Providing Alarm and Automatic Termina-tion of Release 74 e e.
- b. Effluent System Flow-Rate Measuring I- *** 'NA I j";
Device , ,y 1 *** - NA 74 *8'
- c. Sample Flow Rate E*
Measuring De C
~
.9-
LS-89-006-Paga 35 of 127 TABLE 3.3.7.1-1-(Continue'd) l . RADIATION MONITORING INSTRUMENTATION TABLE NOTATIONS When irradiated fuel is being handled in the secondary containment.
** Alarm oniv.
h"* During operation of the main condenser air ejecto
# With fuel in the new fuel storage vault.
'## .With irradiated fuel in the spent fuel storage pool, t Reactivity concentration expected at the monitor location is a noble gas Y mix with a 2.9 minute decay.
tt
-( gas mix released from the off-gas treatment system.Radioactivityconcentrationexpecte (a) A channel may be placed in an inoperable status for up to 6 hours for re-quired surveillance without placing the trip system in the tripped condi-tion provided.at least one other OPERABLE channel in the same trip system is monitoring that parameter.
(b) Channel OPERABILITY shall include the capability of either the Main Control Room Central Control Terminal (MCR-CCT) or the Radiation Protection Office Central Control Terminal (RP-CCT) to provide the alarm status of the applicable radiation monitor channel (s).~ - ACTION , ACTION 70 - a. With.one of the required monitors inoperable, place the inoperable channel in the tripped conditjon within 1 hour; restore the inoperable channel to OPERABLE status within 7 days, or, within the next 6 hours, initiate and maintain operation of the control room emergency filtration system in the high radiation mode of operation,
- b. With both of the required monitors inoperable, initiate and maintain operation of the control room emergency filtration system in the high radiation mode of operation within 1 hour.
ACTION 71 - With the required monitor inoperable, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours. , ACTION 72 - a. With both the MCR-CCT and RP-CCT inoperable,
- 1. Perform a CHANNEL CHECK using local monitor indication within 8 hours and at least once per 8 hours thereafter, and
- 2. Restore the MCR-CCT or RP-CCT to OPERABLE status for the applicable channel (s) within the next 30 days, and if unsuccessful, prepare and' submit a Special Report pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the CCT failure or malfunction and the action taken to restore the inoperable equipment to OPERABLE status.
CLINTON - UNIT 1 3/4 3-72
e LS-89-006 L , . Pcg3 36 tf 127: t , (: - - TABLE 3. 3. 7.-1-l ' (Con tinued) RADIATION MONITORING INSTRUMENTATION L, TABLE NOTATIONS
- b. With the Pre-treatment Off gas PRM - Noble Gas Activity ,
j Monitor otherwise inoperable, gases from the main h condenser off gas treatment system may be released to the environment provided:
- 1. The off gas treatment system is not bypassed, ana
~ 2. The post . treatment air ejector off gas PRM high range M noble gas activity monitor is OPERABLE, or the provisions of ACTION 73-b are 'in effect, and
- l. 3. Grab- samples are taken at least once per 8 hours and
,._ analyzed for gross noble gas activity within 4 hours. { b . ACTION 73 - a. With both the MCR-CCT and RP-CCT inoperable,
- 1. Perform a CHANNEL CHECK using local monitor g' indication within 8 hours and at least once per 8 hours thereafter, and -
- 2. Restore.the MCR-CCT or RP-CCT to OPERABLE status for t.he - sopi f cacia chsnno!(s) wi thhi the aer; 30 days, y and ar. sue:assi;.1, p"oparc :.nd ;2.mi'. ; fpcci21 Report pursuant to Specification 6.9.2 within the next'10 days. outlining the cause of the CCT failure or malfunction and the action taken' to restore the-
. inoperable equipment to OPERABLE status,
- b. With the Post. treatment Off gas PRM High Range Noble Gas
-Activity-Monitor otherwise. inoperable, effluent releases-via this pathway may continue provided grab ' samples are taken at least once per 8 hours'and analyzed for gross ~
noble gas activity within 24 hours. ACTION 74 - With the number of channels OPERABLE less than required by*the Minimum Channels OPERABLE requirement, effluent releases via this pathway-may continue provided the flow rato is estimated at least--once per 8 hours. t
~ D e.\ d c s e e- P%'-
74
- CLINTON - UNIT 1 3/4 3-72a
l 4 Y
$ TABLE 4.3.7.1-1 y RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS-
,E
' CHANNEL-SOURCE FUNCTIONAL CHANNEL- .
CHANNEL E TEST CALIBRATION APPLICABILITY Z INSTRUMENTATION CHECK CHECKf- ' R :1,.2, 3,'5, and *
" S NA H
-1. Main Control Room Air Intake Radiation Monitor
- 2. Area Monitors NA M .R
- a. New Fuel Storage S
-Vault NA M R w b. Spent Fuel Storage S A Pool NA M R At all--times Control Room D'irect S c. " Radiation Monitor Pre-Treatment-Off gas PRM- D(3) M Q(1) R(2)..
3. Noble Gas Activity Monitor
- 4. Post-Treatment Off gas PRM D(3) D Q(1) R(2)t I a. High Range Noble Gas Activity Monitor Provid-ing Alarm and Automatic Termination of Release NA. Q R
- b. Effluent System Flow- D Rate Measuring Device
[aah, { HA Q R
** v?~
- c. Sample Flow-Rate D .y Measuring Device G
s m__ _ _ _
O l'J , s LS-89-006 Paga 38 of 127 TABLE 4.3.7.1-1 (Continued) RADIATION M0t,{ITORING INSTRUMENTATION SURVEILLANCE RE0VIREMENTS TABLE NOTATION
*When irradiated fuel is being handled in the secondary containment.
h*Duringoperationofmaincondenserairejector
#With fuel in the new fuel storage vault.
.##With irradiated' fuel in the spent fuel storage pool. '-
- 9. ,
J. tAutomatic isolation of valve IN66-F060 shall be demonstrated during the
? CHANNEL CALIBRATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that the MCR-CCT or i RP-CCT responds with annun_ciation and event printout to each of the following conditions:
- 1. Instrument indicates measured levels above the alarm / trip (HIGH) setpoint.
- 2. Detector failure (LOW FAIL, HI FAIL).
- 3. Sample flow failure (EXTERNAL FAIL).
l 4. Instrument not set-in normal operate mode (UNINITIALIZED, CALIBRATE, MAINTENANCE, or STANDBY). 1 (2) -The initial CHANNEL CALIBRATION 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 measure-ment assurance activities with NBS. These standards shall permit calibrat-ing the system over its intended energy range and measurement range. Subsequent CHANNEL CALIBRATION shall be performed using the initial radio-active standards or other standards of equivalent quality or radioactive sources that have been related to the initial calibration. (3) 'The CHANNEL CHECK shall. also determine that channel communication is established to the MCR-CCT or RP-CCT. CLINTON - UNIT 1 3/4 3-74
i l LS-89-006 f Page 39 of 127 j
- e ~
DELETE (IN$iRUMENTATION N
, RAD 10 ACTIVE L10UiO EFFLUENT MON!TORING INSTRUMENT ATION TEXT
. (To BE MPLACgg)
LIMITING CONDITION FOR OPERATION , v ^ 3.3.7.11 The radioactive liquid ef fluent monitoring instrumentation channels shown in Table 3.3.7.11 1 shall be OPERABLE with their alarm / trip setpoints set I to ensure that the limits of Specification 3.11.1.1 are not exceeded. The M MD46 1 alarm / trip setpoints of these channels shall be determined anc adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION OF 12*1 MANUAL (00CM). ADPLICABILITY: During releases via this pathway. ACTION:
- a. Vith a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specifi-
' cation, without delay suspend the release of radioactive liquid effluents monitered by the af f ected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
- b. Vith less than the minimum number of radioactive liquid ef fluent monitoring instrumentation-channels OPERABLE, take the ACTION shewn'in Table 3.3.7.11-1.
= Restore the inoperable in's'truments to OPERABLE status witnin 30 days and, if unsuccessful, explain in the next Semiannual Radica:tive Effluent Release Report why the inoperability was not correctec in a timely manner.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
~
SURVEILLENCE RE00!REMENTS 4.3.7.11 Each radioactive licuid effluent monitoring instrumentat. ion channel shall be demonstrr.ted OPERABLE by performance of the CHANNEL CHECK, SOURCI
- CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the f reRuencies shown _in Table 4.3.7.11-1.
k 3/a 3-85 j C' !NTON - UNIT 1 ! 1
. ..y
- r A >,
l[n {)ejekt enOE t- P"SE- ! j- TABLE 3;3.7.11-1 + 2-o. 7 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION , E - ! U MINIMUM ' 2 w CHANNELS INSTRUMENT OPERABLE ACTION
~
l 1. RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC ~ TERMINATION OF' RELEASE
- a. Liquid Radwaste Discharge Process Radiation Monitor 1(8) 110
- 2. RADI0 ACTIVITY MONITORS PROVIDING ALARM BUT NOT.PROVIDING i
AUTOMATIC TERMINATION OF RELEASE s
- a. Plant' Service Water Effluent Process Radiation Monitor 1(a) 111
[
- b. Shutdown Service Water Effluent Process Radiation Monitor. 1/ Division *(a) yyy
- c. Fuel PooliHeat Exchanger Service Water Radiation Monitor 1(a) yyy
- 3. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent.Line 1 112
- b. Plant Service Water Effluent Line 1 112
- 4. TANK LEVEL INDICATING DEVICES
- a. Cycled Condensate Storage 1 -113 me
- b. Reactor Core Isolation Cooling Storage ~- 1 113-' {"4
.n?
.: .8?
CDivision I and Division II only. f
~. .J . . - . - . _ . . n.L.- '_~-:--.. .: - .i - - - . -
E LS-89-006 0 - ~ Pcg3 41 of 127
~
Dr.lah.tnWL P*$% ,
~ TABLE 3.3.7.11-1 (Continued)
. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION P TABLE NOTATION (a) Channel OPERABILITY shall include the capability of either the Main -
Control Room Central Control Terminal (MCR-CCT) or the Radiation Protectior.' Office Central Control Terminal (RP-CCT) to provide the alarm status of the applicable . radiation monitor channel (s). i. ACTION ACTION 110 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement,-effluent releases may continue via this pathway provided that prior to initiating a release: a, At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and
- b. At least two technically qualified members of the Facility -
Staff independently verify the release rate calculations < and discharge line valving: Otherwise, suspend release of radioactive effluents via this pathway.
-ACTION 111 - a. With both the MCR-CCT and RP-CCT' inoperable perfo' l CHANNEL CHECK using local monitor indication within 8 hours and at least once per 8 hours thereaf ter.
I b. With the monitor otherwise inoperable, effluent releases l via this pathway may continue provided that at least once j per 12 hours,' grab samples are collected and analyzed for radioactivity at a limit of detection of at least 10 7 pCi/ml. , ACTION 112 - With the number of channels OPERABLE less than required by the r Minimum Channels OPERABLE requirement, effluent releases via , this pathway may continue provided the-flow rate-is estimated' at least once per 4 hours during actual releases. Pump perfor-mance curves generated in place may be used.to estimate flow. 7
~ ACTION 113 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue provided the tank liquid level is estimated during all liquid additions to the tank.
CLINTON - UNIT 1 3/4 3-97
- )
I+. .s _ . .+: 2 - -
._ . . ~.. e
- p. , ._..
- f -
1-
~
._ ~ - -
[ o n r. De.1e.hc. e.nhrc. PWst- , . .
~
!' -TABLE 4.3.7.11-1 l.
'o i RADI0 ACTIVE LIQUID EFFLUENT MONITORING' INSTRUMENTATION SURVEILLANCE REQUIREMENTS l 'E CHANNEL H ~
!- CHANNEL SOURCE CHANNEL- FUNCTIONAL' ' ' H INSTRUMENT [ CHECK CHECK- - CALIBRATION ~ TEST 1 l 1. RADI0 ACTIVITY MONITORS PROVIDING' ALARM
, ALARM AND AUTOMATIC TERMINATION OF RELEASE l .
- a. Liquid Radwaste Discharge Process Radiation Monitor Ef fluent Line.
D(5)' P R(3) -Q(1)'
- 2. RADI0 ACTIVITY MONITORS PROVIDING ALARM BUT NOT
,, PROVIDING AUTOMATIC TERMINATION OF RELEASE .
s
- a. Plant Service Water Effluent Process 3 Radiation Monitor. D(5) M R(3) Q(2) cm
- b. Shutdown Service Water Effluent Process Radiation Monitor D(5) M R(3) -
Q(2)
- c. Fuel Pool Heat Exchanger Service Water Radiation Monitor D(5) H R(3) Q(2)
- 3. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line .D(4) NA >R Q.
- b. Plant Service Water Effluent Line D(4) NA R Q._
EG
% s,
#7 u g-
. ?., *
. ~
7
.u-- p e..r'+ 4 ga g .
-g '9 ,we.4 4 6p 4 % .w.r4 ge, y-^.yg9-,.g g- -w ig9..h g.9:.gv+-g, +-,pl-- g.++ >g
-- , - . . . , . . _ g. , m.
4
~;
-~- -
u-- ;,;-- - Delefe.'crtbre.:[*$e. . ,
'. IAnlE 4.3.7.ll-1 (Continued) -
5 . _ Q ~ ltAlll0ACIIV[.1II)llti) [IFillfili IWilll10lilllG IH51RtilifiliA110N SilRVEltl ANCE REQUIRfiltills _ i ..
- c. ~
'(llAHilEL 2
'l
' CllAHilLL - 50llRCE ' CllANNEL ' :flINCT10HAL j
f
"* ~ CilCCK -- CllECK CAtluRAllott 1E51 11:511111111ll[
- 4. I AttK ILVEL -IllillCAllHC ULVICES D* .NA R. IIA -
- a. Cycled Condensate Storage li . Neactor Core Isolation Cooling G* HA - R' flA 1" *During linguid additions to the tank. ~
s sos O [ _/ ~ J e e
'd g
ow a
~
~
a m-ww- .a- he% s -wem_e _ am.seww.-. _e-_w-e.J -em_~. mswo-mi.e..u-,6-.e_.a_A- - m--
LS-89-006= Pags 44 of 127'
' TABLE 4.3.7.11-1 (Continued) t RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION '
SURVEILLANCE REQUIREMENTS Dade. enbec P* W TABLE NOTATIONS (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs and that the MCR-CCT or RP-CCT provides annunciation,and event printout in response to each of the following s conditions: i
- 1. Instrument indicates measured levels above the alarm / trip (HIGH)
'se tpoi nt.
- 2. Detector failure (LOW FAIL, HI FAIL).
- 3. Sample flow failure (EXTERNAL FAIL).
- 4. Instrument not set in normal operate mode (UNINITIALIZED, CALIBRATE, MAINTENANCE, or STANDBY) *
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that the MCR-CCT or: L RP-CCT responds with annonciation and event printout to each of the following conditions: l
- 1. Instrument indicates measured levels above,the alarm (HIGH)
L setpoint.
- 2. Detector failure-(LOW FAIL, HI FAIL).~
- 3. Sample flow failure (EXTERNAL FAIL). ,
- 4. Instrument not set in normal operate mode (UNINITIALIZED, CALIBRATE, MAINTENANCE, or STANDBY).
i (3) The initial CHANNEL CALIBRATION shall be performed using one or more of b 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. These standards shall permit calibrating the system over its intended range of energy and measurement range.' For subsequent CHANNEL CALIBRATION, sources that have
- . been related to the initial calibration shall be used.
(4) CHANNEL- CHECK shall consist of verifying indication of flow during periods
-of release. CHANNEL CHECK shall be made at least once per 24 hours on day which continuous, periodic, or batch releases are made.
(5) The CHANNEL CHECK shall also determine that channel communication is established to the MCR-CCT or RP-CCT. l
*A demonstration of automatic isolation of the release pathway is not applicable to this condition.
CLINTON - UNIT 1 3/4 3-100 .
+
LS-89-006-
. Page 45 of 127 i
( _INSTRUWINTAi!ON ' RAD 1010ilVE GASIOUS EFFLUENT MONITORING INSTRUMENTATION
]
ESPI 4'f-
, ,otA LIMIT 1W3 CONDITION FOR OPERATION ~~
Tas<rt 3.3.7.12 The radioactive 3.3.7.12-1 gaseous effluent monitoring instrumentation channels shall be OPERABLE with their alare/ trip setpoints set shown in Table to ensure that the limits of Specification 3.11.2.1 and 3.11.2.6 are not exceeced. The alarm / trip setooints of these channels shall be determined and acjusted in accorda'ce with the methocology and parameters in the 00CM. ] APPLICABILITY: As shown in Table 3.3.7.12-1. ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentation channel alare/ trip setpoint less conse 'ative than required by the above Scecifi-cation, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, l- -
b. Vith less than the minimum number of radioactiv't gaseous ef fluent monitoring 3.3.7.12-1. instrumentation channels OPERABLE, take the ACTION shown in Table Restore the inoperable instrumentation to OPERA 3LE status within 30 days and, if unsuccessful, explain in the next Semiannual Racicactive Ef fluent Release Report pursuant Jo Specification 6.S.I.7,why this inoperability was not corrected in a timely canner.
- c. ihe provisions of Specifications 3.0.3 and 3.0.4 are not. applicable, L .
l SURVEILLANCE RIOUIREMENTS 4.3.7.12 Ea'ch radioactive gaseous ef fluent monitoring instrumentation channel shall be demonstratec OPERABLE by performanct of the CHANNEL CHECK, SOURCI CMICX, ' CHANNEL CAlliRATION and CHANNEL FUNCTIONAL T!37 operation,s at the frequencies
~
j
- snown in Tatie 4.3.7.12-1.
l' . l I 95 C'.INTON - UN*T 1 3/4 3 .01 1 1
.LS 89-006
- Page 46 of=127 Insert for vare 3/4 3 95 ,
INSTRUMENTATION - MAIN CONDENSER OFFCAS TREATMENT SYSTEM EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION
-3.3.7.11 At least one main condenser offgas treatment system explosive gas ,
monitoring instrumentation channel shall be OPERABLE with its alarm / trip setpoint set to ensure that the limits of Specification 3.7.8.1 are not exceeded. APPLICABILITY: . During operation of the main condenser air ejector, s 2 ACTION:
- a. With the explosive gas monitoring instrumentation channel alarm / trip setpoint less conservative than required by Specification 3.7.8.1, declare the channel inoperable and take the ACTION required below. ,
- b. With less.than 1 explosive gas monitoring instrumentation channel
- OPERABLE, operation of the main condenser offgas treatment system !
may continue provided grab samples are collected at least once per 4 hours and analyzed within the following 4 hours. Restore the inoperable channel-to OPERABLE status within 30 days and, if g unsuccessful, prepare and submit a Special Report to the l Commission pursuant to' Specification 6.9.2 to explain why this L inoperability was not corrected in a timely manner.
- c. The provisions of- Specification 3.0.3 and 3.0.4 are not applicable.
SURVETLLANCE REOUIREMENTS l 4 3.7.11 The explosive gas monitoring instrumentation channel (s).shall be [ demonstrated OPERABLE by performance of. a CHANNEL CHECK at least once per 24 L hours, a CHANNEL CALIBRATION
- at least once per 92 days and a CHANNEL FUNCTIONAL TEST'at.least once per 31 days.
l'-
*The CHANNEL CALIBRATION shall include the use of standard samples containing
-a nominal:
- 1. 1.0 vol. % hydrogen, balance nitrogen, and 2, 4.0 vol. % hydrogen, balance nitrogen.
RFP2:CSL8
, * , , .- - t :.:' . vp . c + ~y:m' c
~
.n g ; efgje, ., page. .-. ? TABLE 3.3.7.12-1 '
( ERADI0 ACTIVE GASEOUS EFFLUENT MONITORING: INSTRUMENTATION O e MINIMUM E INSTRUMENT
# ~
~
CHANNELS OPERABLE APPLICABILITY ' ACTION-w 1. Station HVAC Exhaust PRM
- a. High-Range Noble Gas Activity '
1(a). 4- . 121 Monitor
- b. Low-Range Noble Gas Activity 1(")
- 121 Monitor
- c. Iodine Sampler- 1
- 122
{ d. Particulate Sampler 1 * - 122 y e. Sample Flow-Rate Measuring 1
- 123 g Device
- f. Effluent System Flow Rate 1
- 123 Measuring Device ,
- 2. Standby Gas Treatment System Exhaust PRM l a. High-Range Noble Gas 1(") **~ 121 Activity Monitor i b. Low-Range Noble Gas 1(a), ** 121
- Activity Monitor e7 C
- c. Deleted % 4, i
.. vi "8
O e t l 1 t _ ~
, . - . . . , , _e . , . - _ . _ .-~ . . . , . . . , . _ _ _ . ., .._..m -_ ..a
. . . .~ ~ ,
, , ~
. , .. q
'- gg~
~
-M
~
J, ,
~
'~ '
N L; /g;De.leJe ' enth pay..
. TABLE'3.'3.7.12-1 (Continued)-
L P ~
..E L RADI0 ACTIVE ~GASE0US-EFFLUENT-MONITORING INSTRUMENTATION. #
.g-u l z
'~
MINIMUM E- INSTRUMENT- CHANNELS 0PERABLE ~APPLICABILITYi ACTION A s 2. Standby Gas Treatment: System
~-Exhaust PRM (Continued) .
l d. Iodine'Sampier 1- ** 122
- e. Particulate Sampler 1 -** 122
- f. Sample Flow-Rate Measuring- 1 ** '123 Device R
- g. Effluent System Flow-Rate 1 ** 123
, Measuring Device 8
- 3. Main Condenser Off gas Treatment System Explosive Gas Monitoring System
- a. Ilydrogen Monitor 1 *** 124
% 4,
.n i ag
- o. .
O
~
._..:.__..__.n.n___.1._1 '
_.._i._ _ . . . _ . _
~ < ,
' LS-89-006 :
Pcco 49 of 127 ; pc,tde enbre,pqc.; u - TABLEV3.3.7.12-1 (Continued) [: .;
'RADIDACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATIONS AU all times. ;
**~ .During standby gas treatment system operation.
^^*' Ob ,, operation of the main condenser air ejec' tor.
# A channel may.be placed in an-inoperable status:for up to 1 hour for the :
purpose of performing surveillances. >
. (a) Channel OPERABILITY shall-include the capability'of either the Main Control- Room Central Control Terminal (MCR-CCT) or the Radiation Protection Office Central Control Terminal .(RP-CCT) to provide the alarm-status of the applicable; radiation monitor channel (s).
l ACTION > E ' With both the MCR-CCT and RP-CCT inoperable, perform a' ACTION 121 - a. < CHANNEL CHECK using local monitor indication within 8 hours ., l ,
'and at'least once per 8 hours thereafter.
L b. With the noble gas activity monitor channel (s).otherwise- , inoperable, effluent releases via this pathway may 4
- continue.provided grab' samples are taken at least once per l -8 hours and analyzed for gross noble gas activity within 24-hours.
ACTION.122 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via . this pathway may continue provided that, within 4 hours after i the channel has been declared inoperable, samples- are contin-uously collected with auxiliary sampling equipment as required in Table 4.11.2-1. ACTION 123 - With the number of channels OPERABLE less than required by the 4 Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at
.least once per 4 hours.
. ACTION 124 -' With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the main condenser off gas treatment system may continpe provided grab i ,
samples are collected at least once per 4 hours and analyzed within the following 4 hours. ;
-ACTION 125 - Deleted ACTION 126-- -With the number of channels OPERABLE less than required by the y Minimum Channels OPERABLE requirement, suspend release of radio- f I activity effluents via this pathway.
CLINTON - UNIT 1 3/4 3-104 J
zw. - n m .
~
DELETE ? ECTidE' PAGE
' TABLE 4.3.7.12-1 :
RADI0 ACTIVE-GASEOUS EFFLUENT' MONITORING ^ INSTRUMENTATION SURVEILLANCE REQUIREMENTS' - z - t CHANNEL ~ E' ' CHANNEL' -SOURCE. CHANNEL . FUNCTIONAL
~ INSTRUMENT CHECK CHECK CALIBRATION TEST' . APPLICABILITY ~..
f
- 1. Station HVAC Exhaust PRM -
- a. High-Range Noble Gas Activity D(4)~ M R(2). *-
-Q(1)-
Monitor
- b. Low-Range Neble Gas Activity
~
D(4) M R(2') Q(1)
- Monitor
- c. Iodine Sampler W NA NA ~NA- *
- d. Particulate Sampler W NA NA- NA
- y
~
- e. Sample Flow Rate Measuring Device D NA R
- Q
- f. Effluent System Flow Rate Measuring D NA R Q
, Device
- 2. Standby Gas Treatment System Exhaust PRM-
- a. High-Range Noble. Gas Activity Monitor D(4) NA **
R(2) Q(1)
- b. Low-Range Noble Gas Activity Monitor D(4)- M **
R(2) Q(1)
- c. Deleted
- d. Iodine Sampler W NA NA ~NA
- e. Particulate Sampler. W NA NA NA **
$. y$
E; & o8 r~
, ~ . - i........ ., , . , . , , , ,, , -Lr, . , _ , _ . . - . . . . . . . . ,-. . _ . - . .
; u, n r
~
s .;; ; :=_'-
.~.
37 33
. -- ..g ;. ,
,~
.O Dele.te. cnti' e-' 7"Se -
.rAlitr-4.3.7.i2-1 (cont lin.eill-C. ItAllI0ACIIVf- GA5E0tts Ef fitilllT H0til10 RING Itt51RIN1[HTAi!0ft StfRVEll.l ANCE RfQtilRittfHIS
- A .
.R CllAllt#[L- ~
E~ CIIAt#HEL SOURCE- Cil4 fill [L - FullCllollAL .
' Clif CK CAllDRAllON 1[51 APPLICAlllllIY EllECK c III51Rtuli tti
.s.
_x . ~ d
- 2. St aeuttiy Gas T reatment System Extianst PHil- ;
" (Cont.iniscal) ;
aa-D NA R q
- f. Sample f! cst-Itake Heasuring Device HA R q I Etfluent System Iloe Rate Heasuring
~
D g. Ilevice f .
- 3. Itain Constenser Off gas Treatment. ~
System Explosive Gas Honitoring System *** .. HA Q(3) H
.O
- a. flystrogen Honitor
't *'.
4 4 4 g . k l *u t~ 2 m
. 90 e f f3 CD 3
Vi e ,
- e-* O '
o I O - cb I - s w { N
.u n
l l - C.7
- . _ _ . . . , . . . . , . _ _..-_._w.. _ - . . , , . _ , . . . , , , . . _ _ _ , , _ , . ~Y . ~ _J. , , _ . ,
?
;- ~
n p , j LS-89-006~ p Pegs 52'of 127- ' h[ ' ' j Aleke edtrc.' Pasc. TABLE 4. 3.7.12-1 (Continued) j [R L RADIDACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS : 2
- ., 1 g , TABLE' NOTATIONS
]
*' At all times, i i,
i
** 1During operation of the standby gas treatment system. r
***: .During; operation of the main condenser air ejector.
' (1).1The CHANNEL FUNCTIONAL TEST shall also demonstrate that the.MCR-CCT or
'RP-LCT: responds with~ annunciation and event printout to each of the f011owing conditions:'
- 1. Instrument indicates: measured levels above the alarm (HIGH) setpoint.
.p
, 2. Detector failure (LOW FAIL, HI FAIL).
- 3. Sample flow failure (EXTERNAL FAIL).
-4. Instrument not set in normal operate mode (UNINITIALIZED, CALIBRATE,
- . MAINTENANCE, or STANDBY). ,
(2);...The: initial CHANNEL CALIBRATION shall be performed using one or more of the reference' standards certified by theLNational- Bureau of Standards or usi_ng ,
- standards;that have been obtained from suppliers that participate in measure-l
-ment' assurance activities with-NBS.. These standards shall permit calibrat- *
, ing the system over its intended range of: energy and measurement range. t Subsequent CHANNEL CALIBRATION shall be performed using thelinitial radio-
' active standards or other standards of equivalent-quality or radioactive. !
'so'u rces that have been related'to the initial calibration.
~
L l .(3) .The' CHANNEL CALIBRATION shall include the.use of standard samples contain- $ r" ing a nominal:
- 1. 1.0.vol. % hydrogen, . balance . nitrogen, and >
L
'2.: 4.0 vol. % hydrogen, balance. nitrogen.
i: H (4)ThesCHANNEL CHECK shall also determine that channel communication is E established to the MCR-CCT or RP-CCT. ' " [. I lJ .
?CLINTON UNIT 1 3/4 3-107
.: o
, -- LS-89-006 Pagd 53 of-127 O ,
p 4 I l l 4 t IN57%'u!NT ai10NV 4 3/L 3.8 TUREINE OVE* SPEED FR0i!CTION SY$i!M Llu.1 TING CON 01710N FOR;.0PERATION 3.3.8' At least one turbine overspeed protection system shall b'e OPE'RABLE. AsDLICA51LITY: OPERAi10HAL CONDITIOH$ 1 and 2. ACTION: 4. With one turbine control valve, one turbine stop valve and/or with one turbine comcined intermediate valve inoperable, restore the inoperable valve (s) to OPERABLE in the affected steam lead orstatus isolatewithin 72 hours the turbine from theor steam close supply at least one valve within the next 6 hours,
- b. Vith the above required turbine overspeed protection system otherwise inoperable, within 6 hours isolate the turbine from the steam supply.
- c. The provisions of Specification 3.0.4 are not applicable for entry into DPERATIONAL CON 0li10H 2 provided the turbine is tripped and the turbine is isolated from the main steam supply by closed turbine stop and control
.' valves. , ,
SURv!!LLANCE REOUIREMENTS 4.3.8.1' The provisions of Specification 4.0.4 are not applicable. 4.3.8.2 The above required turbine overspeed protection system shall be ' ' cemenstrated OPERABLI:
- a. At least once per 7 cays by cycling each 'of the following valves from the running position and observing valve closure:
- 1. Four low pressure turbine combined intermediate valves, and i
- 2. Four high pressure turbir.e stop valves.
j_
' '- At .least once per 31 days by cycling each of the four high pressure turbine -
control valves from the running position and observing valve,closurt. g
- c. At least once per 18 months by performance of a CHANNEL CALI5 RAT 10H of the tuttine overspeed protection instrumentation, i
- c. At least cr :. per 40 months by disassembling at least one of 'each of the
'! above valves anc performing a visual and surface inspection of all valve a seats, cisks and stems and verifying ho unacceptable flaws or excessive corrosion. If unacceptacle flaws or excessive corrosion are found, all other valves of that type shall be inspected.
6 34
I c. LS-89-006 > Pago 54-of 127 ] j
^
j
; INSTRUMENTATION 3/4.3.9 PLANT SYSTEMS ACTUATION INSTRUMENTATION i
LIMITING CONDITION FOR OPERATION
.l 13.3.9 J The plant systems actu'ation instrumentation channels shohn in'
' Table'3.3.9-1-shall be 0PERABLE-with their trip setpoints set consistent with
' the= values. shown in the. Trip Setpoint column of Table 3.3.9-2. j
; APPLICABILITY: As shown in Table 3.3.9-1.
s , ACTION:1
. a .. . 'With a'pignt' system actua' tion instrumen'tation channel trip setpoint less
,. conservative than the value shown in the Allowable Value column of' L Table 3.3.9-2, declare the channel inoperable and either place the L'
~-inoperable channel in the tripped condition until the channel is restored
'to OPERABLE status with its trip setpoint adjusted consistent.with the Trip Setpoint value, 'or declare the associated system / loop inoperable.
c b.- For the' containment. spray system:- 1, L 1. -With the. number'of OPERABLE channels less than required by the E , Minimum OPERABLE Channels-per containment spray loop requirement for
. ,one containment spray loop,, place at least one inoperable. channel in --
the tripped condition within 1 hour or declare.the associated loop inoperable.7 l
- 2. With the' number of-OPERABLE channels less than required by the l o Minimum OPERABLE Channels per containment spray loop requirement for l' both loops; declare the associated-loop inoperable. _, , , ,
l c.- For the feedwater system / main turbine trip system: . , 1.- With the number of OPERABLE channels one less than required by the , Minimum OPERABLE Channels, requirement, restore the inoperable channel
..to OPERABLE status within 7 days or be in at least STARTUP within the ' '
.next 6 hours.
~L
'2. With the number of OPERABLE channels two less than required by the 2 Minimum OPERABLE' Channels requirement, restore at-least one of~the inoperable channels to OPERABLE status within 72 hours or be in at ,
least STARTUP within the next 6 hours. d .' For'the suppre'ssion pool makeup system (SPMS) with the number of channels, one less than the minimum 0PERABLE Channels Requirement of Table 3.3.9-1 take.the ACTION required by Table 3.3.9-1. . f s --. - - 97 CLINTON -. UNIT 1 3/4 3 , 4 _-.'-_L.-__._--_-_-____.__-_----__.__---.__-_--.-_ -. --o---
LS-89-006' Page 55 of-127 INSTRUMENTATION ~ I PLANT SYSTEMS ACTUATION INSTRUMENTATION i, - I SURVEILLANCE REQUIREMENTS - 4.3.9.1 Each plant system actuation 'instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL-
.- TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the f requencies ~ shown _in Table 4.3.9.1-1.
4.3.9.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months. Each trip system or division of the plant system actuation logic associated with the Nuclear System Protection System shall be manually tested independent of the SELF TEST SYSTEM during separate refueling outages such l. that all divisions and all trip functions are tested at least once every four fuel cycles.* 4 4 i. [
- Manual testing for the purpose of satisfying Specification 4.3.9.2 is not
. required until after shutdown during the first regularly scheduled refueling '
.! outage.
.CLINTON -- UNIT 1 3/4 3 hP' l
~ ~ ~ A A1
.a: M9 , , :
TABLE 3' _: . ;: - _
- p PLANT SYSTEMS ACTUATION INSTRUMENTATION' }
}2
. MINIMUM OPERABLE CHANNELS PER . APPLICABLE' i CONTAINMENT OPERATIONAL TRIP FUNCTION SPRAY LOOP CONDITIONS
-E-
~ .
-i 1. CONTAllmENT SPRAY SYSTEM- ,
e
- a. Drywell Pressure-High i 2* 1, 2,'3
- b. Containment Pressure-High . .
2* 1, 2, 3
- c. Reactor Vessel Water Level-Low Low Low,~ Level.1- 2* - 1,'2. 3 :
- d. . Timers
.(1) Loop A, Loop B (10 minutes)' 1 1, 2, 3 (2) Loop B only (90 seconds)- 1 - 1, 2,' 3
- e. Manual Initiation 1 1, 2," 3 V R MINIMUM OPERABLE
- CHANNELS w 2. FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM H
$ a. Reactor Vessel Water Level-High, Level 8 3* 1.
t MINIMUM GPERABLE
- 3. SUPPRESSION POOL MAKEUP SYSTEM CHANNELS PER TRIP SYSTEM ACTION
. - a. Drywell Pressure-High- 2* ' 1, 2, 3 50 l b. Reactor Vesse1~:Waier Level-Low Low Low, Level 1 2* . 1,2,3 50 ! c. Suppression Pool Water Level-Low Low. '2* - 1, . 2, ' 3 51 l d. Suppression Pool Makeup Timer 1 1, 2, 3 - 51
- e. SPMS Manual Initiation 2 1,2,3 '51
- f. SPMS Mode Switch Permissive 1 ' 1, 2, 3 -
51 i
*A channel may be placed in an inoperable status for up to 2 hours for required surveillance without
- placing the trip system in the tripped condition.provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.
m ta
; $. a, .
; o . -
.,e-
=
G
, , ,, - - ,. c. n, , , s.~.+ . e,- - - -, ..ae n. . . + - , -,v,..l. ,n.-~a.,l
w... . pl , .. ' ~ ' " LS-89-006
'*~ Pega 57 of.127 -i O -
TABLE 3.3.9-1 (Continued) ! PLANT SYSTEMS ACTUATION INSTRUMENTATION-ACTION ACTION 50 - With the number of OPERABLE channels less than, required by -l
- f. ;- the Minimum OPERABLE Channels per Trip System requirement:- ;
E a. For 1 trip system, place the inoperable channel (s) and/or that trip system in the tripped condition within one hour or declare the SPMS inoperable and take the action of .
.} '
. Specification 3.6.3.4.
.- [
t- ..b. For both trip systems, declare the SPMS inoperable and take the action of Specification 3.6.3.4.
~
ACTION 51 - With the number of OPERABLE channels less than required by . t the Minimum OPERABLE channels per Trip System requirement, declare the SPMS system inoperable and take the action of ,.
- Specification 3.6.3.4.
.I ' .
7 4 Ge t
-i k
. e J
q
? cLINTON - UNIT 1 3/4 3 l
. 1
m- ,
- .x.
~ '
~
~" '
TABLE 3.- '2 ~
- . n.
-, y .
'C- PLANT SYSTEMS ACTUATION INSTRUNENTATION SETPOINTS' ~
2
.i
- 1 g ,2.
.. . ALLOWABLEL c-. TRIP FUNCTION,- . TRIP SETPOINT VALUE -
z i 5 1. CONTAINMENT SPRAY SYSTEM'
- a. Drywell Pressure-High <~1.68 psig .: < 1.88 psig
- b. Containment: Pressure-High. 7 22.3 psia- 7 22.4 pria
- c. Reactor Vessel Water Level-Low Low Low, Level l' i-145.5 in.*
F-147.7 in.
- d. Timers
- 1. Loop'A, Loop B .10.17 min. > 10.10 < 10.23 min.-
- 2. . Loop B only J -< 90 sec.- :7 90.6 sec. ,
- 2. FEEDWATER SYSTEM / MAIN TURBINE-TRIP SYSTEM R a. Reactor Vessel Water Level-High, Level 8 5 52.0 in.* i 52.6 in.
- l.
- 3. SUPPRESSION POOL MAKEUP SYSTEM ;
1- __ ., s w-o. a. Drywell Pressure-High . 5 1.68 psig $ 1.88 psig
- b. Reactor Vessel Water level-Low Low Low, [
> -145.5 in.*
Level 1 . > -147.7'in. ' f c. Suppression Pool Water Level-Low Low > 37 9/16 in.** > 29 in.**'
- d. Suppression Pool Makeup Timer 1 25 minuter 1 30 minutes ,
- e. SPMS Manual Initiation MA NA , .
- f. SPMS Mode Switch Permissive NA . NA ,
*See Bases Figure B 3/4 3-1.
** Instrument zero is 727'-0" as1.
. . ~ gg
! %l 4,
. wi .
, .L
- 8 . !
k7
- i.
y
.-- - .. - .,-:,. . - ,- . . - - . . - - . . - . . . ~ . ~ .
- - w . - . w -
u . . . . _. ._
. . = , . . , _ _ , ,
, , ,p: n
. n:
. . ; e.
; ~ L, ,Lm
-2
.., .. a. ,
TABLE'4.3.9.1-1 3-
.o . .
C PLANT SYSTEMS ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS
'i 9 o -
z . 4
. CllANNEL .
OPERATIONAL-CHn.' c. --FUNCTIONAL' CHANNEL CONDITIONS IN MIICll. c 5 TRIP FUNCTION' CHECaC ~ -TEST CALIBRATION SURVEILLANCE REQUIRED
" 1. CONTAINMENT SPRAY SYSTEM Drywell Pressure-High 5 M 1, 2, 3' a.
- b. Containment' Pressure-High S' -.- M.
R((a) R ,) _ -- 1, 2, ~ 3
- c. Reactor Vessel Water: Level-Low .
R(,)
. Low Low, level l' ,
5 M 1. 2, 3
- d. Timers NA M R 1, 2,'3
- e. Manual Initiation' NA R NA 1, 2, 3
- 2. FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM .
- a. Reactor Vessel Water Level-High,.
Level 8 S M R 1
%0 3. SUPPRESSION P001 MAKEllP _
- a. Drywell Pressure-High S M RI *) 1, 2, 3
- b. Reactor Vessel Water Level - R(,)
Low Low Low, Level 1 S M 1,2,3
- c. ' Suppression Pool Water Level-tow Low 5 M .R(b) 1, 2, 3
- d. Suppression Pool Makeup Timer NA M Q , 1, 2, 3
- e. -SPMS Manual Initiation MA R NA 1,2,3 .
, g am
- f. SPMS Mode Switch Permissive "NA R NA 1, 2, 3 $5 J. 'F
*8
' (a) Calibrate the analog trip module at least once every.31 days. Qo 4
f ' ~ (b) Calibrate the analog comparitor unit at least once~every 31 days. g_
. ~
-w+ +m. . y .g .w-r - F g* 4- ed t r- Ps g,v'**a'
"%.- r p ='gi,, mw.-. f p,. q., , w., y w --g...ge.-e- %w,e,,,,.w ,, .wr. , , y w #.a ..,.maa .p.g.
LS-89-006 r Page 60 of 127 JNSTRUMENTATION , F - 3/4.3.10 NUCLEAR SYSTEM PRCTECTION SYSTEM - SELF TEST SYSTEM LIMITING CONDITION FOR OPERATION ,
-i 3.3.10 The SELF TEST SYSTEM (STS) of the Nuclear System Protection System
- . shall be OPEPABLE and operating in the fully automatic mode." .
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, and S. ACTION: e
- a. With the STS not operating in the fully automatic mode initiate corrective
- action within 24 hours to restore the STS to automatic operation for the maximum number of divisions available.
- b. If the STS is-not restored to fully automatic operation within 30 days, be in at least HOT SHUTDOWN within the next 12 hours and COLD SHUTDOWN within the following 24 hours.
- c. The provisions of Specification 3.0.4 are not applicable.
1' L , SURVEILLANCE REQUIREMENTS: . 4.3;10 Status indications of the STS shall be obtained at.least once per 24 hours, whenever. the STS is operating in the fully or partially automatic L mode. 4 b -. -. 1
- l. -
[ . l l' .*The STS may be parfodically taken out of the fully automatic mode of operation for up to 4 hours for the purpose of performing surveillance testing and pre- - ventative or correctiv>4 maintenance to satisfy technical specification requirements for those components the STS is designed to monitor. I CLINTON - UNIT 1 3/4 3 4 r - - - , ~ - - ., - , _ _ . _ __ -m_ ._- --_-_ _ M
s'A' M1 PLhJT* sWram s ts.89 006 f Page 61 of 127 [
=-RADI0ACTIVEEFFLUENTS[ l }
' gl!QUIDQfDOUD TANKS * \ {
-\.J4,*7,f % STOR AG E.
i LIMITING CONDITION FOR OPERATION u
;i.11 '
C.11.1. d he quantity of radioactive material contained in each of the following l unprotected outdoor tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.
- a.- Cyc1/ Condensate Storage Tank !
- b. .RCIC Storage Tank l
. c. Outside temporary tank -
APPLICABILITY: At all times. ACTION:
- a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive !
material to the tank, within 48 hours reduce the tank contents to within ' the limit, and describe the events leading to this condition in the next i., Semiannual Radioactive Effluent Release Report. / -? b .' The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. !
' SURVE!LLANCE REQUIREMENTS _ i
.p .
+
\
f il.1.3 The quantity of.raoicactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a~ l } representative sample of the tank's contents at least once per 7 days when , radioactive materials are being added to the tank. . ,,,, l 6 1. CTanks' included in this specification are those outdoor tanks that are not _ surrounded by liners, dikes, or walls capable of holding the tank contents
-and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
'CLINTON - UNIT 1 3/4
- 9
.f . _
e - -
o, , [ .n ! i LS-89-006 Page 62 of 127 ! PLANT SYSTEMS l Y l [ RAD 10 ACT I v'E EF F LUENfB +- 3/4.7.8 NAIN CONDENSER OFFGA5 MONITORING l l4 EXPLOSIVE GAS MIXTURE ' l b 0FFGAS-
' LIMITING CONDITION FOR OPERATION 3.7.5.1 .
Q.11.2 0 The concentration of hydrogen in the main condenser offgas treatment 1 system shall be limited to less than or equal to 4% by volume. - l
' APPLICABILITY: Whenever the main condenser air ejector is in operation.
i ACTION:
- a. With the concentration of hydrogen in the main condenser offgas treatment ,
system exceeding the limit, restore the concentration to within the limit within 48 hours.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.8.! j
.:,1.2di) The concentration of hydrogen in the main condenser offgas treatment t system shall be determined to be within the above limits by continuously monitoring the waste gases in the main condenser offgas tregtment system ,
whenever the main condenser evacuation system it, n operation with the hydrogen ! monitors required OPERABLE byGable 3.3.7.12-1 f pecification 3.3.7.12.. l l I i p. L g .
- n ,,- -
i 1 y LS-89-006 ! [ RADIOACTIVE EFFLUENTS]+ PLANT SYSTEMg Page 63 of 127 g l { MAIN CONDENSERfg-OFFGAS - N08LE GAS RADICACTIVITY R ATE l l LIMITING CONDITION FOR OPERATION 3.7.B.E v 3.11.2.ZJ The radioactivity rate of noble gases measured at the offgas recom- l l biner effluent shall be limited to less than or equal to 289 mil 11 curies /sec ; after 30 minutes' decay. - . APPLICABILITY: During operation of the main condenser air ejecto'r. ; ACT!g With the radioactivity rate of noble gases at the offgas recombiner effluent exceeding 289 mil 11 curies per second after 30 minutes decay, restore the gross radioactivity rate to within its limit within 72 hours or be in at least HOT i SHUTDOWN within the next 12 hours. SURVEILLANCE REOUIREMENTS
- 4. 7. 8. 2.1 4.11.2.7.1P The radioactivity rate of noble gases at the offgas recombiner l ,
effluent shall be continuously monitored by the Pretreatment Off-Gas process radiation monitor trecuired to be OPERABLE or as otherwise provided by he ODCM. Qable 3.3.7.1-1 T ,
- 4. 7. 8. 2.2 6 f- 3.7.8.2 (skove) k4.11.2.7.2JThuradioactivityrateofnoblegasesfrmtheoffgasrecombiner} - '
effluent shall be determined to be within the limi of SpecificationQ.11. 2.I - ' t at the following frequencies
- by performing an isotopic analysis of a represen-l tative sample of gases taken at the discharge (prior to dilution and/cr dis-
- charge) of the offgas recombiner:
1 l a. At least once per 31 days,
- b. Within 4 hours following an increase, as indicated by the Pretreatment l
I Off-Gas process radiation mlnitor required to be OPERABLE or as otherwise provided byLTable 3.3.7.1- 7, of greater than 50%, after factoring out l increases due to changes Tn THERMAL POWER level, in the nominal steady state fissio gas release from the primary coolant. the ODCM
)
*The provisions of Specification 4.0.4 are not applicable.
7 20 3/4 11-1 I
F, LS-89-006 Pag 2 64 of 127 { p : I)elete taket - f%D. , 3/4.11 RADIOACTIVE EFFLUENTS , , f 3/4.11.1 LIOUID EFFLUENTS . CONCENTRATION c LIMITING CONDITION FOR OPERATION
; 3.11;1.1 The concentration of radioactive material released in liquid effluents '
to UNRESTRICTED AREAS (see Figure 5.3.3-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix.B. Table II, Column 2 for radionuclides - other than dissolved or entrained noble gases. For dissolved or entrained noble i 1 gases, the concentration shall be limited to 2 x 10 4 microcuries/ml total ; activity. l i APPLICABILITY: During release via this pathway. ; ACTION: , With the co'ncentration of radioactive material released in liquid effluents to : UNRESTRICTED AREAS exceeding the above limits, immediately restore the concen- .
.tration to within the above limits. . t SURVEILLANCE REQUIREMENTS 4.}1.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11.1-1.
4.11.1.1.2 The res'ults of the radioat.tivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that.the ; concentrations at the point of release are maintained within the limits cf *"
- Specification 3.11.1.1.
l' . i 1- , 9 l CLINTON - UNIT 1 3/4 11 , i u
I LS*89-006 Dgjde Chilf t f f A $C. A. TABLE 4.12,1-1 ; RADI0 ACTIVE LIOUID WA$TE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT : MINIMUM OFDETECTj0N LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD) TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/ml) A. Batch Waste P P Releage Each Batch Each Batch PrincipajGamma 5x10 7 Tanks Emitters
. 1-131 1x10 8 P M Dissolved and 1x10 5 One Batch /M Entrained Gases (Gamma Emitters),
P Q H-3 1x10 5 d Each Batch Composite Gross Alpha 1x10 7 j ; P Q Sr-89, Sr-90 5x10.s j ' d j Each Batch Composite Fe-55 , 1x10 5 a I i
- m. m.
9 4 e G \ CLINTON - UNIT 1 3/4 11-2
DELETE ENTIRE PAGE . Ls.gg.006 f Page 66 of 127 TABLE 4.11.1-1 (Continued) RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM { r TABLE NOTATIONS }
"The LLD is defined, for purposes of these specifications, as the smallest !
concentration of' radioactive material 'in a sample that will yield a net ! count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank' observation ; represents a "real" signal. i For a particular measurement system, which may include radiochemical [ separation: ,l D LLD = E *.V~. 2.22 x 108 Y exp (-Aat) Where-LLD is the "a priori" lower limit of detection as defined above. [ as microcuries per unit mass or volume, j sbis the standard deviation of the background counting rate or of , the counting rate of a blank sample as appropriate, as counts per ' minute, , E is the counting efficiency, as counts per disintegration, , V is the sample size in units of mass or volume, 2.22 x 10s is the number of disintegrations per minute per_ microcurie,
~ ""
'Y is the fractional radiochemical yield, when applicable, ,
A is the-radioactive decay constant for the particular radionuclide
.(sec-1) and.
At for plant effluents is the elapsed time between the midpoint of I sample collection and the time of counting (sec). Typical values of E. V, Y, and At should be used in the calculation. ., It should be recognized that the LLD is defined as an a priori (before I L the fact) limit representing the capability of a measurement system and not as an,a posteriori (after the fact) limit for a particular measurement. l Abatchreleaseisthedischargeofliquidwastesofadiscrei.evolume. Prior to sampling for analyses, each batch shall be isolated and - then thoroughly mixed by a method described in the ODCM to assure representative sampling. , l l l CLINTON - UNIT 1 3/4 11-3 l . l ' l
] ,
]
LS-89-006
'y mg* n nr 137 g ]
, D e3<A s enU'E P'S ' ' .
p TABLE A.11.1-1 (Continued) i RADI0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM i f i TABLE NOTATIONS (Continued) C The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58..Co-60, 2n-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but ; with an LLD of 5 x 10 8 This list does not mean that only these ' nuclides are to be detected and reported. Other gamma peaks that are together with those of the above nuclides, shall also be measurable,d analyzed an reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.4 in a format outlined in Regulatory Guide 1.21, Appendix B, Revision 1 June 1974. dA composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. 1 l i . I ~
\ .
l t l ,
- 1. .
l i CLINTON - UNIT 1 3/4 11-4 - J
. l LS-89-006 Pcg3 68 of 127
$cledL CrlO C, f 3 C. '
f J(RADI0ACTIVEEFFLUENTS
' 00SE- - !
LIMITING CONDITION FOR OPERATION , 3.11;1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from ; F radioactive materia 1F.'In liquid effluents released to UNRESTRICIED AREAS (see
;4 Figure 5.1.3-1) shall be limited: l
, a. During any calendar quarter to less than or equal to 1.5 mrems to the {
[, total body and to less than or equal to 5 mrems.to any organ, and , b.. During any calenda'r year to less than or equal to 3 mrams to the total
. body and to less than or equal to 10 mrems to any organ. .'
I' APPLICABILITY: At all times. ,
! ACTION: ,
- a. With the calculated dose from the release of radioactive materials in :
i liquid effluents exceeding any of the above limits, prepare and submit to [ the Commission within 30 days, pursuant.to Specification 6.9.2, a Special t Report that identifies the cause(s) for exceeding the limit (s) and defines < the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases-will be in compliance witt, th6 above limits. ;
- b. The provisions of Specificatio0s 3.0.3 and 3.0.4 are not applicable. ;
SURVEILLANCE' REQUIREMENTS 4.11.1.2. Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in , accordance with the methodology and parameters in the ODCM at least once per 31 days. , [ - i 9
' s G
e h CLINTON - UNIT 1 3/4 11-5 V - v -w, r..
e LS-89-006 Page 69 of 127 RAD 10 ACTIVE EFFLUENTS O d e. N Ob b .- A-~ . L10V!D RA0 WASTE TREATMENT SYSTEM ; LIMITING CONDITION FOR OPERATION _ l 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE. T.he appro-priate portions of the system shall be osed to reduce the radioactive materials in liquid wastes print to their discharge when the projected doses due to the liquid effluent to UNRESTRICTED AREAS (see Figure 5.1.3-1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31-day period. APPLICABILITY: At all times. . ACTION: .
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the liquid radwaste treatment !
system not in operation prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that includes the following information:
- 1. Explanation of why liquid radwaste was being discharged without treat- :
ment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- 2. Action (s) taken to res-to,re the inoperable equipment to OPERABLE status, and j
- 3. Summary description of action (s) taken to prevent a recurrence,
- b. The provisions of Specif_ications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS , f 4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be pro- ' I jected at least once per 31 days in accorcance with the methodology and parameters in the ODCM., , 4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABLE i by meeting Specifications 3.11.1.1 and 3.11.1.2. ) l [ i {
~
t 1 e CLINTON - UNIT 1 3/4 11-6 i
=,
LS-89-006 Page 70 of 127 RADIDACTIVE EFFtVENTS Nletc, crtWc . M t . 7 i LIQUID HOLDUP TANKS
- F L LIMITING CONDITION FOR OPERATION s -
1-3.11.1.4 :The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to -10 curies, excluding tritium and dissolved or entrained noble gases. - l
- a. Cycle Condensate Storage Tank
- b. RCIC Storage Tank
- c. Outside temporary tank APPLICABILITY: At all times.
ACTION:
- a. With the quantity of radioactive material in 'any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours reduce the tank contents to within
- the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Reltase Report.
- b. - The provisions of-Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above. listed tanks shall be determined to be within the above limit by analyzing a r:presentative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank. ' 3 (Tanks included in this specification are those outdoor tanks that are not ' surrounded by. liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. . NTON - UNIT 1- 3/4 11-7 .
- e 9 - +
t LS-89-006 Page 71 of 127 l D e.le.te. 4.rdir c. Pa3 e.. RADIOACTIVE EFFLUENTS f 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE . LIMITING CONDITION FOR OPERATION P 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) shall be limited to the following: s
- a. For noble gases: Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and b .* For iodine-131, for iodine-133, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.
APPLICABILITY: At all times. ACTION: With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s).
)* SURVEILLANCE REQUIREMENTS .
l l 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be' : determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing j analyses in accordance with the sampling and analysis program specified in . . . . , Table 4.11.2-1, 4.11.2.1.2 The dose-rate due to lodine-131, iodine-133, tritium, and all radio-nuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with # the methodology and parameters in the ODCM by obtaining representative samples l and. performing analyses in accordance with the sampling and analysis program
, specified in Table 4.11.2-1.
e
. h CLINTON - UNIT 1 3/4 11-8
.I ~
TABLE 1. 2-1 --
~
-i . C^ RAD 10 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS-PROGRAM
'5 .
-g _
. - MINIMUM LOWER LIMIT OF "
c SAMPLING ANALYSIS- TYPE OF' DETECTION (LLD)a _% GASEOUS RELEASE TYPE _ FREQUENCY- FREQUENCY ACTIVITY ANALYSIS (pCi/mi) v A. Station HVAC MC :M C
Principal Gamma Emitters D 1x10 4 Exhaust Grab Sample H-3 Ix10 8 C
?
B. Standby Gas M Principal Gamma Emitters b 1x10 * *- Treatment System Grab Sample- M P Exhaust, when flow H-3 1x10 8 exists $ to C. All release Types Continuous I W9 I-131 1x102 y 1 as Listed in A and Charcoa1' Sample I-133 1x10 88 w B above o T I b " P Continuous W9 Principal Gamma Emitters 1x10 88 Particulate (I-131,others) E Sample Continuous # M Gross Alpha Ix10 88 Composite Particulate - Sample Continuous # Q Sr-89, Sr-90 1x10 88 Composite -
, Particulate Sample 5G 24
~?
~o oe
~ _
u' W - + w qSm a- gw ,-yi- w.y-T f- -,g 9 4 gg e 4--*-4' q w-w s gr- mh- 6- e e m %y---ay . ,_A__--2_.amuw _e em a w ->-eas*wV my-w ru M
Dtldt CAM @"6 LS-89-006 i Page-73 of 127 l f
. TABLE a.11.2-1 (Continued) ,
RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS a ' The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95%. probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical .: separation:- 4.66 s D i LLD = l E V 2.22 x 108 Y exp (-AAt) ; Where: LLD is the "a priori" lower limit of detection as defined above, , as microcuries per unit mass or volume, ; s is the standard deviation of the, background counting rate or of b the counting rate of a blank sample as appropriate, as counts-per minute, E is the counting efficiency, as counts per disintegration, , L V is the sample size in units of mass or volume, - 1
- 2.22 x IOS is the number of disintegrations per minute per microcurie, l .
Y is the fractional radiochemical yield, when applicable. l A is the radioactive decay constant for the particular radionuclide i (seed ) and At.for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting (sec). - Typical values of E, V, Y, and at should be used in the calculation. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement, k . CLINTON - UNIT 1 3/4 11-10 X
[ l LS-89-006 ags 74 of 127 1 p g(gje. enUff- P"66* TABLE 4.11.2-1 (Continued) ! J RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM l TABLE NOTATIONS (Continued) , b The principalincludethefokammaemittersforwhichtheLLDspecificationapplies lowing radionuclidesi Kr-87, Kr-88, Xe-133, Xe-133m, I Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn 65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 in iodine and particulate releases. Tnis list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in ; the Semiannual Radioactive Effluent Release Report pursuant to Specifica-tion 6.9.1.7 in the format outlined in Regulatory Guide 1.21,' Appendix B,
- Revision 1,' June 1974 C
Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a , 1-hour period. d Not applicable.
' Tritium grab saniples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool, i I
The ratio of the sample flow rate to the sampled stream flow rate shall be known for-the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
*95amples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from sampler.
Sampling shall also be performed at least once per 24 hours for at least --
- 7. days following each shutdown, startup, or THERMAL POWER change exceeding -
15% of RATED THERMAL POWER in 1-hour period and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has increased more than a factor of 3, and (2) the noble gas monitor' shows that effluent activity has increased more than a factor of 3. e e l CLINTON - UNIT 1 3/4 11-11 C
i LS-89-006 'I ' Page 75 of 127 p elott e r.li t't go.g t . I RADIOACTIVE EFFLUENTS l 1 DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION !
. +
3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (se.e Figure 5.1.3-1) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equa,1 to 10 mrad for beta radiation, and
- b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrad for beta radiation.
APPLICABILITY: At all times. ACTION
- a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed. corrective actioni to be taken to assure that subsequent releases will be in compliance with the '
above limits. ,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS ,, , , , 4.11.2.2 Cumulative dose contributions for the current calendar quarter and , current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCH at least once per 31 days.
'I
\. CLINTON - UNIT 1 3/4 11-12
LS-89-006 l
.-e- -
RADI0 ACTIVE EFFLUENTS Del *** ""d" N' i P DOSE - 10 DINE-131, 10 DINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM { LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY ' (see Figure 5.1.3-1) shall be limited to the following: -
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
APPLICABILITY: At all times. ACTION:
- a. With the calculated dose from the release of iodine-131 iodine-133, tri-tium,andradionuclidesinparticulateformwithhalfilvesgreaterthan 8 days, in gaseous effluents exceeding any of the above limits prepare >
and submit to the tommission within 30 days, a Special Report that identifies the cause(s) pursuant to Specification for exceeding the limit and 6.9.2, defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits, t b. The provisions of Specifications. 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS i h l 4.11.2.3 Cumulative dose contributions for the current calendar quarter l and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per , 31 days, i 4 J . i l
~
CLINTON - UNIT 1 3/4 11-13
p t LS-89-006 Page 77 of 127 i O eddt cotir e- PaSt-RADI0 ACTIVE EFFLUENTS 7l ; i GASEOUS RADWASTE (OFFGAS) TREATMENT , LIMITING CONDITION FOR OPERATION . 3.11.2.4 The GASEOUS RADWASTE (OFFGAS) TREATMENT SYSTE'M shall.be in operation. I APPLICABILITY: Whenever the main condenser steam jet air ejector system' is , in operation. J ' ACTION: ,
- a. With gaseous radwaste from the main condenser air ejector system being discharged without treatment for more than 7 days, prepare and submit to ,
the Commission within 30 days, pursuant to Specification 6.9.2, a special Report that includes the following information:
- 1. Identification of any inoperable equipment or subsystems, and the reason ,for the-inoperability, t
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence. ,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 1 4.11.2.4 The GASEOUS RADWASTE (OFFGAS) TREATMENT SYSTEM shall be verified to be in operation once every 12 hours when the main condenser air ejector is in , . I use to ensure that the main condenser offgas treatment system is functioning. 1 l l 1 e b
. em CLINTON - UNIT 1 3/4 11-14
4 g LS-89-006
, Page 78 of 127 :
ADI0 ACTIVE EFFLUENTS De,le,te, encre- Pat S-VENTILATION EXHAUST TREATMENT t LIMITING CONDITION FOR OPERATION
- 3
{ ra.11.2.5
. dioactiveThe VENTILATION materials EXHAUST in gaseous waste TREATMENT prior to their SYSTEM discharge. when' the pro- shall be used to red jected doses-due to gaseous effluent releases to areas at and beyond the SITE t BOUNDARY (see Figure 5.1.3-1) would exceed 0.3 mrem to any organ in a 31-day
. period.
APPLICABILITY: At all times other than when the VENTILATION EXHAUST TREATMENT : system is. undergoing routine maintenance. ACTION:
- a. With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following '
information: #
- 1. Explanation of why gaseous radwaste was being dischar0ed without ,
treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability. -
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE :
status, and
- 3. ' Summary description of action (s) taken to prevent a recurrence. .
. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. ,
SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses'due to gaseo.us releases from the site shall be projected at least once per 31 days in accordance with the ODCM, when the ventilation
. exhaust treatment system is not in use.
4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM shall be con-sidered OPERABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 or 3.11.2.3. . e
-~
F . i LS-89-006 Page 79 of 127 i RADIDACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE Dele.te erttico Pa Sc-
]p '
' LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be limited to less than or equal to 4% by volume. -
L' APPLICABILITY: Whenever the raain condenser air ejector is in operation.
- c. ACTION: .
- a. With the concentration of hydrogen in the main condenser offgas treatment system exceeding the limit, restore the concentration to within the limit within 48 hours..
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be determined to be within the' above limits by continuously monitoring the waste gases in the main condenser offgas tregtment system whenever the main condenser evacuation system is in operation with the hydrogen monitors required OPERABLE by Table 3.3.7.12-1 of Specification 3.3.,7.12. e e i 4 CLINTON - UNIT 1 3/4 11-16 j
LS-89-006
'(
Peg) 80 cf 127 RADIOACTIVE EFFLUENTS beladC d.11No. fa.38, ; MAIN CONDENSER' p, LIMITING CONDITION FOR OPERATION 3.11.2.7 The radioactivity rate of noble gases measured at the offgas recom-biner effluent shall be limited to less than or equal to 289 millicuries /sec after 30 minutes' decay. - t APPLICABILITY: During operation of the main condenser air ejecto'r. ACTION
\
With the radioactivity rate of noble gases at the offgas recombiner effluent exceeding 289 millicuries per second after 30 minutes decay, restore the gross radioactivity rate to within its limit within 72 hours or be in at least HOT SHUTDOWN within the next 12 hours. SURVEILLANCE REOUIREMENTS 4.11.2.7.1 The radioactivity rate of noble gases at the offgas recombiner ef fluent shall be continuously monitored by the Pretreatment Off-Gas process radiation monitor recuired to be OPERABLE or as otherwise proviced by Table ?. 3. 7.1-1, 4.11.2.7.2 The radioactivity rate of noble gases from the offgas recombiner effluent shall be determined to be,within the limits of Specification 3.11.2.7 at the following frequencies
- by performing an isotopic analysis of a represen-I tative sample of gases taken at the discharge (prior to dilution and/or dis-i charge)Dof the offgas recombiner:
t .
- a. At least once per 31 days,
- b. Within 4 hours following an increase, as indicated by the Pretreatment #
.0ff-Gas process radiation monitor required to be OPERABLE or as otherwise ,
l provided by Table 3.3.7.1-1, of greater than 50%, after factoring out ' increases due to changes in THERMAL POWER level, in the nominal steady l state fission gas release from the primary coolant. I t l
*The provisions of Specification 4.0.4 are not applicable. -
CLINTON - UNIT 1 3/4 11-17 4
De.lde, Crlh % &* fL - i RADIDACTIVE EFFLUENTS ' LS-89-006 A 3/4.11.3 SOLID RADI0 ACTIVE WASTE Page 81 of 127 LIMITING CONDITION FOR OPERATION - i 3.11.3 Radioactive wastes shall be SOLIDIFIED or dewatered in accordance with the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements I during site, transit, and disposal site requirements when received at the disposal APPLICABILITY: At all times. ACTION: a. With SOLIDIFICATION or dewatering not meeting disposal site and shipping F and transportation requirementt, suspend shipment of the inadequately pro-cessed wastes and correct the PROCESS CONTROL PROGRAM, the procedures and/
. or the solid waste system as necessary to prevent recurrence.
- b. With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, (1) test the improperly processed waste in each '
container to ensure that it meets the burial ground ard shipping require- :
- 1. ments, and (2) take appropriate administrative action to prevent :
recurrence. .
- c. The nrnvisinns of specifica:icas 3.0.3 and 3.0.4 . = not applic.oie.
t SURVEILLANCE REQUIREMENTS l 4.11.3 SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive wastes (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions and sodium sulfate solutions) shall be verified in accordance with the PROCESS CONTROL PROGRAM.
- a. If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional
, test specimens can be obtained, alternative SOLIDIFICATION parameters can l be determined in accordance with the PROCESS' CONTROL PROGRAM, and a sub-sequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may I then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM. , t i b .- If the initial test specimen from a batch of waste fails to verify SOLIDI-1 FICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each concecutivi batch of the - same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste. -
.. CLINTON UNIT 1 3/4 11-18
~
f .
- l. -
LS-89-006 ;
i Page 82 of 127 l 7 D e.l e.f c. e.n tif t PA$t 12 RADIOACTIVE EFFLUENTS , c SOLID RADI0 ACTIVE WASTE , e , SURVE!LLANCE REQUIREMENTS (Continued) 4.11.3 (Continued) i c.- With the installed equipment incapable of meeting Specification 3.11.3 or I declared inoperable, restore the equipment to OPERABLE status or provide i' for contract capability to process wastes as necessary to satisfy all : applicable transportation and disposal, requirements. ;
~
E
.$ ~
l O
. +
E ! 4 % [ V e 4 4
.~_d 3/4 11-19
' (CLINTON-UNIT 1 ,
w
r i LS-89-006 - Pagt 83 of 127 De.ide. entire. , page. RADIDACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem'to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. APPLICABILITY: At all times. t ACTION: ;
- a. With the calculated doses from the relecse of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-tion 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. or ,
3.11.2.3.b, calculations shall be made including direct radiation contri-butions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If
- such is the case, prepare and submit to the Commission within 30 days, ,
l pursuant to Specification 6.9.2, a Special Report that defines the correc- t ! tive action to be taken to reduce subsequent releases to prevent recut-rence of exceeding the above limits and includes the schedule for achieving , conformance with the above limits. This Special Report, as defined in ; { 10 CFR'Part 20.'405c, shall include an analysis that estimates the radiation - exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition
~
r resulting in violation of 40 CFR Part 190 has not already been corrected, ' the Special Report shall include a* request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is con-sidered a timely. request, and a variance is granted until staff action on the request is complete. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. b. SURVEILLANCE REOUIREMENTS 4.11.4.1 Cumulacive dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2., and 4.11.3.3, and in accordance with the methodology and parameters in the ODCM. 4.11.4.2 Cumulative dose contributions from direct radiation from the reac' tor and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Specification 3.11.4.a. CLINTON - UNIT 1 3/4 11-20 - v m - - - - ~ - - - - - - -_ _ - - - -
[ G . t . . LS-89-006 DELETE ENTIRE PAGE Page 84 of 127 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING. t . [ 3/4.12.1 MONITORING PROGRAM , LIMITING CONDITION FOR OPERATION 3.12.1' The Radiological Environmental Monitoring Program shall be conducted i cs specified in Table 3.12-1. - L APPLICABILITY: At all times. ACTION: a... With the radiological environmental monitoring program not being conducted as: specified in Table 3.12-1 prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specifica-tion 6.9.1.6, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
- b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the report levels of Table 3.12-2 when averaged over any eclendar quarter prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2,
-a Special Report that identifies.the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose
- to a MEMBER 0F THE PUBLIC is.
less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3. When more~than one of=the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be. submitted if: concentration (1)
- concentration - (2) +
reporting level (1) reporting level (2) . . .$. 0 When radionuclides other than those in Table 3.12-2 are detected and the - - i result of plant affluents, this report shall be submitted if the potential annual dose
- to a MEMBER OF THE PUBLIC is equal to or greater than the L calendar year limits of Specifications 3.11.1.2, 3.11.2.2, or 3.11.2.3.
This report is not 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 Radiologica1' Environmental l L Operating Report.
- c. With milk or fresh leafy vegetation samples enavailable from one or more of
! the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitor-l ing program within 30 days. The specific locations from which samples were I unavailable may then be deleted from the monitoring program. Pursuant to Specification 6.2.1.7, identify the cause of the unavailabi1Ry of samples and ,
*The methodology and parameters used to estimate the potential annual dose to l a MEMBER OF THE PUBLIC shall be indicated in this reporu i 3/4 12-1 '
{LINTON-UNIT 1 e -- , , - - - . , + - -S -
- 1 LS-89-006 Pag) 85 of 127 t,
1 RADIOLOGICAL ENVIRONMENTAL MONITORING v ' MONITORING PROGRAM LIMITING CONDITION FOR OPERATION (Continued) 3.12.1 ACTION (Continued):
! identify the new location (s) for obtaining replacement samples in the I !. next Semiannual Radioactive Effluent Release Report and also include in k the report a revised figure (s) and table for the ODCM reflecting the new location (s),
- d. The provisions of Specification 3.0.3 and 3.0.4 are not applicable. ,
1 SURVEILLANCE REQUIREMENTS _ 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the det.ection capabilities required by Table 4.12-1. l Det<)e. e.nDt' P% t-1 l l l l l l CLINTON - UNIT 1 3/4 12-2
TABLE 3.12-1 P g RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM z
EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY a
-E AN0/0R SAMPLE SAMPLES AND SAMPLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS U b g 1. DIRECT RADIATION 40 routine monitoring stations Quarterly Gamma dose quarterly.
either with two or more dosi-meters or with one instrument h for measuring and recording dose rate continuously, placed
\1 as follows:
(1) an inner ring of stations, b one in each meteorological 0 sector in the general area " w of the SITE BOUNDARY; I 1 g (2) an outer ring of stations, $
'y one in each meteorological -
w sector in the 6 to 8 km range from the site; Q (3) the balance of the stations to be placed in special in-3 terest areas such as popu- D 1ation centers, nearby resi-dences, schools, and in 1 or 2 areas to serve as control stations. %
%a o, ? .
. ,o O e
~
m_m.,. . _ _ _ . . . _ _ _ _, c -e- *- - * - - - =
./ -
TABLE 3.12-1 (Continued) n RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM C
*i L
e EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE 8 SAMPLING AND TYPE AND FREQUENCY i AND/OR SAMPLE SAMPLES'AND SAMPLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS c . i"i 2. AIRBORNE Radioiodine and Samples from 5 locations: Continuous sampler Radioiodine Canister: Particulates operation with sample I-131 analysis weekly.
- a. 3 samples from close to the collection weekly, or 3 SITE B0UNDARY locations more frequently if in different sectors of the required by dust Particulate Sampler:
highest calculated annual loading. Gross beta radioactivity Q E. average ground-level D/Q. analysis following filter C.
- b. I sample from the vicinity ...
change Gamma isotopic of a community having the analysis' of composite e' highest calculated annual . (by location) quarterly. $. w average ground-level D/Q. e 1 g c. I sample from a control 3 7 location, as for example 15-30 km distant and in $ , the least prevalent wind direction.C
- 3. WATEEBORNE
.e r
- a. Surface I
1 sample upstream E9 Compositesampfeover Gamma isotopic analysis' *3 1 sample downstream 1-month period monthly. Composite for $4 tritium analysis quarterly. o S
- b. Ground Samples from 1 or 2 sources, Quarterly Gamma isotopic
- and tritium C only if likely to be affected analysis quarterly. "
- c. Drinking 1 sample of each of 1 to 3 of Composite sample I-131 analysis on each the nearest water supplies over 2-week period9 composite when the dose that could be affected by its when I-131 analysis- calculated for the consump-discharge. is performed, monthly tion of the water is greater
~
W}. _- ',
.7 +3;;; Q ,
Q. .,_ _ ; 3 x _s y ; ~ . ,
-TABLE 3.12-1-(Continaed)L
' ~ "
~
F^ ^W I ' RADIOLOGICAL FNVIR0fmENTfL MONITORING PROGRAM 1 - V
'i . - -
- g 0 '#
' EXPOSURE PATHWAY -NUMBER OF REPRESENTATIVE . SAMPLING AND TYPE AND FREQUEhCY a '
g 'AND/OR SAMPLE . SAMPLES AND SAMPLE LOCATIONS COLLECTION FREQUENCY ~GF_ ANALYSIS' [ 3. WATERBORNE (Continued) 1 sample from a control positeforgrossbetaap location. ~ gamma isotopic analyses sonthly. Composite for , tritium analysis quarterly. ,
- d. Sediment I sample from downstream area Semiannually Gamma' isotopic analysis' E from with existing or potential . ' semiannually. -
Cm shoreline recreational value. ~ 3:* -
.m
- 4. INGESTION :2 e d
[ a. Milk Samples from allking. animals- ..Semiconthly when Gamma isotopic
- and 1-131 g# ,
in 3 locations within 5-km animals are on analysis semimonthly when -
^~
distance having the highest pasture, monthly animals are on pasture; dose potential. If,there are at other times monthly at other times. {' none, then, I sample from allk- m
^
ing animals in each of 3 areas between 5 to 8 km distant where ! doses are calculated to be. .
. greater than 1 erem per yr.g '
l + I sample from allking animals- ! I at a. control location,.15-30 km - l e distant'and in the least pre- t i valent wind direction. . t i .. ;
- b. Fish and 1 sample each of 3 important Sample in season, or Gamma isotopic analysis' ,
Inverte- species in vicinity of plant semiannually if they on edible portions. I brates discharge area. are not seasonal ,
. ee y, y l 1 sample of same species in areas l not influenced by plant dis-charge.
*3 .
., g4
=
w. _ _ m. .
~-
~
n
; :'y - ,,
" . . . . A&
[N 4 TABLE 3.12-l'(Ccntinued)l.
~- l?Q$
O . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.
~
m ._ y ., 8' - z.
' EXPOSURE PATHWAY : NUMBER OF REPRESENTATIVE, SAMPLING ANO . TYPE AND FREQUENCY:
a. SAMPLES AND SAMPLE LOCATIONS . COLLECTION FREQUENCY OF ANALYSIS' E AND/0R SAMPLE _ - Q . g 4. INGESTION (Continued)
- c. Food 1 sample of.each ~ principal-class At time.of harvest3 ' Gamma isotopic analysis' Products .of food products from any area! on edible portion.' g-that is irrigated.by water..in p wh'ich liquid plant. wastes have g
been discharged. -+--
. 16.
Samples of 3 different kinds Monthly during Gamma isotopic' and I-1311 ,( of broad leaf vegetation grown l growing season analysis. 3.
. nearest each of two different .s,
. 'P offsite locations of highest (
~
) predicted annual ~ average ground-g level D/Q if milk sampling is not T
m performed.
;[;:p I 1' sample of each of-the similar Monthly during Gamma isotopicand I-131 broad leaf vegetation grown growing season 15-30 km distant in the least .
prevalent wind. direction if milk sampling is not performed. t 6 5A t,@
.C
~
,_e,.
r 1
~
g, l LS-89-006 _ s, , Page 90 of 127 DELETE E'NTIRE PAGE TABLE 3.12-1 (Continued) . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
' TABLE NOTATIONS .
8
' Specific parameters of distance and direction sector from the HVAC stack and additional description where pertinent, shall be provided for'.each'and every sample;1ocation in Table 3.12-1 in a table and figure (s) in the ODCM. Refer to .i NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for '
Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from' .i the required sampling schedule,if specimens are unobtainable ~due to hazardous l conditions, seasonal unavailability, malfunction of automatic sampling equip- i
'rient and other legitimate reasons. If specimens-are unobtainable due to sampling equipment malfunction, every effort shall be made to complete correc- -
tive action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environ-D mental Operating Report pursuant to Specification 6.9.1.6. It is recognized ' i
~that. at times it may not be possible or practicable to continue to obtain s
'sa:ples of the media-of choice at the most desired location or time. In these
- instances suitable alternative media and locations may be chosen for the par-ticular pathway in question and appropriate substitutions made within 30 days '
in the radiological environmental monitoring program. In lieu of a Licensee Event Report:and pursuant to Specification 6.9.1.7, identify the cause of the unavailability of samples for that pathway and identify the new location (s).for J' obtaining. replacement samples in the next Semiannual Radioactive Effluent Release - Report and also . include in the report a revised figure (s) and table for the l ODCM reflecting the.new-location (s). i b 0ne or more instruments, such as a pressurized ion chamber,-for measuring and j recording dose rate = continuously may be used in place of, or in addition to, l integrating dor meters. For the purposes of this table, a thermoluminescent _, , , , dosimeter (TLD) is' considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film. badges shall not be used j as' dosimeter's for measuring direct radiation. The 40 stations.is not.an abso- 1
- 1ute number. The number of direct radiation monitoring stations ~may be reduced .;
according to geographical limitations; e.g., at an ocean site, some sectors will i
~ be over' water so'that the number of dosimeters may be reduced accordingly. The j fregency of analysis or readout for TLD systems will depend upon the characteris- :l (tics of the-specific system used and should-be selected to'obtain optimum dose '
information' with' minimal fading. .i c The' purpose of.this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and 1 wind' direction criteria, other sites that provide valid background data may be substituted. d { Airborne-particulate sample filters shall be analyzed for gross beta radioactivity
- 24 hours or more after sampling to allow for raden and thoron daughter decay.
If gross beta activity in air particulate samples is greater than ten times the yearly mean-of control samples, gamma isotopic analysis shall be performed on the individual samples. NTON - UNIT 1 3/4 12-7 j
E b LS-89-006
/pe. tete ent,ve. Page.
*1'*' *'
TABLE 3.12-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ; TABLE NOTATIONS (Continued) j
' Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
I The " upstream sample" shall be taken at a distance beyond significant influence of the discharge. The " downstream" sample shall be taken in an area beyond but near the mixing zone. " Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence. Salt water shall be sampled only. i when the receiving water is utilized for recreational activities. 9A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid (or time) and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period { (e.g., monthly) in order to assure obtaining a representative sample. h Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas-where the hydraulic gradient or recharge proper-ties are suitable for contamination. The dose shall be calculated for the maximum organ and age group l using the octhodology and parameters in the ODCM. d If harvest occurs more than once a year, sampling shall be performed during , each discrete harvest. If harvest occurs continuously, sampling shall be ! monthly. Attention'shall be paid to including samples of tuborous and root i l food products. 1 i l n l , 1 1. p L i l
- CLINTON --UNIT 1 3/4 12-8
}
- -( . . =~
TABLE-3.'12 - h REPORTING' LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS-IN ENVIRONMENTAL SAMPLES .
'r E WATER- AIRBORNE PARTICULATE- FISH MILK : F000 PRODUCTS- '
Z ANALYSIS- (pCf/1) 'OR GASES (pci/m3 )' ' (pCi/ka, wet) (pCf/t) (pCi/kg, wet)' s H-3. .20,000*. ' Mn-54 1,000 30,000 Fe-59 400 10,000' o-Co-58 1,000 30,000 Co-60 300 10,000 ~ w m - ~
} Zn-65 w
300 20,000' j
~
T m Zr-Nb-95 400t 5 I-131 . 2** 0. 9 - 3 100 1 o Cs-134 30 10 1,000 60 1,000
- Cs-137 50 20 2,000 70 2,000 Ba-La-140 200t 1300 -
l *For drinking water samples. This is 40 CFR Part 141 value. -If no drinking water pathway exists, a value i of 30,000 bCi/t may be used.
**If no drinking water pathway exists,'a value of 20 pCf/1 may be used.
- iTotal for parent and daughter . -,
i
- 2C
% 4,
~
, ,~
;S I-o,, 8 a
~
a 'q_. = . , ~ . . - . - - m, y ~.m, eb. , - ..y .m,s . . _ _ . _ , , _ __.w.m -m._ __ _ _ _ -.=__2.m _ _ _ _m -
m
, . s .
~ '
','A,~' 4
-TABLE 4.12-1 -
g C
~
a ,b- - DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS ,
'i -
E LOWER LIMIT OF DETECTION (LLD)c ., E .
*-* WATER AIRBORNE PARTICULATEi ~ FISH - MILK. FOOD PRODUCTS SEDIMENT.
[ ANALYSIS (pCi/t) 'OR GAS (pCf/m3 ) .(pCi/kg, wet) - (pCi/1)~ (pCi/kg, wet) ' (pCi/kg. dry) Gross beta 4 0.01. g H-3 2000* ,7, -
-4 Mn-54 ' 15 130
. m Fe-59 30 260 3 .. 7, w Co-58,60 15 130 m s ' w Zn-65 30 260 7~
'? ' e .
! $$ Zr-95 30 , Hb-95 15 I-131 1** 0.07 1 60 Cs-134 15 0.05 130 - 15 60' 150 Cs-137 18 0.06- 150- 18 80- 180 Ba-140 60 60, . La-140 15 15
.o e '
am ft
*If no drinking water pathway exists, a value.of 30d6 pCi/1 may be used. .E h-
@ t-
**If no drinking water pathway exists, a value of 15 pCi/1 may be used. ,wg-
.o-
.,- ,-u... . . , , , . - . . , . , .. .,. , . - . . , , . . . , . . . - -
~ ~
LS-89-006 DELETE ENTIRE PAGE Page 94 of 127 TABLE 4.12-1 (Continued) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS a ,b . TABLE NOTATIONS a This list dpes not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of.the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13, Rev.1, July 1977. C The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. - i For a paNicular measurement system, which may include radiochemical separatior.: 4.66 s b LLD = E' V 2.22 Y - exp(-Ast) Where: LLD is the "a priori" lower limit of detection as defined above, as picoeuries per unit mass or volume, - -- s is the standard deviation of the background counting rate or of - tNecountingrateofablanksampleasappropriate,ascountsper minute, E is-the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular 'FadionuClide (sec 1), and at for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting (sec). Typical values of E, V, Y, and'at should be used in the calculation. LINTON - UNIT 1, 3/4 12-11
LS-89-006-Pegs 95.of 127 De.)e)s - enU(L ^ PQ3 d-TABLE 4.12-1 (Continued)
- DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS a ,b .
TABLE NOTATIONS (Continued)'
, It_should be recognized that the LLD is defined as an a priori (before
~
1
-the fact)' limit representing the capability of a measu ement system and not as an.a pocteriori (after the fact) limit for a particular measurement.
Analyses shall be performed-in such a manner that the stated LLDs will be.
-achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or ' -
other uncontrollable circumstances may. render these LLDs unachievable. In.such cases, the contributing factors shall be identified and described in the- Annual Radiological Environmental Oper'ating Report pursuant to Specification 6.9.1.6. 3 l 9 l
\
4
'CLINTON - UNIT 1 3/4 12-12
LS-89-006
> Page 96 of_127~
De.It.ke-I , erN re. P"Y RADIOLOGICAL ENVIRONMENTAL MONITORING 7 3/4.12l2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors*of garden of the nearest greater thanmilk animal, 50 m2 (500 ftthe 2 nearest residence and the nearest producing broad leaf vegetation. For elevated or mixed mode releases as) defined in Regulatory Guide 1.111 Revision 1, July 1977, the land use census shall also identify within a , distance of 5 km (3 miles) the' location in each of the 16 meteorological-broad leaf vegetation. sectors of all milk animals and all gardens of greater than 50 m2 APPLICABILITY: At all times. ACTION: a. With a land use census identifying a location (s) that yields a calculated dose or dose commitment greater than the values current Semiannual tion 6.9.1.7. Radioactive Effluent Release Report,, pursuant to Specifica- [ 'b. With a land use census identifying a location (s) that yields a calculated - dose or dose commitment (via the same exposure pathway) 20 percent greater i than atwith dance a location from which Specification 3.12.1 samples are currently being obtained in accor j environmental monitoring program, within 30 days. add the new location (s) to the ra excluding' the control station location, having the lowest calculated doseThe sam or dose commitment (s)
'-use this monitoring progra,m after October 31 of the year in which this la census-was conducted.
Pursuant to Specification 6.9.1.7, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report
-and also include
' reflecting the newinlocation the report (s).a revised figure (s) and table for the ODCM
- c. .
i The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
- Broad leaf vegetation sampling of at least three different kinds of vegetation with the highest predicted 0/Qs in lieu of the garden census.may be pe Specifications -
for broad-leaf vegetation sampling in Table 3.12-1.4c shall be followed,
-including-analysis of control samples.
s CLINTON - UNIT 1 3/4 12-13
LS-89-006 g - _ , - - A Paga97g{127
'/ RADIOLOGICAL ENVIRONMENTAL MONITORING LAND USE CENSUS ~~ Delefe. e n +i e<'- FaSe SURVEILLANCE REQUIREMENTS
$ ,4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide.the best results,.such as by a door-to-door survey, aerial survey, or by consulting
<1ocal agriculture authorities. The resultslof the land use census shall be
-included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
I
'O'-
E 9 l D
'CLINTON - UNIT 1 3/4 12-14 f
l
~
LS-89-006 ' Page 98 of 127 l De.\e.kr e nd re. Past . RADIOLOGICAL ENVIRONMENTAL MONITORING. l 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM ' LIMITING-CONDITION FOR OPERATION 3.12.3= Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that-has been approved by the Commission, that correspond to samples required by Table _3.12-1. e APPLICABILITY: At all times. ACTION:
- a. With analyses not being performed as required above, report'the corrective !
actions taken'to prevent a recurrence to the. Commission in the Annual i Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
- b. The. provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
, SURVEILLANCE REQUIREMENTS
- 4.12.3 The Interlaboratory Comparison Program shakl be described in the 00CM.
A summary of the results obtained as part of the.above. required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6. - L l 4 e 9 e
/
/
j CLINTON - UNIT 1 3/4 12-15 .
F L LS-89-006 Page 99 of 127 ,
'INSiRUMENTATION
~
BASES
~
3/4.3.7.11- RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION The radisactive liquid effluent instrumentation is provided to monitor and con-trol, as applicable,'the releases of radioactive materials in liquid ~ effluents- @** during actual or potential releases of liquid effluents. The a'larm/ trip set- . h*O points fcr these instruments'shall be calculated and adjusted in'accordance. *
'with the methodology and parameters in the ODCH 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 requirements of--General , Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. The purpose of -' tank level indicating devices is to assure the detection and' control of leaks I that if not controlled could potentially result in the transport of radioactive
-1 materials to UNRESTRICTED AREAS.
3/4.3.7.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION '
.p The ' radioactive gaseous effluent instrumenatation is provided to monitor and H control, as: applicable, Lthe release of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm /
trip setpoints for.these instruments shall be calculated and adjusted in
- - accordance with'the methodology and parameters in the ODCH to ensure-that the n alarm / trip will occur prior to-exceeding the limits of 10 CFR Part 20. This
' instrumentation'also includes provisions for monitoring and controlling the L concentrations of potential.ly explosive gas mixtures in the gaseous.radwaste '
ttreatment system. The'0PERABILITY.and use of this instrumentation is consis-tent;with the. requirements of General Design Criteria 60, 63 and_64 of Appendix
'A to 10_CFR Part 50. - Thet sensitivity of any noble gas activity monitors 'used p :to show compliance with the gaseous effluent release requirements of Specifica-tion 3.11.2.2 shall' be such that concentrations as low as 1 x 10 8 pCi/m1'are ~ ~
(measurable. ; s :3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM ' This specification is provided to ensure that the turbine overspeed protection system instrumentation and the. turbine speed control valves are OPERABLE and l: will protect the turbine from excessive overspeed. Protection from turbine excessive. overspeed is requ' ired since excessive.overspeed of the turbine could generate potentially; damaging, missiles which could impact and damage safety related-components, equipment or structures. l
'3/4.3.9 ' PLANT SYSTEMS ACTUATION INSTRUMENTATION The plant systems actuation instrumentation is provided to initiate action to mitigate-the-con. sequences of accidents that are beyond the ability of the opera-tor to control. The LPCI mode of the RHR system is automatically initiated on a high dryWell. pressure signal and/or a low reactor water level, level 1, signal.
The. containment' spray system will then actuate automatically following high drywell and high containment pressure signals. Negative barometric pressure
'CLINTON - UNIT 1 ,
B 3/4 3-8
J .I LSo890006' Page 100 of 127.; Insert for name B 3/4 3-8 , E .7.11 MAIN CONDENSER OFFCAS TREATMENT SYSTEM EXPLOSIVE CAS MONITORING INSTRUMENTATION t
.The main condenser offgas treatment system' explosive- gas ' monitoring j instrumentation-is provided to monitor and control.the concentrations ~of ,
H' potentia 11y' explosive gas mixtures in the main condenser offgas ; treatment-system.. ! i l.
.The intent of'the
- note-attached to the CHANNEL CALIBRATION requirement- $
-is to specify that the CHANNEL. CALIBRATION is to be performed using at' ;
least two separate gas samples of different, specific hydrogen concentrations appropriate for the sensor range. The balance of the sample gas mixture (normally nitrogen) is not'necessarily restricted
~
purely to nitrogen but must be in accordance with the requirements or
~
recommendations provided by the manufacturer of the explosive gas monitoring instrumentation. 1 5 d i
'i, L
f a 1 LRFP2:GSL8
t 'N
. . I ~- -
T LS-89-006 . 7
, Page 101 of;127 l 8.- ,
.?
4 PLANT SYSTEMS. ' 2 , , v .
. BASES .
;..?3/4.7.4 ' SNUBBERS (Continued) . ,
i
.etc. . .. . ' The requirement to monitor the snubber service.31fe is inclu'ed d to !
ensure that_the snubbers periodically undergo a performance evaluation in view of their age-and operating conditions. These records will provide statistical.
- bases for future consideration of-snubber service' life. The requirements for the maintenance of records'and the snubber service life review are not intended: .
itofaffectlplantoperation. . :
^
3/4.7.5' SEALED SOURCE CONTAMINATION
" The limitations on removable contamination for sources requiring leak testing, lincluding alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. ,
- This limitation-will ensure.that-leakage from byproduct, source, and special nuclear. material sources will-not exceed allowable intake values. Sealed ,
" sources are classified into.three groups.according to their.use,.with surveil ~
lance; requirements commensurate with the probability of damage to a source in-that group. Thase' sources which are frequently. handled are required to be stested more often than those which are not. Sealed sources which are continu-ously; enclosed'within aushielded mechanism, i.e., sealed sources within radia- j tion monitoring devices, are considered to be stored and need.not be-tested. c unless they-are removed-from the shielded mechanism. -
" ~3/4;7.6 MAIN TURBINE BYPASS SYSTEM '
t 7Thefmain turbine bypass system is required to be' OPERABLE consistent with the assumptions.of'the. feedwater controller failure analysis in FSAR Chapter 15.
, Lsant . h are.. '~ '
l- , I 4
'I 1
LCLINTON -' UNIT 1 B 3/4 7-3
t 1 LS-89-006. Page 102 of 127 Insert for Pare B 3/4 7 3 l l 3 /4 . 7 . 7 LIOUID STORAGE TANKS The tanks listed in this Specification include all those outdoor storage tanks
- that are not surrounded by liners, dikes, or walls capable of holding the tank- L contents-~and that do not have tank overflows and surrounding area drains !
connected to the liquid radwaste treatment system. .
- Restricting the quantity of radioactive material contained in each of the s specified tanks provides assurance that in the event of an uncontrolled L
L release of the contents from any of these tanks, the resulting concentrations [ would be less-than the limits of 10 CFR Part 20, Appendix B, Table II, Column. 2, at the nearest potable water supply and the nearest surface water supply in - an UNRESTRICTED AREA. e L 3/4.7.8- MAIN CONDENSER OFFCAS MONITORING ' 3/4.7.8.1 0FFCAS - EXPLOSIVE GAS MIXTURE L Although there should normally be more than sufficient steam flow to the steam jet air ejectors to ensure adequate dilution of hydrogen (and thus prevent the offgas from attaining hydrogen levels in excess' of. the flammability limit), l
-this specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the offgas holdup system is-monitored and maintained below the flammability limit of hydrogen. Maintaining the ll concentration of. hydrogen below its flammability limit provides assurance that j the releases of radioactive materials will be controlled in conformance with l- th~ requirements of General Design Criterion 60 of Appendix A to 10 CFR Part
- 50. .
3 /4 . 7 . 8 . 2 0FFCAS - NOBLE CAS RADIOACTIVITY RATE I Restricting the gross radioactivity rate of noble g'ases from the main condenser provides reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10 CFR Part 100 in the event this effluent in inadvertently
-discharged directly to the environment without treatment. This specification implements the requirements of General Design-Criterion 60 and 64 of Appendix
>A to 10 CFR Part 50.
L RFP2:CSL8.
_ _= _ . - _ ._ _ _ . . _ _ _ _ _ p ,.
-l LS-89-006 ,_
P' age 103 of 127 ( Deje fe, entir e. Pa.ge.. )A ' 1/4.11 RADIOACTIVE EFFLUENTS
-BASES c
3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATION ,
'This specification is provided to ensure that the concentration'of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioaptive materials in bodies of. water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appen-dix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.106(e) to the population. The cor. centration limit for di.' solved or entrained noble gases is based upon the assumption that Xe-135 is the control-ling radioisotope and its MPC in air (submersion) was converted to an equiva- ;
lent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.- This specification applies to the release of radioactive materials'in liquid effluents from the site. The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the ' lower limits of detection (LLDs). L . Detailed discussion of the LLD, and other detection limits can be found in L
- Currie,- L; A. , " Lower Limit of Detection: Definition and Elaboration of a L Proposed ' Position for Radiological Effluent and Environmental Measurements,"
NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 , (revised annually). 3/4.11.1.2 005E . This specification is provi'ded to implement the requirements of Sections 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 statements 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 to UNRESTRICTED AREAS will be kept."as low as is reasonably achievable." Also, for fresh: water sites with drinking water s'upplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility l
will not result in radionucli fef concentrations in the finished drinking water p that are in excess of the requirements of 40 CFR Part 141. The dose calcula-
' tion methodology and parameters in the 00CM implement the requirements in Section III. A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models a.nd data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ecuations specified in the -
ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in
'CLINTON - UNIT 1 B 3/4 11-1
- s
' LS-89-006 '
- Page 104 of 127 N x RADIOACTIVE' EFFLUENTS, h M e. co b P 36. M s BASES 3/4.11.1.2 OOSE (Continued)
Regulatory Guide-1.109, " Calculation of Annual Doses to Man from Routine Releases of-Reactor Effluents for the Purpose of Evaluating Compliance with ' 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory
- Guide l'.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
This specification applies to the release of radioa'ctive materials in liquid l effluents from the one reactor unit on the site. . 3/4.11.1.3- LIQUID RADWASTE TREATMENT SYSTEM The 0PERABILITY of the liquid radwaste treatment system ensures that this L system will be avai,lable for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept '"as low as L is reasonably achievable." This specification implements the' requirements of , L 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50' { l and the design objective given in Section II.0 of Appendix I to 10 CFR Part 50. L The specified limits governing.the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose
. design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for-liquid' effluents, i This. specification. applies to the release of radioactive materials in liquid j- effluents from the one reactor unit on the site. .
3/4.11.1.4 LIQUID HOLOUP TANKS ,
.The tanks listed in,this Specification include all those outdoor radwaste' tanks that are not. surrounded by liners, dikes, or walls capable of holding the tank L
contents and that do not have tank overflows. and surrounding area drains connected to the. liquid radwaste treatment system.
- Restricting the quantity of radioactive material contained in the specified .,
l tanks provides' assurance that in the event of an uncontrolled release of the . tanks' contents,.the resulting concentrations would be less than the limits of 10'.CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply'and the nearest surface water supply in an UNRESTRICTED AREA. ( . l l l CLINTON'- UNIT 1 B 3/4 11-2
m . _ . - - _ _ _ _ __ _ LS-89-006 Page 105 of 127
- 3' l t w e. ent.n. pa.p.- y RADIOACTIVE EFFLUENTS BASES v
3/4.11.2 GASEOUS EFFLUENTS , L 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose at any time at and
~
beyond the SITE BOUNDARY from gaseous effluents from all units on the site f' will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associate'd with the concentrations of 10 CFR Part 20, Appendix B., Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either l within or outside the SITE BOUNDARY, to annual average concentrations exceeding " the limits specified in Appendix B. Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE j BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently ' low to' compensate for any. increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS'0F THE i PUBLIC, with the appropriate occupancy factors, shall.be given in the ODCM. The specified _ release' rate limits restrict, at all' times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or be-yond the SITE BOUNDARY to less than or equal to 500 mrem / year to the whole body or to less than or equal to 3000 mrem / year to the skin. These release rate limits ; also restrict, at.all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway .to less than or equal to 1500 mrem / year. This specificition applies to the release of radioactive materials in gaseous effluents from the one reactor unit on the site. The required detection capabilities for radioactive material in gaseous waste . samples are tabulated in terms of the lower limits'of detection (LLDs). Detailed discussion of _ the LLD, and other detection limits can be found in Currie, L. ' A. , " Lower Limit of Detection: Definition and Elaboration of a Proposed Posi-tion for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984), and in.the HASL Procedures Manual, HASL-300 (revised annually). f 3/4.11.2.2 DOSE - NOBLE GASES . This specification is provided to implement the requirements of Sections II.B. III.A and IV.A of Appendin I, 10 CFR Part 50. The Limiting Condition for , l Operation implements the guides set forth in Section II.B of Appendix 1. The ! ACTION statements 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 gaseous effluents to. UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III. A of Appendix I that .
.conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE' PUBLIC through appropriate pathways is unlikely to be substantially underesti-mated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates for radioactive noble INTON . UNIT 1 B 3/4 11-3
,w t
LS-89-006 Page 106 of 127 RADIDACTIVE EFFLUENTS'
)W !
BASES I
'J 3/4.11.2.2 DOSE'- NOBLE GASES (Continued)-
gases in gaseous effluents are consistent with the methodology.provided in Regulatory Guide 1.109," Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating. Compliance with , i 10 CFR Part 50, Appendix I, " Revision 1, October 1977 and Regulatory Guide 1.111 " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous
-Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. .
[ This specification applies to the release of radioactive materials in gaseous i: effluents from the site. 3/4.11.2.3 DOSE - 10 DINE-131. IODINE-133. TRITIUM, AND RADIONUCLIOES IN PARTICULATE FORM l. This: specification is provided to implement the requirements of Sections II.C, III.A and IV.A of' Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I. The ACTION
' statements 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 materials in gaseous effluents to UNRESTRICTED AREAS will,be kept "as low as-is reasonably achievable." ~ The.00CM calculational .
methods specified in the Surveillance Requirements implement'the requirements in Section III. A of Appendix I that conformance with the guices of Appendix I be shown by calculational procedures based on models and data, such that-the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is . unlikely to be substantially underestimated. The OOCH calculational method-b ology and parameters for calculating the doses due to the actual release rates l of the subject materials are consistent with the methodology provided in L -Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine-Releases of Reactor Effluents for the Purpose of Evaluating Compliance with L' 10' CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111 h
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Efflu-ents in' Routine Releases from Light-Water-Cooled Reactors,", Revision 1, July
-1977. These equations also- provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were
- 1) individual inhala-
- examined in the development of these calculations were:
E tion of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. I CLINTON - UNIT 1 B 3/4 11-4 1
}
ku; . l
< -1 LS-89-006 i Page 107 of 127
/[ '
i RADI0 ACTIVE EFFLUENTS Raptue cc 9%6 BASES , 3/4.11.2.3 DOSE - 10DINEk 131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM (Continued) . This specification applies to the release of radioactive materials in gaseous- s < effluents from one reactor unit on the site. . 3/4.11.2.4 AND 3/4.11.2.5 GASEOUS RA0 WASTE TREATMENT SYSTEM AND VENTILATION-
. EXHAUST TREATMENT SYSTEM
-The OPERABILITY of the WASTE. GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever l _'
~ gaseous effluents require treatment prior to release to the environment. The '
requirement that the appropriate portions of these systems be used, when. specified, provides reasonable assurance that the releases of radioactive j materials-ingaseouseffluentswillbekept"aslowasisreasonablyachievable."[ This' specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section I1.0 of. Appendix I to 10 CFR Part 50. The specified limits !' _ governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
-This specification applies to the release of radioactive materials in gaseous
-effluents.from the one reactor unit on the site.- ,
l 3/4.11.2.6 EXPLOSIVE GAS MIXTURE 1 ll This_ specificatio'n is provided to ensure that the concentration of potentially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM is maintained below the flammability limits of hydrogen. Automatic control . features are included in the system to prevent the hydrogen concentrations'from reaching i these flammability .11mts. These automatic control features include isolation of the source of hydrogen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration below the flammability limits. Maintain-ing the concentration of hydrogen below its flammability limits provides assur-
.ance-that the releases of radioactive materials will be controlled.in conform-ance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR'Part 50.
- l. '3/4.11.2.7 MAIN CONDENSER Restricting the gross radioactivity rate of noble gases from the main condenser provides reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of-10 CFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment. This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.
_ (CLINTON - UNIT 1 B 3/4 11-5 _ 8 v # . - - _ _ _ _ _ _ _ _ _ _ __ __.________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
, 4 4
4 1. LS-89-006- y 9 - Page 108 of 127
-]
-RADICACTIVE EFFLUENTS Da.la.tt. e nb re. Pa4 6-I BASES )
J l 3/4.11~-3 SOLIO RADI0 ACTIVE WASTE
. j L .
I This specification implements the-requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. .The process 'i L 1 parameters included in establishing the PROCESS CONTROL PROGRAM may include, but-are not limited to waste type, Waste pH, waste / liquid / solidification agent / 1 . catalyst ratios, waste oi1* content, waste principal chemical constituents. and mixing and curing times. 3/4.11.4 -TOTAL DOSE l' This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The specifica-tion requires the preparation and submittal of a Special Report whenever the E l calculatedidoses from plant generated radioactive effluents and direct radia-L tion exceed 25 mrems to the total body-or any organ, except the thyroid, which
- shall be limited to less than or equal to 75 mrems. For sites containing up to '.
i 4 reactors,. it is highly 'unlikely that the resultant dose to a MEMBER OF THE , L PUBLIC will exceed the dose-limits-of 40 CFR Part 190 if the individual reac-tors remain within twice the dose design objectives of Appendix I, .and if direct radiation doses from the reactor units and outside storage tanks are kept small.- The Special Report will describe a course of action that should E result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within a the'40 CFR Part 190 limits. For the purposes.of the Special Report', it may be assumed that the dose commitment to the HEMBER OF THE PUBLIC from other uranium fuel cycle' sources is negligible, with the. exception that dose contributions i from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE'PUBLIC is estimated to exceed the . requirements of' 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the a provisions of 40 CFR Part 190.11 and 10 CFR Part 20.405c, is considered to be a l timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates.to the limits of 40 CFR
+
Part 190, and does not apply in any way to the other requirements for dose ; limitation of 10 CFR Part 20, as addressed in Specifications 3.11.1.1 and 3.11.2.1.~ An individual is not considered a. MEMBER OF THE PUBLIC during any period.in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
~
CLINTON - UNIT 1 B 3/4 11-6 N
-L-.__l-_-__-------_-__.-----L______._---.--
'LS-89-006 Page 109 of 127 , /4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING DELETE ENTIRE M PAGE BASES 374.12.1- MONITORING PROGRAM The radiological environmental monitoring program required by this specifica-tion provides representative measurements of radiation and of radioactive materials in those exposure pathway.s/and for those radionuclides that lead to.
the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological efflu-ent' monitoring' program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not-higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The initially specified monitoring program will be
- effective for at'least the first three years of commercial operation. Follow-ing this period, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms.of the lower limits of detection (LLDs). -The LLDs required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the.LLD is defined as an a priori (before the fact) limit representing the capability of a-measure-ment system and-not as an a posteriori (after the fact). limit for a particular measurement. Detailed discussion of the Lt.0, and other detection limits, can be found in Currie, L. - A. , " Lower Limit of~ Detection: Definition and Elaboration of a Proposed Position.for Radiological Effluent and Environmental Measurements," . NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 (revised annually). 3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall 1 be used. This census satisfies t5e requirements of Section IV.B.3 of Appen-dix I to*10 CFR Part 50. Restricting the census to gardens of grcter than 50 m2 provides assurance that significant exposure pathways vie leafy vegeta-bles will be identified and monitored since a garden of r.his size is the mini-mum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this mini-mum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage)
- and (2) a vegetation yield of 2 kg/m2, ,
B 3/4 12-1 (CLINTON-UNIT 1
1 i
-. j LS-89-006 -
Page 110 of 127 1
'l l
RADIOLOGICAL ENVIRONMENTAL MONITORING BASES ) I 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison
- Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environ-mental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B 2 of Appendix I to 10 CFR Part 50.
4 DELETE ENTIRE PAGE Se o e e 4 e CLINTON - UNIT 1 8 3/4 12-2
g , c n 4 h' LS-89-006 i
- No chaqd, fo- this page.. ggg provided onig for conWoul%, ,
L ADMINISTRATIVE CONTROLS:
- PROGRAMS '
6.8.4 The following programs shall be established, implemented, and maintained: - a, Primary Coolant Sources Outside Containment
- A programito reduce leakage from those portions of systems' outside containment !
'-- that could contain highly radioactive fluids during'a serious transient or acci - '
' dent'to as low as practical levels. The systems include the'LPCS.,'HPCS, RHR,
~
I RCIC,, Suppression Pool-Makeup, Combustible Gas Control, Containment Monitoring
-and Post-Accident Sampling. The program shall include the following:
- 1. . Preventive maintenance and periodic visual inspection requirements, and-
- 2. -Integrated leak test requirements for each system at refueling cycle intervals or less.
- b. In-Plant Radiation Monitoring ,
A program which will ensure the capability to accurately determine the -{ airborne iodine concentration in. vital areas under accident conditions.
-This' program shall. include the following: -
- 1. -Training of personnel,
- 2. Proce'dures for monitoring, and l
. 3. Provisions for maintenance of samplin'g and, analysis equipment.
- c. Postaccident'Samplina i A program which will ensure the capability to obtain and analyze reactor ;
i ' coolant, radioactive iodines and particulates in. plant ' gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include ~the following: l 1. Training of personnel,
- i. 2. Procedures for' sample and analysis, and --
L 3. Provisions for maintenance of sampling and; analysis equipment,
- d. Ultimate' Heat Sink Erosion, Sediment Monitorino and Dredoing Program A program to provide maintenance on the ultimate heat sink (UHS) in the
- event inspections of the UHS dam, its abutments or the UHS shoreline indicates erosion or local instability. This progr=.m sha11' ensure that L the UHS is maintained in such a way to achieve the'following objectives: '
-(1) During normal operation, there will'be a volume of water in the VHS below elevation 675 sufficient to receive the sediment load from a once in 25 year flood event, and .
(2) Still be adequate to maintain the plant in a safe-shutdown condition for 30 days under meteorological conditions of the severity suggested by Regulatory Guide 1.27.
- e. Fire Protection Prooram -
A program to implement and ma'intain in effect all provisions of the ,
" approved fire protection program as described in the Final Safety Analysis Report as amended, and as approved in the Safety Evaluation Report (NUREG-0853)
',' dated February 1982 as supplemented. Noncompliance with the above Fire Protection Systems described in plant procedure CPS No. 1893.01 shall be ' reported as a REPORTABLE EVENT in accordance with Section 6.6.1 of these - Technical Specifications. CLINTON - UNIT 1 6-16
LS-89-006 . . Page-112'of 127 ADMINISTRATIVE CONTROLS-f
- f. Radioag11v,e Effluent Controls Procram A program shall'be'provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as-low as reasonably achievable. ._The program (1) shall be contained.in the ODCM, (2) shall ,
be implemented by operating procedures, and (3).shall include remedial actions to be taken whenever the-program limits are-exceeded. The program-shall include the following elements: '!
- 1) Limitations on the operability of radioactive liquid and gaseous ;
monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, L 2). Limitations-on the concentrations of radioactive material released in liquid effluents 'to UNRESTRICTED AREAS conforming to 10 CFR ' Part 20, Appendix B, Table II, Column 2
- 3) Monitoring, sampling, and analysis of radioactive liquid and gasecus effluents in accordance with 10 CFR-20.106 and with the methodology and parameters in the ODCM,-
Limitations on the annual and quarterly doses or dose commitment 4) to a MEMBER OF THE PUBLIC from radioactive materials in liquid Mc effluents released from the' unit to UNRESTRICTED AREAS conforming
, to Appendix I to 10 CFR Part 50, q
f '
- 5) Determination of. cumulative and projected dose contributions from-radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least-every 31 days, ,
* , 6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate-portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed. 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to'10 CFR Part 50, ,9c j 7) Limitations on the dose rate resulting from radioactive material XV released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix
, B, Table 11, Column 1, ;
't ;
5 r 9 U. .CLINTON UNIT 1 6-16a U ,
' Da w
e e - , LS-89-006
' 4 Page 113 of 127 ADMINISTRATIVE CONTROLS Radioactive Effluent Controls Procram (Cont.)
- 8) ' Limitations on the annual and quarterly air doses.resulting from "
noble gases released inTgaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part
. 50,
- 9) Limitations on the annual and-quarterly doses to a MEMBER OF THE-PUBLIC from Iodine-131, Iodine 133, tritium, and all radionucliden-in particulate form with half-lives greater than 8 days in gasocus effluents released frca the unit to areas' beyond the SITE BOUNDARY conforming'to Appendix I to 10 CFR Part 50, and i
- 10) Limitations on the annual dose or dose commitment to any MEMBER OF !
THE PUBLIC due to releases of radioactivity and to rcdiation from j uranium fuel cycle sources conforming to 40 CFR Part 190. j
- g. Radiological Environmental Monitorine Program
, . l
.A program shall be provided to monitor the radiation and radionuclides in the' environs'of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential-exposure pathways, ar.d (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure- pathways. The 1
program-shall (1) be' contained in the ODCM, (2) conform to the guidance of: Appendix I to 10 CFR Part 50, and (3) include the following: 1. [" 1) Monitoring, sampling, analysis, and eporting of radiation and o radionuclides in the environment-in accordance with the L methodology and parameters in the ODCM, L' 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY'are identified and that modifications
-to the monitoring program are made if required by the results of this census, and 1
-3) Participation in a Interlaboratory Comparison Program to ensure -
that independent checks on the precision and accuracy of the : measurements of radioactive materials in environmental sample matrices-are performed as part of'the quality assurance program for environwental monitoring. L
~CLINTON-UNIT 1 6-16b o i.
'l
\'t . :
-1 I
LS-89-006 i Page 114 of 127 LI ADMINISTRATIVE CONTROLS l
~
ANNUAL REPORTS (Continued) E estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for.- In.the aggregate,- ry at least 80% of the total whole-body dose received from external sources should be assigned to specific major work functions: b.- Documentation of all challenges to safety valves or safety / relief valves, and
- c. Any other unit unique reports required on an annual basis.
The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.5 should include the following information: (1) Peactor power history starting 48 hours prior to.the first sample in which the limit was exceeded; (2) Results of the last iso-topic analysis.for radioiodine performed prior to exceeding the limit, results of-analysis while limit was exceeded-and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiciodine concen-trations; (3) Clean-up system flow history starting 48 hours prior to the first sample in which the limit was exceeded;-(4) Graph of-the I-131 con- " contration and one other radioiodine isotope concentration in microcuries
.per gram as a function of' time for the duration of the specific activity
.above the steady-state level; and (5) The time duration when the , specific
-activity of the primary, coolant exceeded' the radioiodine limit. -
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT , [6.9.1.6-RoutineRadiological'EnvirenmentalOperatingReportscoveringtheopera-tion of the unit during the previous calendar year shall be submitted prior to , May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.
. The- Annual Radiological Environmental Operating -Reports shall include summaries, M interpretations, and an analysis of trends of the-results of the radiological [
S 7 environmental surveillance activities for the report period, including 'a compar- ' og# 3 1 son with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed' impacts of the plant operation on the environment. 'The reports shall falso include the results of land use censuses required by Specification 3.12.2. z; The Annual- Radiological Environmental Operating Reports shall include the results { lofanalysisofallradiologicalenvironmentalsamplesandofallenvironmental i radiation measurements taken during the period pursuant to the locations speci-fied in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurcments in the format of the table in the CLINTON - UNIT 1 6-18
sp N7' i O [- 4
. t -LS 89-006 l Page 115 of 127 t
Insert for Page 6-18
+
t 6.9.1.6 The. Annual Radiological Environmental Operating Report covering. the operation of the unit during the previous calendar year shall be
, submitted before May 1 of'each year. The report shall' include
- g. summaries, interpretations, and analysis of trends of-the results of the Radiological Environmental Monitoring Program for the reporting period.
The; material provided shall be consistent with the objectives outlined
'inL(1) the ODCM andE(2) Sections IV.B.2,.IV.B.3', and IV.C of Appendix:I
-toJ10 CFR Part 50. ,
L , t e i
..i 4
1
. 4 11
- 1. .
i, i t i l t i *
't l-l', 1' 1
I I i E > F F 4 i i 1 t t k 5 t D JRFPl!:CSL2" p:
I LS-89-006 Page 116 of 127 ) i ADMINISTRATIVE CONTROLS
# ^ '
ANNUAL HADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued) f ku ielogical Assessment Branch Technical Position, Revision 1 November 1979. f l In the event that some individual results are not available for inclusion with I 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 ' j in a supplementary report. '
)
The reports shall also include the following: a summary description of the radiological env,ironmental monitoring program; at least two legible maps
- cover-ing all sampling locations keyed to a table giving distances and directions ,
from the HVAC stack; the results of licensee participation in the Interlaboratory ) Comparison Program, required by Specification 3.12.3; discussion of all devia- ! tions from the sampling schedule of Table 3.12-1; and discussion of all analyses ; in which the LLD required by Table 4.12-1 was not achievable. SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 7 3
.1. 7 Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality.
The Semiannual Radioactive Effluent Release Report shall include a summary of the ouantities of radioactive liquid and gaseous effluents and solid waste M released from the unit as outlined in Regulatory Guide 1.21 " Measuring, Eval-l # uating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive gcd Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis fol-lowing the format of Appendix B thereof. For solid wastes, the format for l Table 3 in Appendix B shall be supplemented with 3 additional categories: 1 class of solid wastes (as defined by 10 CFR Part 61), type of container (e.g., LSA, Type A Type B, Large Quantity), and SOLIDIFICATION ogent or absorbent (e.g., cement, urea formaldehyde). 1 The Semiannual Radioactive Ef fluent Release Report to be submitted within 60 dayg f after logicalJanuary 1 of over data collteted eachtheyear shallyear. previous include Thisan annual annual summary summary may be of hourly m either in the form of an hour-by-hour listing on magnetic tapt of wind speed, J wind direction, atmospheric stability, and precipitnion (if measured), or in
. the form of joint frequency distributions of wind speed, wind direction, and L J
~
0ne map shall cover stations near the site bopadary and a second map shall7 [Qncludethemoredistantstations y ,
+
CLINTON - UNIT 1 6-19
gr - . 4 LS.89 006 l Page 117 of 127- l I, f Insert for Page 6+19 l I 6.9.1.7 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be !
- submitted within 60 days after January 1 and July 1 of each year. The ;
report shall include a summary of the quantities of radioactive liquid .; and gaseous effluents and solid waste released from the unit. The ! material provided shall be (1) consistent with the objectives outlined. j
- . lin the ODCM and PCP and (2) in.conformance with 10 CFR 50.36a and- i
!- Section IV.B.1 of Appendix I to 10 CFR Part 50. i i [' ; I : L : t. i i k i-n , q- E k t t t t 4 I F P O
'RFP1;CSL2 ; ;
i ft LS-89-006 ; Page 118 of 127 ) i ADMINISTRATIVE CONTROLS i b SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) q atmospheric stability.* This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released ! from the unit or station dbring the previous calendar year. This same report l shall also include an assessment of the radiation doses from radioactive liquid - and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside ,' the SITE BOUNDARY (Figure 5.1.3-1) during the report period. All assumptions , used in making these assessments, i.e., specific activity, exposure time and , f location, shall be included in these reports. The meteorological conditions ' concurrent with the time of release of radioactive materials in gaseous ; effluens, as determined by sampling frequency and measurement, shall be used ' for determining the gaseous pathway doses. The assessment of radiation doses ; shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM). The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall also include once a year an assess- ' ment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protec-tion Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977. - l The Semiannual Radioactive F.ffluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped f offsite during the report period: I
- a. Container volume,
- b. Total curie quantity (specify whether determined by measurement or estimate),
- c. Principal radionuclides (specify whether determined by measurement l or estimate),
1
- d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms), ,*
- e. Type of container (e.g., LSA, Type A, Type B, large Quantity), and
( f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).
*In lieu of submission with the first half year Radioactive Effluent Release
! Report, the licensee has the option of retaining this summary of required l meteorological data on site in a file that shall be provided to the NRC upon request. CLINTON - UNIT 1 6-20 i
\
LS-89-006 Page 119 of 127 ADMINISTRATIVE CONTROLS EMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) M fTheSemiannualRadioactiveEffluentReleaseReportsshallincludealistand description of unplanned releases from the site to UNRESTRICTED AREAS of radio- } active materials in gaseous and liquid effluents made during the reporting period. The Semiannual Radioactive Effluent Release Reports shall include any changes f I made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the i I i f.0FFSITEDOSECALCULATIONMANUAL(ODCM),pursuanttoSpecifications6.13and6 respectively, as well as any major changes to liquid,' gaseous, or Solid Radwaste ! Treatment Systems pursuant to Specification 6.15. It will also include a list-fingofnewlocationsfordosecalculationsand/orenvironmentalmonitoringiden-L tified by the land use census pursuant to Specification 3.12.2. j MONTHLY OPERATING REPOR15
- 6. 9.1. 8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the main steam system safety /
relief valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report. SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the i Regional Office of the NRC within the time period specified for each report. i 6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at ~ least the minimum period indicated. 6.10.2 The following records shall be retained for at least 5 years:
- a. Records and logs of unit operation covering time interval at each power level,
- b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety,
- c. All REPORTABLE EVENTS.
- d. Records of surveillance activities, inspections, and calibrations required by these Technical Specifications and the Fire Protection Program 1
CLINTON - UNIT 1 6-21
LS-89-006 l Page 120 of 127 l ADMINISTRATIVE CONTROLS i i RECORD RETENTION (Continued) !
- e. Records of changes made to the procedures required by Specification 6.8.1.
- f. Recoros of radioactive shipments. !
- g. Records of sealed source and fission detector leak tests and results.
- h. Records of annual physical inventory of all sealed source material of record, i
6.10.3 The following records shall be retained for the duration of the unit ' Operating License: >
- a. Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report. :
- b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories,
- c. Records of radiation exposure for all individuals entering radiation I control areas.
- d. Records of gaseous and liquid radioactive material released to the i environs. '
- e. Records of transient or operational cycles for those unit components identified in Table 5.7.1-1. ,
4
- f. Records of reactor tests and experiments. i
- g. Records of training and qualification for current members of the unit staff,
- h. Records of inservice inspections performed pursuant to these Technical " l Specifications. ;
- i. Records of quality assurance activities required by the Operational Quality Assurance Manual not listed in Section 6.10.2, which are classi-fied as permanent records by applicable regulations, codes, and standards.
- j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k .- Records of meetings of the FRG and the NRAG. t proahd only be continuMy .
'CLINTON - UNIT 1 6-22
LS-89-006 , Page 121 of 127 ! r ADMINISTRATIVE CONTROLS l RECORD RETENTION (Continued) ,
- 1. Records of the service lives of all snubbers including the date at which $
the service life commences and associated installation and maintenance
- records.
- m. Records of analyses required by the radiological environmental monitoring program that would permit evaluation of the accuracy of the analysis at a s later date. This should include procedures effective at specified times gg and QA records showing that these procedures were followed. '
6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consis-tent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure. 6.12 HIGH RADIATION AREA l 6.12.1 In lieu of the " control device" or " alarm signal" required by pa'regraph , 20,203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit . (RWP)
- Any individual or group of individuals permitted to enter such areas l shall be provided with or accompanied by one or more of the following:
- a. A radiation monitoring device which continuously indicates the radiation dose rate in the area,
- b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have . been made knowledgeable of them,
- c. A health physics qualified individual (i.e., qualified in radiation pro-tection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the "
area and shall perform periodic radiation surveillance at the frequency L specified by the Radiation Protection Supervisor in the RWP. 6.12.2 In addition to the requirements of Specification 6.12.1, areas access-ible to personnel with radiation levels such that a major portion of the body could receive in 1 hour a dose greater than 1000 mrem ** shall be provided with
, locked doors to prevent unauthorized entry, and the keys shall be , maintained !
- Radiation protection ~ personnel or personnel escorted by radiation protection personnel shall be exempt from the RWP issuance requirement for fields of less than 3000 mrem per hour during the performance of their assigned radiation pro-tection duties, provided they are otherwise following plant radiation protec- j tion procedures for entry into high radiation areas. j
** Measurements made at 18 inches from sources of radioactivity.
CLINTON - UNIT 1 6-23
t' gi ,;
,. k," _'$.,.o' 1
(Ja -
'\.
i n 3' '
' f' y:.- _ , y
< r - 3
, g pH. '
1 . , Ls.89 006-x-:- Page.122 of 127'
, .y.
y _ v : Insert for Page 6 23-
'i.w 9 "
n 2
- n. - -Records of reviews performed for changes made to the OFFSITE DOSE
; CALCULATION MANUAL and the PROCESS CONTROL PROGRAM. .
o
.;-s. .
;b
*' e ' i I f'
? k-s-'
$ 1't yi
(: ,
. .4.- ,
(4
. 't i t
;;;s -
- >y; , . . ,
s
-- g t ,
o c r; $., 4 1: 9-v., , ' I h -'
, , ,- . , o.
A 4-' '%,, l, . u. l-I 4 I E
, s._ -, 8 b,,c.
, T_ RFP1:CSL2.-
I i
?
LS-89-006 Page 123 of 127 ADMINISTRATIVE CONTROLS I under the administrative control of the Shift Supervisor on duty and/or the l Radiation Protection Supervisor. Doors shall remain locked except during l periods of access by personnel under an approved RWP.* For individual areas I accessible to personnel with radiation levels such that a major portion of the body could receive in I hour a dose in excess of 1000 mrem ** that are 1 located within large areas, such as the containment, where no enclosure t exits for purposes of locking, and no enclosure can be reasonably constructed ; around the individual areas, then that area shall be roped off, conspicuously posted, and a flashing light shall be activated as a warning device. 6.12.3 In addition to the requirements of Specifications 6.12.1 and 6.12.2, for individual areas accessible to personnel such that a major portion of the body could receive in 1 hour a dose in excess of 3000 mrem,* entry shall : require an approved RWP which will specify dose rate levels in the immediate work area and require that stay times shall be established. In lieu of the stay time specification of the RWP, continuous surveillance, direct or remote (such as use of closed circuit TV cameras), may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area. i [6.13 PROCESS CONTROL PROGRAM (PCp) N+ f6.13.1 The PCP shall be approved by the Commission prior to implementation. \
\
L i 6.13.2 Licensee-initiated changes to the PCP: 5
. '\
l a. Shall be submitted to the Commission in the Semiannual Radioactive i i I
' Effluent Release Report for the period in which the change (s) was made. k g This submittal shall contain: i "! 1. Sufficiently detailed information to totally support the rationale \
y for the change without benefit of additional or supplemental l l information; E 2. A determination that the change did not reduce the overall conformance
? of the solidified waste product to existing criteria for solid wastes; Sk and Eu I 3. Documentation of the fact that the change has been reviewed and found
- acceptable by the FRG.
Shall become effective upon review and acceptance by the FRG. (b.
" Radiation protection personnel or personnel escorted by radiation protection personnel shall be exempt from the RWP issuance requirement for. fields of '
less than 3000 mrem per hour during the performance of their assigned radia-tion protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.
** Measurements made at 18 inches from sources of radioactivity.
CLINTON - UNIT 1 6-24
r' t LS-89-006-I Page 124 of 127 i Insert for Page 6 24 f 6:13 PROCESS CONTROL PROCRAM (PCP) Changes to the PCP: .;
- a. Shall be documented and records of reviews performed shall I be retained as required by Specification 6.10.3.n. This L
documentation shall contain: .e r h 1) Sufficient information to support the chanBe together ; with the appropriate analyses or evaluations justifying the change (s) and
- 2) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other ,
applicable regulations,
- b. Shall become effective after review and acceptance by the ,
. FRG and the approval of the Manager Clinton Power Station, i
J l t 4 RFP1':GS'L2
- LS-89-006 Page 125 of 127 >
ADMINISTRATIVE CONTROLS
~~
6.14 0FFSITE DOSE CA: CULATION MANUAL (ODCM) NN
; 6.14.1 The ODCM shall be approved by the Commission prior to implementation. '
6.14.2 Licensee-initiated changes to the ODCM: i
\ a. Shall be submitted to the Commission in the Semiannual Radioactive i
1 Effluent Release Report for the period in which the change (s) was made '
\ effective. This submittal shall contain:
I 1. Sufficiently detailed information to totally support the rationale
'9 MS for the change without benefit of additional or supplemental infor-h
,Mg6 mation. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided '
with an approval and date box, together with appropriate analyses or i L evaluations justifying the change (s); o l 2. A determination that the change will not reduce the accuracy or
) reliability of dose calculations or setpoint determinations; and
/ ;
[ / 3. Documentation of the fact that the change has been reviewed and l / found acceptable by the FRG.
- i. I Shall become effective upon review and acceptance by the FRG.
l (b. ! f f 15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASEOUS, ANOTOLID WASTE TREATMENT } l SYSTEMS" l l 6.15.1 Licensee-initiated major changes to the radioactive waste systems, liquid, gaseous and solid: - L l a. Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the FRG. The discussion of each change shall contain:
- 1. A summary of' the evalua 4cn that led to the determination that the change could be made in accordance with 10 CFR Part 50.59.
- 2. Sufficient detailed information to totally support the reason for the /
\
change without benefit of additional or supplemental information; I P,--
- 3. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; j 4. An evaluation of the change, which shows the predicted releases of
' 9 radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the ,
license application and amendments thereto; i
" Licensees may choose to submit the information called for in this Specifica-tion as part of its annual FSAR update.
L .- -
]
CLINTON - UNIT 1 6-25
~~;
.}
LS 89 006 l- Page 126 of 127 r l
' Insert for Page 6 2!. i l
6.14 OFFSITE DOSE CALCU1ATION MANUAL (ODCM)
; Changes to the ODCM: ;
- a. Shall bu documented and records of reviews performed shall ,
L be retained as required by Specification 6.10.3.n. This documentation shall contain: 4
- 1) Sufficient information to support the change together -
with the appropriate analyses or evaluations ! justifying the change (s) and- ,
- 2) A determination that the change will maintain the
;. level of radioactive effluent control required by 10 CIR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or t sotpoint calculations.
- b. Shall become effective after review and acceptance by the ,
FRG.and the approval of the Manager - Clinton Power Station. :
- c. Shall be submitted to the Commission in the form of a '
complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by ' markings in the margin of the affected pages,' clearly g indicating the area of the page that was changed, and shall l indicate the date (e.g.. month / year) the change was ' implemented.
. a l
1 , O' L RFP1:GSL2
' ~
l LS-89-006 n z Page 127 of 127 ADMINISTRATIVE CONTROLS m
/ 5. ~ An evaluation of the change, which shows the expected maximum exposures i to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general '.
,; population that differ from those previously estiraated in the license '
; application and amendments thereto; f 6. A comparison of the predicted releases of radioactive materials, in /
,. i
' liquid and gaseous effluents and in solid waste, to the actual releases /
L for the period prior to when the changes are to be made;
- 7. An estimate of the exposure to plant operating personnel as a result /
of the change; and
- 8. Documentation of the fact ~that the change was reviewed and found /
;- acceptable by the FRG.
[
, hall become effective upon review and acceptance by the FRG.
l^ 1 I I i CLINTON - UNIT 1 6-26 l j
. a}}