ML20127B804
| ML20127B804 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/23/1992 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20127B767 | List: |
| References | |
| NUDOCS 9301130136 | |
| Download: ML20127B804 (52) | |
Text
_
Three h1ile Island Nuclear Station, Unit 2 (Th112)
Operating License DpR 73 Docket No. 50-320 Tedmical.Speejtkation Change RequestfrSCRLNoJ7jpM! RecoYery.operathms !!!1itLChange ReymtlROPCHLNo 49 m
The 1.ieensee requests that the attached changed pages of the Appendix A Technical Specifications (Tech. Specs.) (i.e., ii, iii, s i, is, x, 1-6,3.3-1,3.3-2,3.3-3,il3/43-1,il3/4 3-2,113/4 3-3,51,6-8,610a, and 611 through 617) replace the corresponding pages in the Appendix A Tech. Specs. The Licensee ako requests that the attached changed pages of the Appendix 11 Tech. Specs. (i.e., i, ii, 1-1,2-1,3-1, and 5-3 through 5 9) replace pages i, ii,1-1 through 1-1, 2-1 through 2-16, 3-1, 3.2-1 through 3.2-12, and 5-3 through 5 4 in the Appendix il Tech. Specs. Finally, the Licensee requests that the attached changed pages of the Th11-2 Recovery Operations Plan (ROP) (i.e., i., 4.31, and 4.3-4 through 4.3-8) replace the corresponding pages in the ROP.
Pursuant to NRC Generic Letter 89 01, dated January 31, 1989, a copy of the ODChi is inchided for NRC reference. The ODChi is a combined Th11-I and Th11-2 document; therefore, the sampling frequencies and locations are done on a site basis.
.Dncription of. Change The Tech. Specs. related to radiological eldnents are being relocated to the Offsite Dose Calculation hianual (ODCht), in accordance with NRC Generic Letter 84-01. Accordingly, Sections 1.22,1.23,1.24,1.25, 6.8.4, and 6.13, are being added to the Appendix A Tech.
Specs., Sections 3.3.3.1 and 3/4.3.3.1 aie being deleted from the Appendix A Tech. Specs., and Sections 5.1.3, 5.1.4, 6.5.3.1, 6.8, 6.9, and 6.10 of the Appendix A Tech. Specs. are being revised. Further, Appendix 11 Tech. Spec. Sections 2.1, 3.2, 5.5, 5.5.2, 5.5.3, 5.5.4, and 5.6.1 A.(2) and C. are being deleted and Sections 1.0,5.4, and 5.6.2 are being revised. Finally, ROP Section t.3.3.1 and Table 4.3-3 are being deleted.
In addition, the required frequency of the Quarterly Dose Assessment Repon and Semi annual Radioactive Efnuent Release Repon is being changed to " annual."
Reaxyt or_ Change f
Generic Letter S0 01 provides guidance on the relocation of the Radiological Efnuent Tech.
Specs. to the ODCh1. This TSCR is being proposed in accordance with that generic letter. The conesponding changes to the Appendix A Tech. Specs., the Appendix B Tech. Specs., and the ROP were accomplished in accordance with Generic Letter 89-01. Ilowever, since there are currently no Thil-2 Recovery Tech. Specs. addressing solid radioactise wastes and no related Process Control Progr:un (PCP), per se, that ponion of the generic letter guidance will not be incorporated. Finally,10 CFR 50.36a was amended (57 FR-160, August 31,1992) to required annual submittal of radiological effluent reports. This nile change has been adopted.
9301130136 921223 PDR ADOCK 05000320 P
i Juttificathin of Cllimge Tlie following is a section by section jnstification of the Tech. Specs, and ROP changes requestetl herrin:
AppemlhA SestionLL22123.1.24. aniL25 The definition for ODChi is being added in accordance with Generic letter 89 01. Also adde 41 are the definitions for h1Eh11111R(S) OF Tl111 DUllLIC, UNRESTRICTED ARIIA, and SITil llOUNDARY.
ImtifiGlion of ClKmgc This change is being acconiplisliert as prescribed in Generic Letter 89-01.
Sectioli 3.3.3.1 - Radilttittt110nituting_iminintentallau The Liiniting Condition for Operation (LCO) requiring operability of tiie Th11-2 radiation nionitors is being reloca'ed to the ODChi.
h!htiftGliMLulChaute This change is being acconiplished as prescribed in Generic lxtter 89-01.
Srction 3/4.3,3.1 Radiation _hlenilerintinitatulentitlinu-The liasis for the LCO on radiation inonitors is being rekicated to the ODChl.
hiitif0 rat!citeLClumec This change is being accoinplished as prescribed in Generic Letter 89-01.
- Srction 5.1.3 - Silgll.elmdarv for GaSrEILlifflutnis This section is being revised to reference the ODChi.
hillification of Change This change is being accomplished as requested by the NRC during the public inecting held on hiay 21, 1991.
1 Section 5.1.4 - Site Bomidarv for LiuuliEflhent.3 This section is being revised to reference the ODCh!.
hitiRG. tion of Changg This change is being accomplished as requested by the NRC during the public meeting held on hiay 21,1991.
Ses11pn 6.5.3 - Audits A requirement to audit the ODChi and its implementing documents is being added consistent with the Thti-1 Tech. Specs.
Justification of CJrumc Quality Assurance requirements for radiological progr:uns are contained in Thfi 2 Tech.
Specs. Appendix B Section 5.5.2 which is being deleted. Since both the Radioactive Efnuent Controls Program (RECP) and the Radiological Environmental Afonitoring Program (REh!P) are contained in the ODCht, the proposed audit requirement incorporates the to-be-deleted Appendix B Tech. Spec. and is consistent with the Th11-1 Tech. Specs.
Section 6.8 - Procedures and _PIegrams The title of this section is being changed from " Procedures" to " Procedures and Programs."
hs.tiGGtion of Change The inclusion of the programmatic controls for the RECP and the REh1P into this section necessitates the change in the title.
Section 6.8.4 Programmatic controls for the P.ECP and the REh!P are being included in the Appendix
' A Tech. Specs, hstification of Changg This change is being accomplished as prescribed in Generic Letter 89-01.
Srclion 6.9 - R.rporting Requitancul5 The requirements for the Annual Radiological Envimnmental Operating Repon and the Annual Radioactive Ef0uent Release Report are being added to the Appendix A Tech.
Specs. The requirement for a Quanerly Dose Assessment Repon and a Semi-annual Effluent Release Repon are being deleted.
hiitincation of Changc The annual repon is twing added as prescribed in Generic letter 89-01. The quarterly and semi annual repons which were requirements of the Appendix B Tech. Specs, are being deleted in accordance with the amendment of 10 CFR 50.36a (57 FR-169, August 31, 1992).
Srslign 6.10 - Reeprds Retention The requirement to retain the records of reviews perfonned for changes made to the ODChi is being added to the Appendix A Tech. Specs.
htslineation of Changc This change is being accomplished as prescribed in Generic letter 89-01.
Section 6.13 - Off-sittyose Calculation hiamtal Administrative controls related to the ODChi are being added to the Appendix A Tech.
Specs.
hiitification of Claunc This change is being accomplished as prescribed in Generic Letter 89-01.
b
l AITENDLXE LO dkfinilluiu All definitions except the "NPDilS Pennit" definition are being deleted.
htstificittinitaf_.Gitnge Applicable definitions are contained in the Appendix A Tech. Specs. or the ODCA1, as necessary.
LhliittilingDenditiens for Openttien The entire section is being relocated to the ODChi as Pan 11 Sections 2.0 and 3.0. The only changes made to this section are renuinbering and typographical corrections.
hulilicali0lLOLCllituto This change is being accomplished as prescribed in Generie Ixtter 89-01.
11;_BadielegleitLEnvironmttttaLMeuiluting The entire section is being relocated to the ODChi as Part I Section 8.0. Since Pan I of the ODChi applies to both Th11-1 and Th11-2, there were instances where the original Tech. Spec. requirements for Units 1 and 2 were not exactly the same. In those cases, the more restrictive requirement was incorpomted in ODChi Part I Section 8.0. The only other changes made to this section are renumbering and typographical corrections.
4
,lustinclition of Change This change is being accomplished as prescribed in Generie Ixiter 89-01.
5.4 - Slate _aniErderal Pentti1 Land CeniReales The references to Sections 2 and 3 are being deleted, hulifical101LOLG1DEC Sections 2 and 3 are being deleted in their entirety; therefore, references to these sections should be deleted.
5.5 - Precediurs This section is being deleted in its entirety.
9 i
Antification of Change i
Radiological prognunmatic c ntrols are being relocated to the Appendix A Tech. Specs.
Section 6.8.4.
5.5.2 - Ouldity Assttnulce of Pmgnun Results This section is being delete 41 in its entirety.
htidhgation of Changs f
Quality Assurance requirements for radiological prognuns are contained in the Appendix A Tech. Specs. Section 6.8.4.
5.5.3 Compilance with Procedntc5 t
This section is being deleted in its entirety.
h1511fication of Change Prognunmatic controls are being relocated to the Appendix A Tech. Specs. Section 6.8.4.
i 5.5.4 - Changes in Procedures. Station Design. or Operation This section is being deleted in its entirety, htitiftrittion of Change Radiological prognunmatic controls are being rek)cated to the Appendix A Tech. Specs.
Section 6.8.4. In addition, technical review and contml is addressed in the Appendix A Tech. Specs. Section 6.5.1.
5.6 - StationJkpon Requirements 5.6.1 - Routine Iype113 Section 5.6.1.A.(2), penaining to radiological reponing, is.being relocated to the Appendix A Tech. Specs. Section 6.9.1.1 and the ODChi Part III Section 1.0. Section :
4 5.6.1.C. is being relocated to the Appendix A Tech. Specs. Section 6.9.1.3 and the ODChi Part III Section 3,0.
h!1tif1tation of Ch:U1gg The relocation of Section 5.6.1.A.(2) is being accomplished as prescribed in Generic Letter 89-01. The requirement for an annual effluent release report.is replacing the m..
current Quarterly Dose Assessment Report requireinent of 5.6.1.C consistent with the amended requirements of 10 CFR 50.36a (57 CFR 169, August 31, 1992).
$.6.2 - Nn11mulinclcinth The reference to Section 2.0 is being deleted.
hnliRrMon of Change Section 2.0 is being deleted in its entirety; therefore, reference to this section should be deleted.
ikcore1yJope_rauenLPlan 4.3.3.1 - Radiadon MonitoringJnitatutentallDB The surveillance requirements of the Thil-2 radiation monitors are being relocated to the ODCh!,
hallikation of Clange This change is being accomplished as prescribed in Generic Letter 89-01.
No.Elgniikantila7ards Consideralien 10 CFR 50.92 provides the criteria which the Commission uses to evaluate a No Signincant flazards Consideration. 10 CFR 50.92 states that an amendment to a facility license involves -
No Signincant llazards if operation of the facility in accordance with the proposed amendment.-
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.
The proposed change to relocate the radiological effluent monitoring requirements from the Thil.
2 Recovery Technical Specifications to the ODCM has no impact on the safety of the evolutions occurring at TMI-2. - This proposed change adheres to the guidance provided in Generic Letter 89-01 by implementing the prognunmatic controls in the Tech Specs, and relocating the procedural details to the ODCM.
l t
The proposed change to delete the requirements for quanerly dose assessment and semi annual radioactive efnuent release reponing in favor of an annual n:poning is being accomplished in accordance with the provisions of 10 CFR 50.36a(a)(2) made effective October 1,1992.
These changes simplify the radiological efnuent Tech. Specs. (RETS) and meet the regulatory acquirements for radioactive efnuents and radiological environmental monitoring.
Therefore, the proposed changes do not:
1.
Involve a signincant increase in the probability or consequences of an accident previously evaluated. The relocation of the RETS to the ODChi does not alter the requirements currently being followed by Th11-2. Changing the reponing requirements from quanerly and semi-annually to annually simplines the RETS, meets the regulatory requirements for radioactive efnuent and radiological environmental monitoring, and is considered a line-item improvement of the Tech. Specs. Therefore, there is no increase in the probability or consequences of an accident previously evaluated.
2.
Create the possibility of a new or different kind of accident from any accident previously-evaluated. The reh> cation of the RETS to the ODChi does not alter the requirements-currently being followed by TA112. Changing the reporting requirements from quarterly and semi-annually to annually simplines the RETS, meets the regulatory requirements for radioactive effluent and radiological environmental monitoring, and is considered a line-item improvement of the Tech Specs. Therefore, there is no possibility of a new or different kind of accident from any accident previously evaluated.
3.
Involve a significant reduction in a margin of safety. There is no impact on any margin of safety. The rek) cation of the RETS to the ODChi does not alter the requirements currently being followed by Thil-2. The administrative revision of the frequency of reponing has no impact on any margin of safety.
11ased on the above analysis, it is concluded that the proposed changes involve no signincant hazards considerations as defined by 10 CFR 50.92.
Imnkmet11athil It is requested that the amendment authorizing this change become effective within 60 days upon issuance to allow ample time for _ implementation of affected procedure changes.
=. _.
. i l
i 1
i TilREE MILE ISLAND - UNIT 2 TECilNICAI, SI'ECIFICN110NS Al'I'ENDIX A r
is-.
+
w r--
,,w..-,..~,,
. -, -. ~,av,-,-
,--n-w-,-,,,
-na
,,n,...
y
-..w,m, w
r,-,.-,.-
. ~, - -
INDEX DilillNITIONS EliCRON 121111
.L(LilliElNITIONS - (Continuc41) 1.21 CONTAINhlENT ISOLATION..................
16 1.22 OI:1 SIT 11 DOSl! : TLCULATION hlANUAL (ODCht).....
16 1.23 bl.7.h1BER(S) OF Tile PUBLIC 1-6 1.24 UN R BSTRICTED A R EA........................ 16-1.25 SITE IlOUNDARY 16 FACILITY hlODES (TABLE 1.1)....................... 1-7 FREQUENCY NOTATION (TABLE 1.2)..................
1-8 L(LSAElID' LIMIIS..............................
2-1 TilREE hilLE ISLAND - UNIT 2 li
'i j
i INDIiX Lih10'ING CONDITIONS FOR OPERATION.
-i SECTION 1%QE 3.0 A PPLI C AHILIlX 3.0- 1 11 WATER. INJECTION COOLING AND REACTIVITY CONTROL SYSTEhtS 3.1.1 BORATION CONTROL........
3.1 1 Bonited Cooling Water Injection..........................
3.1-1 Boron Concentration - Reactor Coolant Sys'em.................
3.12 Baron Concentnition - Fuel Transfer Canal...................
3.1-3 Boron Concentnition - Spent Fuel Pool " A"...................
3.1-3 13._INSTRUhlENTATION 3.3.1 NEUTRON h10NITORING INSTRUh1ENTATION,............
3.3-1 Intennediate and Source Range Neutron Flux hionitors............
3.3-1 3.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEh!
INSTRUh1 ENTATION...............................
3.3 1 3.5 3 h!ONITORING INSTRUh1ENTATION.....................
3.3-1 j
h1eteorological Instnnnentation..........................
3.3 1 Essential Panuneters hionitoring Instnunentation................
3.3 2 Chlorine Detection Systems.............................
3.3-2 Fire Detection Instnimentation.......................,
...- 3.3-2 3.4 REACTOR COOLANT SYSTEh!
3.4.1 REACTOR COOLANT LOOPS.........................., 3.4 1 3.4.2 REACTOR VESSEL WATER LEVEL hiONITORING...........
3,4-1 2
3.4.9 PRESSURE /TEh1PERATURE Lih11TS.....................
3,4-1 Reactor Coolant System...............................
3.4-1 3.5 COhth1UNICATIONS 3.5.1 CONTROL ROOh!................................. 3.5 1 3 6 CONTAINhtENT SYSTEhfS 3.6.1 PRIhi ARY CONTAINhiENT..,,....,..................
3.6-1 Containment Integrity...
......,................. 3.6-1 Containment Isolation................................
3.6-4 THREE hilLE ISLAND - UNIT 2 iii
____.,_.~._.a m...
-.. s.
I INDEX JJASES SE.GION PAGE 3/4.0 APPLICAIRLIII.............
..,................B 3/4.0-1 3/4.1 WATER INJECTION COOLING ANILREAC11VITY CONTROL SYSTEhjS 3/4.1.1 BORATION CONTROL AND BORATED COOLING WATER INJECTION................................B 3/4.1-1 J!4.3 INSTRUMENTATION 3/4.3.1 NEUTRON MONITORING INSTRUMENTATION........ B 3/4.3 1 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEh!. B 3/4.3-1 INSTRUh1ENTATION 3/4.3.3 MONITORING INSTRUMENTATION................ B 3/4.3-1 Meteorological Monitoring Instnunentation.............. B 3/4.3-1 Essential Parameters Monitoring Instninientation........... B 3/4.31 Chlorine Detection Systems........................ B 3/4.3-1 Fire Detection Instnunentation...................... B 3/4.3-2 J/4.4 REACTOR COOLANT SYSTEh!
3/4.4.1 REACTOR COOLANT LOOPS..................... B 3/4.4 t 3/4.4.2 REACTOR VESSEL WATER LEVEL MONITORING...... B 3/4.4-1 3/4.4.9 PRESSURE / TEMPERATURE LIMITS................ B 3/4.4 1 TIIREE MILE ISLAND - UNIT 2 vi
=, -,. -
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.0 ADMIN 11TIMIIVE CONTRQM............................
6 1 6.1 R ES PON SLIUllD'.....................................
6-1 (t2._QAGAN17dT108 6.2.1 G PUNC Organization...............................
6-1 6.2.2 TMI-2 Organization................................
6-1 6.3 UNIT STAFF OUALLEICATIONS...........................
6-3 fLi_TR A I NI N G.........................................
6-3 F
6.5 REVIEW AND AUDIT 6.5.1 TECIINICAL REVIEW AND CONTROL..................
6-3 6.5.1.10 Reconis......
6-5 6.5.1.11 Qualifications....................................
6-5 6.5.2 INDEPENDENT SAFI?IT REVIEW.....................
6-5 6.5.2.1 Function.......................................
6-5 6.5.2.5 Responsibilities...................................
6-6 6.5.2.7 Reco ni s........................................
6-7 6.5.2.8 Quali0 cations for Independent Safety Reviewers...............
6-7 (Upon Implementation of IOSRG) 6.5.3 A U DITS....................
6-7 6.5.3.2 Rec o ni s........... i...................
........6-8 6.5.4 SAFETY REVIEW GROUF (SRG) (Until Implementation of IOSRG).
6-8 6.5.4.1 Fu nct ion........................................
6-8 6.5.4.2 Orga nizat io n...................... _.............. -. 6-9 6.5.4.3 Respon sibilities...................................
6-9 6.5.4.6
-Au t ho ri t y......................................,
6-9 6.5.4.7 Quali0 cations...........,,..................... -,.
6-9 6.5.4.8 Reco ni s,,..............,...,,.................
6-10 6.5.5 INDEPENDENT ONSITE SAFETY REVIEW GROUF (IOSRG) 6-10 4
6.5.5.1 Function
......................................6-10 6.5.5.2 Organization....................................
6 10 6.5.5.3 Responsibility...................................
6-10 6.5.5.4 A u t ho ri t y..................................... 6-10a 6.5.5.5 Qualifications.........
6-10a 6.5.5.6 R eco ni s.....................,.............
... 6: 10a TIIREE MILE ISLAND - UNIT 2 ix L.
-j
INDEX f}Dh11NISTRWilyE CONTROL.S SE G M P6GE hA_RiiPORTABL11 EVENT 1AGON........
6-10a 63_ERDLC1URFJ_AND PROGRAbjS
. 6-10a 6,4 REPORTIEG REOUIREh1ENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6-13 6.9.1.1 Annual Radiological Environmental Operating Repon 6-13 6.9.1.2 Annual Radioactive Ef0uent Release Report 6-13 6.9.1.4 Annual Reports
. 6-14 6.9.2 SPECIAL REPORTS 6-15 6.11) RECORD _RETENIIM,
6-15 6J.1_RADiriTION_)310TECTION PROGRAh!
6-16 il2 HIGif RADIATION AREA.
6-16 6.13 OEESITE DOSE CALCULeiTION h1 ANUAL (ODCh{}
6-17 TilREE hilLE ISLAND - UNIT 2 x
1.0 DEFINITIONS -
1.21 CIONTAINhBINT ISOLATION shall exist when; a.
Each penetration is:
1.
Closed by an accessible manual valve, a welded or bolted blind Dange, or a deactivated autonntic valve secured in the closed position to provide isolation of each penetration, or; 2.
Open per an approved procedure but can be closed pursuant to Spc iac on 1.21.a.l. Controls shall be implemented to minimize the time the penstion is allowed open and to specify the conditions for which the penetration is open.
Penetrations shall be expeditiously closed upon completion of the conditions specified in the approved procedures.
b.
The li uipment Ilatch is closed and scaled.
l c.
Each Containment Airlock is OPERABLE pursuant to SpeciGeation 3.6.1.6.
1.22 The DEESITE DOSE CALCULATION M_ANUAL ODCM) shall contain the methodology and parameters used in the calculation of off site doses resu!:ing from radioactive gases and liquid ef0uents, in the calculation of gaseous and liquid efnuent monitoring Alann/ 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 required by Section 6.8.4 and (2) descriptions of the infonnation that should be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report required by Specifications 6.9.1.1 and 6.9.1.2, respectively.
1.23 b1 EMBER (SF OF TIIE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the GPU System, GPU contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
1.24. UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access which is not controlled by the licensee for puq)oses of protection of individuals from exposum to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quaners or for industrial, commercial, institutional, and/or recreational purposes.
l.25 SLTILBOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by GPU Nuclear.
4 TIIREE MILE ISLAND - UNIT 2 1-6
-LIMITING CONDITIONS FOR OPliRATION 3.3 INSTRUMENTATION 3.3. I NJiUTRON_ MONITORING INSTRUMENTATION.
INTERMEDIATE AND SSURCE RANGE NEUTRON FLUX MONITORS 3.3.1.1 As a minimum, the intermediate and source range neutron monitoring instnunentation channels of Table 4.31 of the RECOVERY OPERATIONS PLAN shall be OPERABLE.
9 APPI.lCABILITY: MODEI ACILQN:
a.
With the number of source range neutron monitoring channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement of Table 4.3-1 of the RECOVERY OPERATIONS PLAN, restore the inoperable channel to OPERABLE status within 30 days.
b.
With no source range neutron monitoring channels OPERABL.E, suspend all activities; involving CORE ALTERATION, verify compliance with the boron concentration requirements of Specification 3.1.1.2 at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by a mas _s balance calculation and at least once per 7 days by a chemical analysis and restore at least one source range neutron monitoring channel to OPERABLE status within 7 days.
c.
With no intermediate range neutron monitoring channels OPERABLE, restore at least one intermediate range channel to OPERABLE status within 7 days.
3.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Deleted 3.3.3 h10NITORING INSTRUMENTATION h.IETEOROLOGICAL INSTRUMENTATION 3.3.3.4 The meteorological monitoring instmmentation channels shown in Table 4.3-5 of the RECOVERY OPERATIONS PLAN shall be OPERABLE.
APPLICABILITY: MODES I'AND 2 ACTION:
With any of the above required meteorological monitoring channels inoperable, restore the inoperable channel (s) to OPERABLE status within 7 days, THREE MILE ISLAND - UNIT 2 3.3-1
11MITING CONDITIONS FOR OPERATION ESSENTIAIJMR.Ah1ETERS MONITORIliC MSTRUh1ENTATION B
i 3.3.3.5 The Essential Parameters Monitoring Instrumentation shall be OPERABLE in accordance
~
with the requirements of Table 4.3-7 of'he IGCOVERY OPERATIONS PLAN.
APPLICAlllLITY: MODEI A.CTION:
j For instnunentation not in acconlance with the requirements of Table 4.3-7 of the RECOVERY OPERATIONS PLAN, restore the inoperable instnunent(s) to the requirements of Table 4.3-7 of the RECOVERY OPERATIONS PLAN within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
C11LORINE DETECTION SYSTEMS 3.3.3.7 Two Chlorine Detection Systems, with their alarm / trip setpoints adjusted to actuate at a chlorine concentration of less than or equal to 5 ppm, shall be OPERABLE:
a.
One at the air intake tunnel, and b.
One at the Control Room air supply duct.
APPLICABILITY: MODE 1 ACTION:
With one or more Chlorine Detection Systems inoperable, within I hour initiate and maintain operation of the Control Room Emergency Ventilation System in the recirculation mode of
~
operation; restore the inoperable detection system to OPERABLE status within 30 days.
l L
ELILE DETECTION INSTRUMENTATION l
3.3.3.8 As a minimum, the fire detection instnimentation for each fire detection zone shown in Table 4.3-11 of the RECOVERY OPERATIONS PLAN shall be OPERABLE.
APPLICABILITY: MODES 1,2 and 3 ACTION:
With the number of OPERABLE fire detection instnunents less than required by Table 4.3-11 m the RECOVERY OPERATIONS PLAN, insure that an alternate instrument with the same coverage is OPERABLE, or; 1.
Within I hour, establish a fire watch patrol to inspect the zone with the inoperable instniment(~s) at least once per hour, and 2.
Restore the inoperable instrument (s) to OPERABLE status within 14 days.
=
TIIREE MILE ISLAND - UNIT 2 3.3-2 i
... -... -.. ~..
. ~.....-
.~
. - ~ --
TIIIS PAGE INTENTIONALLY LEFT BLANK l
- TIIREE MILE ISLAND - UNIT 2 3.3-3
3/4.3 INSTI1UMEN_TATION MSES 3// L3.1 - NEUTRON MONITORING INSTRUMENTATION f
The neutron monitoring instrumentation, which was included in the nonnal Reactor Protection System Instrumentation, provides infonnation regarding the shutdown status of the core and it will be used to monitor changes in neutron generation.
3/4.3.2 ENGIN]lERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION Deleted 3/4.3.3 MONITORING INSTRUh1ENTATION 3/4.3.1.4 METEOROLOGICAldNSTRUMENTATION The OPERABILITY of the meteorologicalinstrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public, 3/4.3.3.5 ESSENTIAL _]MRAMETERS MONITORING INSTRUh1]iNTATION The OPERABILITY of the Essential Pammeters Monitoring Instrumentation ensures that sufficient infonnation is available on selected plant parameters to monitor and assess these variables. Reactor Coolant System temperature indication is provided outside the Control Room in the event that Control Room habitability is lost.
3/4.3.3.7 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine detection systems ensures that an accidental chlorine release will be detected promptly and the Control Room Emergency Ventilation System will automatically isolate the Control Room and initiate its operation in the recirculation mode to provide the required protection.
THREE MILE ISLAND - UNIT 2 B 3/4 3-1
l 3/4.3 INSTRUh1ENTATION.
BASES 3/LD.8 and 3/4.3.3.9 FIR _ILDJITECTION INSTRUMENTATION OPERABILITY of the Fire Detection Instnunentation ensures that adequate warning capability as required by the TMI-2 Fire Protection Program Evaluation, is available for the prompt detecction of Gres. The capability is required in order to detect and locate fires in their early stages. Prompt detection of fires is an integral element in the overall facility Gre protection program.
In the event that a portion of the Fire Detection Instmmentation is inoperable, the establishment of frequent Gre patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is returned to service. For purposes of ALARA considerations, remote mechanisms (e.g., CCTV covemge) may be utilized to perfonn the fire patrol. However, the inoperabilty of this instmment would not affect the capability to maintain the safe shutdown condition of the plant nor the ability to prevent offsite releases greater than 10 CFR 100 limts, f
i l
l THREE MILE ISLAND - UNIT 2 B 3/4 3-2 l
,, + _.
, ~. ~.
t t
THIS PAGE INTENTIONALLY LEFT BLANK e
. THREE MILE ISLAND - UNIT 2 B 3/4 3-3
$,0 DF, SIGN FFATURES I
5.1 SITE EXCLUSION SITE 5.1.1 The exclusion area is shown on Figure 5.1-1.
LOW llOPULATION ZONE 5.1.2 The low population zone is shown on Figure 5.1-2.
SITE BOUEDARY FOR GASEOUS EFFLUENTS 5.1.3 The SITE BOUNDARY for gaseous eflhients shall be as shown in the ODCht.
SIIE BOUNDARY FOR LIDULD_EFFLlTiNTS.
5.1.4 The SITE BOUNDARY for liquid effluents shall be as shown in the ODCht.
1,2 CONTAINhlENT CONFIGURATION 5.2.1 The reactor containment building is a steel lined, reinforced concrete building of cylindrical shape, with a dome roof and having the following design features:
a.
Nominal inside diameter = 130 feet b.
Nominal inside height = 157 feet c.
hfinimum thickness of concrete walls = 4 feet d.
hiinimum thickness of concrete roof = 3.5 feet e.
hiinimum thickness of concrete floor pad = 13.5 feet f.
Nominal thickness of steel liner = 1/2 inches g.
Net free volume = 2.1 x 10 cubic feet DESIGN PRESSURE AND TEhlPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 2 psig and a temperature of 286 F.
TIIREE MILE ISLAND - UNIT 2 5-1
~
ADMINIST8ATIVE CONTROLS i
d.
During Modes 1,2, and 3, the performance of activities required by the Recovery Quality Assurance Plan to meet the criteria of Appendix "B",- 10 CFR 50. The audit frequency shall be at least once per 24 months.
During Mode 1, the Emergency Plan and implementing procedures. The audit frequency c.
shall be at least once per 12 months.
f.
Deleted.
- g.
During Modes 1,2, and 3, the Radiation Protection Plan and implementing procedures.
The audit frequency shall be at least once per 12 months, h.
During Modes 1,2, and 3, the Fire Protection Program and implementing procedures. The audit frequency shall be at least once per 24 months, i.
During Modes I, 2, and 3, an independent fire protection and loss prevention progmm inspection a O technical audit shall be perfonned annually utilizing either qualified offsite licensee personnel or an outside fire protection finn.
j During Modes 1,2, and 3, an inspection and technical audit of the fire protection and loss prevention progrmn, by an outside qualified fire consultant at intervals no gnater than 3 years.
k.
During Modes 1,2, and 3, any other area of unit operation considered appropriate by the SRG (until implementation of IOSRG), the Manager, SRG's immediate supervisor, the IOSRG, other managers reporting directly to the Office of the Director _TMI-2, the Office of the Director TMI-2, or the Office of the President - GPUNC. Any other areas required to be audited by QA will be identified to the appropriate QA Management level.
1.
The ODCM and implememing procedures at least once per 24 months.
RECORDS 6.5.3.2 Audit reports encompassed by Section 6.5.3.1 shall be forwarded for action to the 4
management positions responsible for the areas audited and either the SRG, (until implementation-of IOSRG) or the IOSRG (upon its implementation), within 60 days after completion of the audit.
The SRG, (until implementation ofIOSRG) or the IOSRG will review specified audits performed by QA and make corrective action recommendations as appropriate.
6.5.4 SAFETY REVIEW GROUP (SRG)-
EUNCTION 6.5.4.1 The SRG shall be a full-time group of engineers, independent of the Site Operations and Engineering staff, and h)cated onsite within the TMI-2 division. (See Organization Plan Figure 1.2.)
MJ3JCABILITY 6.5.4.1.1 Until implementation of IOSRG.
TIIREE MILE ISLAND - UNIT 2 6-8
6DhllbilSTRATIVE CON 1R_QlJ AUIIIORITY 6.5.5.4 The IOSRG shall have access to the unit and unit records as necessary to perfonn its evaluations and assessments. Based on its reviews, the IOSRG shall provide recommendations to the management positions responsible for the areas reviewed.
QUALIFICATIONS 6.5.5.5 The IOSRG engineers shall have either: (1) a Bachelor's Degree in Engineering or the Physical Sciences and three years of professional level experience in the nuclear power field including technical supporting functions, or (2) eight years of appropriate experience in nuclear power plant operations and/or technology, Credit toward experience will be given for advance degrees on a one-to-one basis up to a maximum of two years.
IlliCORDS 6.5.5.6 Reports of evaluations and assessments encompassed in Section 6.5.5.3 shall be prepared, approved, and transmitted to the Office of the Director, TMI-2, the division vice president responsible for nuclear safety assessment and the management positions responsible for the areas reviewed.
6.6 REPORTABLE EVENT 1 ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 of 10 CFR Part 50, and b.
Until implementation of IOSRG, each REPORTABLE EVENT shall be investigated and reviewed by the SRG, including the preparation and fonvarding of reports covering evaluation and recommendations to prevent recurrence. A report shall be submitted to the Manager, SRG's immediate supervisor and the Office of the Director, TMI-2. Upon implementation of IOSRG, each REPORTABLE EVENT shall undergo an independent safety review, by a qualified ISR. This review may be perfonned after the fact.
c.
Deleted.
6.7 SECTION DELETED 6 8 PROCEDURES AND PROGRAMS m
6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of Regulatory Guide a.
1.33, Revision 2, February 1978.
b.
Recovery Operations Plan implementation.
Surveillance and test activities of safety-related equipment and radioactive waste c.
management equipment.
TilREE MILE ISLAND - UNIT 2 6-10a
ADh1IEISTR ATIVE CONTROLS 6.8.2.1 Each procedure and any change to any procedure prepared pursuant to 6.8.1, shall be prepared, reviewed and approved in accordance with 6.5 and will be reviewed periodically as required by ANSI 18.7 - 1976.
6Property "ANSI code" (as page type) with input value "ANSI 18.7 - 1976.</br></br>6" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..8.2.2 Deleted.
6.8.3.1 Temporary changes to procedures of 6.8.1 may be made provided that:
a.
The intent of the original procedure control is not altered, and b.
(1) For those procedures which affect the operational status of unit systems or equipment, the change is approved by two members of the unit management staff, at least one of whom holds a Senior Reactor Operator's License. (Note: The requirement for a Senior Reaar Operator's License applies during hiode 1 only.)
If one of the two above signatures is not by a supervisory person within the Department having cognizance of the procedure being changed, the signature of that supervisory person within the depanment will also be required, or
- 2) For those procedures which do not affect the operational status of unit systems or equipment, the change is approved by two members of the responsible organization.
If one of the two above signatures is not by a section manager / director within the Depanment having cognizance of the procedure being changed, the signature of that section manager / director within the department will also be required, and c.
The change is documented, Independent Safety Review completed, and the required reviews and approvals are obtained within 14 days, and d.
Those changes to procedures required by Specification 3.9.13 are submitted to the NRC for review within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following approval by the management level specified for implementation by Section 6.5.1.9.
6.8.4 The following programs shall be established, implemented, and maintained:
a.
. Radioactive Effluent Controls Procram A progrmu shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to hfEh1BER(S) OF THE PUBLIC from radioactive effluents as low as is reasonably achievable.
The program (1) shall be contained in the ODChi, (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 ODCh!,
TIIREE hilLE ISLAND - UNIT 2 6-11
ADMINISTRATIVE CONTROLS 2)
Limitations on the concentrations of radioactive material released in liquid efnuents to UNRESTRICTED AREAS confonning to 10 CFR Part 20, Appendix B, Table II, Column 2.
3)
Monitoring, sampling, and analysis of mdioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM, 4)
Limitations on the annual and quanerly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS confonning to Appendix I to 10 CFR Pan 50, 5)
Detennination of cumulative and projected dose contributions from radioactive effluents for the current calendar quaner 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 confonning to Appendix I to 10 CFR Pan 50, 7)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY confonning to the doses associated with 10 CFR Pan 20, Appendix B, Table II, Column 1, 8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each tmit to areas beyond the SITE BOUNDARY confonning to Appendix I to 10 CFR Part 50, 9)
Limitations on the annual and quanerly doses to a MEMBER OF THE PUBLIC from tritium and all radionuclides in paniculate fonn with half-lives greater than 8 days in gaseous effluents released fmm each unit to areas beyond the SITE BOUNDARY confonning to Appendix I to 10 CFR Pan 50.
b.
Radiological Environmental Monitoring Program 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, and (2) verification of.
the accuracy of the effluent monitoring program and. modeling'of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) confonn to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
THREE MILE ISLAND - UNIT 2 6-12
ADhflNISTRATIVE CONTRplS 1) hionitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the
- ODChi, 2)
A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identined and that modiGeations to the monitoring program are made if required by the results of this census, and 1
3)
Panicipation in an 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 pan of the quality assurance program for environmental monitoring.
f;.9 REPORTING REOUIREhfENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCFJ 6.9.1 In addition to the applicable mponing requirements of Title 10, Code of Federal Regulations, the following repons shall be submitted in accordance with 10 CFR 50.4 unless otherwise noted.
ANNUAL RADIOLOGICAL ENVIRON 1] ENTAL OPERATING llEPORT' 6.9.1.1 The Annual Radiological Environmental Operating Report covering the opemtion of the unit during the previous calendar year shall be submitted before hiay I of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental hionitoring Program for the reponing period. The material provided shall be consistent with the objectives outlined in (1) the ODCh1 and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2 6.9.1.2 The Annual Radioactive Ef0uent Release Report covering the operation of the unit during the previous clendar year shall be submitted within 60 days after January 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous efGuents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODChi and (2) in comormance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
i-A single submittal may be made for a multi-unit station.
2 A single submittal may be made for a multi-unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radvraste systems, the submittal shall specify the releases of radioactive material from each unit.
L THREE hfILE ISLAND - UNIT 2 6-13 l
i
ADMINISTRATIVE CONTROLS ANE1ML_RIIPORTF 6.9.1.4 Annual reports covering the activities of the unit as described below during the previous calendar year shall be submitted prior to March I of each year.
t 6.9.l.5 Reports required on an annual basis shall include:
a.
A tabulation of the number of station, utility and other personnel (including-contractors) receiving exposures greater than 100 mrem /yr and their associated manrem exposure according to work and job functions,2 e.g., reactor operations and surs eillance, in-service inspection, routine maintenance, special maintenance 4
(describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose whole body dose received from extemal sources shall be assigned to specific major work functions.
b.
The following information on airemft movements at the liarrisburg International Airport:
1.
The total number of airemft movements (takeoffs and landings) at the IIarrisburg International Airport for the previous twelve-month period.
2.
The total number of movements of aircraft larger than 200,000 pounds, based on a current percentage estimate provided by the airport manager or his 4
designee.
IMRIATION SAFETY PROGRAh! REPOKr 6.9.1,6 Deleted.
BEPORTABLE OCCURRENCES 6.9.1.7 Deleted.
EBOh!PT NOTIFICATION WITil WRrrTEN FOLLOWUf 6.9,1.8 Deleted 1 A single submittal may be made for a multiple unit station. The submittal should combine those sections that are conunon to all units at the station.
2 This tabulation supplements the requirements of Q20.407 of 10 CFR Part 20.
l TIIREE MILE ISLAND - UNIT 2 6-14 y
t
_, ~ _ _
AQh11NISTRATIVE CONTROLS IIIIRTY DAY WRITTEN REPORTS 6.9.1.9 Deleted.
REPORTING REQUIREh1ENTS FOR INCIDENT WHICH OC_C_URRED ON h1 ARCH 28.1979 6.9.1.10 Section deleted. All reporting requirements completed.
SERCIAL REPORTS 6.9.2 Special reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report.
6,10 RECORD RETENTION 6.10.1 The following records shall be retained for at least Ove years:
a.
Records of sealed source and fission detector leak tests and results, b.
Records of annual physical inventory of all sealed source material of record, c.
Records of changes made to the procedures required by SpeciGcations 6.8.1.d and e.
6.10.2 The following records shall be retained as long as the Licensee has an NRC license to operate or possess the Three hiite Island Facility, a.
Records and logs of unit operation covering time interval at each power level.
b.
Records and logs of principal maintenance activitics, inspection, repair and replacement of principal items of equipment related to nuclear safety and radioactive waste systems.
c.
ALL REPORTABLE EVENTS submitted to the Commission.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
Records of changes made to the procedures required by Specifications 6.8.1.a, b, c.
c, and f.
f.
Radiation Safety Program Reports and Quarterly Recovery Progress Reports on the h1 arch 28,1979, incident.
g.
Records of radioactive shipments.
h.
Records and logs of radioactive waste systems operations.
l THREE MILE ISLAND - UNIT 2 6-15
. t\\DMINISTRATIVE CONTROLS 1.
Records and drawing changes reflecting facility design modifications made to-systems and equipment described in the Safety Analysis Report, TER, SD, or Safety Evaluation previously submitted to NRC.
j Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
k.
Records of transient or operational cycles for those unit components designed for a limited number of transients or cycles.
1.
P.ecords of reactor tests and experiments.
m.
Records of training and qualification for current members of the unit staff, n.
Records of in-service inspections perfonned pursuant to these Technical Specifications.
o.
Records of Quality Assurance activities required by the Operating Quality Assurance Plan.
p.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59, q.
Records of meetings of the Plant Operation Review Committee (PORC) and the General Review Committee (GRC) and reports of evaluations prepared by the SRG or by the IOSRG, if applicable to TMI-2.
r.
Records of the incident which occurred on March '28,1979.
s.
Records of unit radiation and contamination surveys.
t.
Records of radiation exposure for all individuals entering mdiation control areas, u.
Records of gaseous and liquid radioactive material released to the environs.
v.
Records of reviews perfonned for changes made to the OFFSITE DOSE CALCULATION MANUAL, 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent 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 HIGII RADIATION AREA In lieu of the " control device" or "alann signal" required by Paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area shall be controlled as specified in the Radiation Protection Plan.
TIIREE MILE ISLAND - UNIT 2 6-16
ADMIMSTRAIlVE CONTROLS 6.13 OFFSITE DOSE CALCULATION MANUAL (ODCM)
Changes to the ODCM:
a.
Shall be documented and records of reviews perfonned shall be retained as n: quired by Specification 6.10.2 v, This documentation shall contain:
1)
Sufficient infonnation to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)
A detennination that the change will maintain the level of radioactive effluent control required by 10 CFR 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 setpoint calculations.
b.
Shall become effective after review and acceptance by GPU Nuclear management.
c.
Shall be submitted to the Commission in the fonn of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the repor1 in which any change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date -
(e.g., month / year) the change was implemented.
l TIIREE MILE ISLAND - UNIT 2 6-17 r'
d w
^.
r-
TIIREE MILE ISLAND - UNIT 2 RECOVERY OPERATIONS PLAN 4
1 INDEX i
SURVEILLANCE REOUIREMENTS SECTION PAGE 4.1 WATER INJECTION COOLING AND.J1EACTIVITY CONTROL SYSTEMS 4.1.1-BORATION CONTROL............................. 4.1 - 1 4.1.1.1 Borated Cooling Water Injection..................,..... 4.1-2 4.1.1.2 Boron Concentration Reactor Coolant System and........,....
4.1-2 Refueling Canal 4.1.1.3 Baron Concentration Fuel Tmnsfer Canal (Deep End)...........
4.1-2 4.1.1.4 Baron Concentration Spent Fuel Pool 'A' 4.1-2 4.1.3 CONTROL ASSEMBLIES 4.1-2 4 3 INSTRUMENTATION m
4.3.1 NEUTRON MONITORING INSTRUMENTATION,......,....
4.3-1 4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION
........... 4.3-1 4.3.3 MONITORING INSTRUMENTATION 4.3-1 4.3.3.4 Meteorological Instnnnentation................
4.3-1 4.3.3.5 Essential Parameters Monitoring Instrumentation..............
4.3-1 4.3,3.7 Chlorine Detection Systems..........................,. 4.3-1 4.3.3.8 Fire Detection.......,
4,3-13 4.4 REACTOR COOLANT SYSTEhl 4.4.1 REACTOR COOLANT LOOPS.........,,.,.........,
4.4-1 4.4.2 REACTOR VESSEL WATER LEVEL MONITORING.........
4.4-1 4.4.9 PRESSURE / TEMPERATURE LIMITS...................
4,4-1 4.5 COMMUNICATIONS.
.......... 4.5-1
- 4. 6 CONTAINMENT SYSTEMS..........,.....,,..............- 4.6-I 4.6.1 PRIMARY CONTAINMENT 4,6.1.1 Containment Integrity '...........,
....,............ 4.6-1 4.6.1.2 Containment Isolation............................. 4,6-1 4.6.1.3 Containment Air Locks (Mode 1) 4.6-1
- THREE MILE ISLAND - UNIT 2 i
_ - =.
SURVEILLANCE REOUIREh1ENTS 4.3 INSTRUh1ENTATION 4.3.1 NFAUTRON_blOElTORING INSTRUh!ENTATION 4.3.1.1 Each intennetliate and source range neutron monitoring instrumentation channel shall be demonstrated OPERABLE by the perfonnance of the CIIANNEL CIIECK, CllANNEL CALIBRATION and CilANNEL FUNCTIONAL TEST operations at the frequency shown in Table 4.3-1.
D.,2 ENDINEEl@D SAFETY FEATURE ACTUATLON SYSTEh! INSTRUMfdITATION Deleted 4.3.3 h10NITORING INSTRUh1ENTATION MEff;DROLOGICAL INSTRUALERTATION 4.3.3,4 Each of the meteorological monitoring instmmentation channels shall be demonstrated OPERABLE by the perfonnance of the CHANNEL CIIECK and CIIANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5.
ESSENTIAL PARAA1ETERS htONITORING INSTRUh1ENTATION 4.3.3.5 Each of the Essential Parameters hfonitoring Instrumentation channels shall be demonstrated OPERABLE by perfonnance of the CIIANNEL CIIECK and CIIANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.
CliLOillNE DETECTION SYJ_TEh1S 4.3.3.7 Each chlorine detection system shall be demonstrated OPERABLE by perfonnance of a CllANNEL CIIECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and a CIIANNEL FUNCTIONAL TEST at least once per 31 days. At least once per 18 months, the following inspections and maintenance shall be performed:
a.
Check constant head bottle level and refill as necessary, b.
Clean the sensing cells, I
c.
Check flow meter opemtion and clean or replace filters and air lines as necessary.
I d.
Check air pump for proper operation, and c.
Verify that the detector responds to HCL.
TIIREE h1ILE ISLAND - UNIT 2 4.3-1
2 A
4-ap S 3--6 a-W--,m L-s
=2 6
e asn,-.
4
,ab-m k
u k,An.,
n, I @ LE 4.3-3 1RDIATION MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS DELETED b
- THREE MILE ISLAND - UNIT 2 4.3-4
.- l
- i'l TIIIS PAGE INTENTIONALLY LEFT BLANK N
d THREE MILE ISLAND - UNIT 2 4.3-5 q
T-4'*J-"'
~
... - -. ~ -.. -
s t
, k
+
A h
t THIS PAGE INTENTIONALLY LEFI' BLANK T
4 P
. THREE MILE ISLAND - UNIT 2 4.3-6 4
m
.--<m--.~.U,e s
,.c
k tills PAGE INTENTIONALLY LEFT BLANK TIIREE MILE ISLAND - UNIT 2
-4.3-7
.r--
--c
<n..
.e---
y A
maA
m A
A
>4
- +-
-4s.-
-a
& s a,.L 1
4 o
-,-a-A b,,
b w..
THIS PAGE INTENTIONALLY LEFT BLANK l
l -,
- THREE MILE ISLAND - UNIT 2 4.3-8
a_.4.,a.,AJ+
4 L
55a 4 a44-E 4
4.-.-
4 w 24 2-4-
E.%AMm -
44eL-4.a a>&
Al.4.4 m
at w, m
W.'La.hh42 m 45 4LL A e d 4-g M. #
+
a
- .4
&i,whd. @Js.
_&& w4. A4.sk A
B b
r i
k THREE MILE ISLAND - UNIT 2 TECHNICAL SPECIFICATIONS APPENDIX B 1
J l
5 1
.E,,.,.
1 TIIREE MILE ISLAND NUCLEAR STATION UNIT 2 ENVIRONMENTAL TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION PAGS 1.0 DEFINITIONS.................
1-1 2.0 LIMITING CONDITIONS FOR OPERATION..
2-1 3.0 ENVIRONMENTAL MONITORING,.
.....3-1 4.0 SPECIAL STUDIES AND REQUIREMENTS 4-1 4.1 RESIDUAL CHLORINE STUDY PROGRAM
'4-1 4.2 THERMAL PLUME MAPPING,.
..................4-3 4.3 IIYDRAULIC EFFECTS
.................4-4 4.4 EROSION CONTROL INSPECTION..
4 -5 4.5 HERBICIDE APPLICATIONS..
4-6 4.6 EXCEPTIONAL OCCURRENCES 4-7 4.6.1 UNUSUAL OR IMPORTANT ENVIRONMENTAL EVENTS 4-7 4.6.2 EXCEEDING LIMITS OF OTHER RELEVANT. PERMITS......... 4-7 5.0 ADMINISTRATIVE CONTROLS 5-1 5.1 RESPONSIBILITY 5.1 5.2 ORGANIZATION.....
. 5-I 5.3 REVIEW AND AUDIT 5-I 5.3.1 INDEPENDENT REVIEW
. 5-1 5.3.2 AUDIT RESPONSIBILITY..
5-3 5.4 STATE AND FEDERAL PERMITS AND CERTIFICATES......... 5-3 5.5 PROCEDURES
. 5-3 5.6 STATION REPORTING REQUIREMENTS...
5-6 5.6.I ROUTINE REPORTS
. 5-6 5.6.2 NONROUTINE REPORTS..
5-7 THREE MILE ISLAND - UNIT 2 i
IAILILDILCDNIliNTS SliG10N 1 % 0 13 5.6.2.a PF ohllrr R EPO RT................................. 5 -7 5.6.2.b TillRTY DAY RiiPORT.............
................57 5.6.2.c CONT 11NT OF NONROUTINil Rl! PORTS........
57 5.7 CIIANGES IN ENVIRONh111NTAL TECilNICAL SPECIFICATIONS AND PERh11TS................................. 5-8 i
i 5.7.1 CilANGliIN ENVIRONh! ENTAL TlicilNICAL SPECIFICATIONS.., 5-8 5.7.2 CilANGES IN PERh11TS AND CliRTIFICATIONS.............
5 8 5.8 Hl! CORDS RETENTION
....................,...,.58 i
i L
A TilREE hilLE ISLAND - UNIT 2 il
-.. -,... ~, -. -....
L0EEIN1110ES l
NEDES Pennit: NPDES Pennit is the National Pollutant Discharge Ellinination Systern Pennit No. PA0(X)9920 issued by the Environniental Protection Agency to hietropolitan Edison Coinpany. This pennh authorized hietropolitan Edison Cornpany to discharge froni Th!!NS, controlled waste water into the waters of the Cornrnonwealth of Pennsylvania, i
k 5
h 4
9 h
l TliREE hilLE ISLAND - UNIT 2 1-1
- -. -... - ~. -
21LlJMIII NG_COND1110N S.f0R.DPJAYDDN Deleted TIIREE MILE ISLAND - UNIT 2 2-1 k
10 ENVIRONMPETALMONITOldNG Deleted I
m.
TIIREE hilLE ISLAND UNIT 2 3-1 i
_____m_.._-
]'
i 3
5.3.2 AUDlI.RiiS!!QNS]DillTX Deleted 5.4 STATHAND_EEllERAL_l'!iRh11TS_AND.fERIlEICNUiS Section 401 of PL 92-500, the Fedend Water Pollution Control Act Amendment of 1972 requires any applicant for a Federal license or pennit to conduct any ac:ivity which inay result in any discharge into navigable waters to provide the licensing agency a certification froin the State having i
jurisdiction that the discharge will comply with applicable provisions of Sections 301,302,306, and 307 of the FWPCA. Section 401 of PL 92-500 funher requires than any certification provided under this section shall set forth any ef0uent limitations and other limitations, and monitoring requirements necessary to assure that any applicant far a Federal license or pennit will comply with the applicable limitations.
Cenifications provided in accordance with Section 401 set fonk
[
conditions on the Federal license or pennit for which the cenification is provided. Acconlingly, the licensee shall comply with the requirements set forth in the 401 certification dated November 9,1977 or its currently applicable revision, issued to the licensee by the Pennsylvania Depanment of F.nvironmental Resources, which requires, among other things, that the licensee comply with effluent limitations stipulated in NPDES pennit PA-0009920, effective January 30, 1975.
i Subsequent revisions to the pennits and/or eenifications will be accommodated in accordance with the provisions of Subsection 5.7.2.
5.5 l'ROCEl?lRiiS Deleted i
l 5.6 STATION _REPORIJNG REQlJ1RiiMENTS 5.6.I ROKl'lHILRilP_QRTS Deleted 5.6.2 EONROUTIND_lWPORTS i
A repon shall be submitted in the event that an Exceptional Occurrence as speciGed in Section 4.6 l
occu rs. Repon shall be submitted under one of the report schedules described below.
5.6.2.a PROMIT _ REPORT Those events specified as prompt report occurrences shall be reponed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile transmission to the NRC followed by a written repon to the NRC within 30 L
- days, i
l TilREE Mil.E ISLAND - UNIT 2 53
I r
5.6.2.b IlilRTY DAY EVENT l
1 Nonroutine events not requiring a nrompt repan as described in Subsection 5.6.2.a, shall be
{
reported to the NRC either within 30 days of their occurrence or within the time limit specified by the reponing mquirement of the corresponding cenification or pennit issued pursuant to Sections 401 or 402 of PL 92-500, whichever time duration following the nonroutine event shall msult in the carlier submittal.
I 5.6.2.c.CONIENT OF NOM 0llTINE REPORTS Written 30-day repons and, to the extent possible, the preliminary telephone, telegraph, or facsimile repons shall (a) describe, analyre, and evaluate the occurrence, inchiding extent and magnitude of the impact, (b) describe the cause of the occurrence, and (c) indicate the corrective action (including any significant changes made in procedures) taken to preclude repetition of the occurmnce and to 1
prevent similar occurrences involving similar components or systems.
5.7 CllANGjiSELENVillONMENTAL TECllNICAL SPECIFIC ATIONS AND PERMITS 5.7.1 CilANGE IN ENVIJtONMENTAL TEC11NICAL SPECIFICATIONS Request for changes in environmental technical specifications shall be submitted to the NRC for review and authorization per 10 CFR 50.90. The request shall include an evaluation of the environmentalimpact of the proposed change and a supponingjustification. Implementation of such requested changes in ETS shall not commence prior to incoqmration by the NRC of the new I
specifications in the license.
5.7.2 C11ANGES IN PERMITS AND CERTIFICATIONS Changes or addition to required Federal, State, local, and regional authority pennits and cenificates for the protection of the envimnment that penain to the requirements of these ETS shall be reponed to the NRC within 30 days. In the event that the licensee initiates or becomes aware of a request for changes to any of the water quality requirements, lhnits or values stipulated in any certification or pennit issued pursuant to Sections 401 and 402 of PL 92-500 which is also the subject of an ETS reponing requirement, NRC shall be notified concurrently with the authorizing agency. The notification to the NRC shall include an evaluation of the environmental impact of the revised requirement, limit or value being sought.
If, during NRC's review of the proposed change, it is-detennined that a potentially severe environmental impact could result from the change, that N'RC will consult with the authorizing agency to detennine the appropriate action to be taken.
TIIREE MILE ISLAND - UNIT 2 54 i
we w - =e i-v v,te-v----r,--r-e e<-i--**m--
aw
--,e-,=,---w,-
4-w+.-
.s-,w--
- -w
.w-<
.-=,e,-
..--ww
<> ~ - - - -- - -
5.8 RiiGlilDJi10HliNIlON Records and logs relative to the following areas shall be inade and retained throughout the term of the operating license. These records and logs shall bc inade available to NRC on request, a.
Records and drawing changes detailing station and unit design changes made to system and equipment which conid potentially affect the environment.
b.
Records of all data from envimnmental monitoring, surveillance and study activities required by these environmental technical specifications, i
i T
e I
I TilREE MILE ISLAND - UNIT 2 5-5 1
i Tills PAGE INTENTIONALLY I. EFT 13 LANK t
k
~ l
?
+
l TIIREE hilLE ISLAND - UNIT 2 5-6
(.-
4 l
,., =.. -.
w
..yu
-~-,,_,m-_J--.
,.-.4
....~.., _,
-~.. - -.
m.
e Tills l'AGli INTliNTIONAl.1,Y LillT llLANK Tilitlill MILII ISLAND - UNIT 2 5-7
f-F-
l h
i Tills I' AGE INTENTIONALLY LEFT BLANK i
i TIIREE MILE ISLAND - UNIT 2 5-8 www,<w,,r-,-r-,-,~,w-_,.,
Tills PAGE INTENTIONALLY LEFT BLANK O
TIIREE MILE ISLAND - UNIT 2 5-9