|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092K5471995-09-20020 September 1995 Revised Tech Spec Pages 4-31,4-32 & 4-33,incorporating Change in TS Section 4.4.1.5 ML20091L2911995-08-23023 August 1995 Proposed Tech Specs Page 6-11a,incorporating Ref to 10CFR20.1302 ML20087F4921995-08-11011 August 1995 Proposed TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements ML20085N1601995-06-22022 June 1995 Proposed Tech Specs Revising Replacement Pages in Package & Remove Outdated Pages,In Response to NRC Request for Addl Info ML20084L4351995-06-0101 June 1995 Proposed TS 5.3.1.1,describing Use of Advanced Clad Assemblies ML20084N3501995-06-0101 June 1995 Proposed Tech Specs,Deleting RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084B3361995-05-24024 May 1995 Proposed Tech Specs Re Change in Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7841995-05-17017 May 1995 Proposed Tech Specs,Consisting of Change Requests 252, Removing Chemical Addition Sys Requirements from TS to COLR ML20079A7811994-12-23023 December 1994 Proposed Tech Specs Page 3-32a ML20069A6781994-05-20020 May 1994 Proposed Tech Specs,Supporting Cycle 10 Control Rod Trip Insertion Time Testing ML20065M6831994-04-19019 April 1994 Proposed Tech Specs,Reflecting Deletion of Audit Program Frequency Requirements ML20065K0451994-04-11011 April 1994 Proposed Tech Specs Reflecting Relocation of Detailed Insp Criteria,Methods & Frequencies of Containment Tendon Surveillance Program to FSAR & Providing Direct Ref to Existing Tendon Surveillance Program ML20073C7731994-03-22022 March 1994 Proposed Tech Specs Re Control Rod Trip Insertion Time Testing 1999-09-01
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20096F0521995-12-31031 December 1995 TMI-1 Cycle 11,Startup Rept ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program 1999-09-01
[Table view] |
Text
'
^
/ .22 17271]
" m,, == - Regulatog gCy.
METROPOLITAN EDISON COMPANY := := n : . . 2 := : i : := n POST CFFICE BOX 542 R * "* PENNSYL /ANI A 19603 TELEPHONE 215 - 929 3601
, f '. N i kt
/y
% //g
/g(l8thic Y August 21, 1975 GQL lh10 IUt N
- $.EcI' d -
\[- g6 { c: _ - .31, Mr. A LAS sso I -
Cl Director, Division of Reactor Licensing @ j!
U.S. Nuclear Regulatory Commission * ?, .,
. y/
Washington, D.C. 20555 '(/
No ~ .
7;/-l/
Dear Mr. Giambusso:
Docket No. 50-289 Operating License No. DPR-50 Technical Specification Change Request No.18 Enclosed are three signed originals and thirty-seven conformed copies of Technical Specification Change Request No.18 requesting amendment to Appandix B of Operating License No. DPR-50. As a part of this request, proposed replacement pages for Appendix B are also enclosed.
Also enclosed is one signed copy of a Certificate of Service of Technical Specification Change Request No.18 to the chief executives of the township and county in which the f acility is located.
Sincerely ,
R. C.' Arnold Vice President RCA:JFV:pa Enclosures : 1. Technical Specification Change Request No.18 (Three (3) Originals /37 Copf es)
- 11. Certificate of Service for Proposed Technical Specification Change Request No.18 File 7.7.4.3.3.1/20.1.1 1459 274
.,2 7910240 7 7
. . s C
METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Cperating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 18 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix B to Operating License No. DPR-50 for Three Mile Island Nuclear Station Unit 1. As a part of this request, proposed replacement pages for Appendix B are also included.
METROPOLITAN EDISON COMPANY By [ -
Vice Prefident-Generation Sworn and subscribed to me this =_R/d day of d e w # __, 1975 cb 12 Notary Public w
RITA' M. POWERS Notary Public, Muhlenberg Twp., Berks Co.
My C:mmiss cn Expires Septemter 30,1978 1459 275
s Three lule Island Nuclear Station Unit 1 (TMI-1)
Operating License DPR-50 Docket No. 50-289
- TECHNICAL SPECIFICATION CHANGE REQUEST NO. 18.a. -
Licensee requests that certain changes , as hereinaf ter described, be made in Appendix B of the TMI-1 Technical Specifications. A copy of the affected pages with these changes indicated is attached.
Proposed Change Page 13, Subsection 2.2.3, pH; add the following qualifying phrase to the Specification:
. . . except that during those periods when the intake pH is greater than 9.0, the plant discharge pH shall not exceed the plant intake pH, and that during those periods when the intake pH is less than 6.0, the plant dischar te pH shall not be lower than the intake pH."
Reason for Requesting Change The subject change will eliminate the need to have to report certain conditions which the station was not responsible for having created.
The fact that fewer reports will thus have to be written will result in a cost savings, which is the reason for requesting this change.
Environmental Analysis Justifying Change The proposed change, if implemented, will not have any adverse effect on the environment, in that during periods of unusual river water conditions (i.e. , pH less than 6.0 or greater than 9.0) , the pH condition of the water which is returned to the river will be no worse, and may actually be better, than the pH condition of the river water itself.
Cost-Benefit Analysis Supporting Change No additional cost will result from implementation of the proposed change, and by making this one Limiting Condition for Operation more flexible, implementation of the proposed change will result in fewer reportable incidents, which, in turn, will result in a decrease in the number of man-hours which will have to be spent in reporting such incidents.
1459 276
- TECHNICAL SPECIFICATION CHANGE REQUEST NO.18.b . -
Proposed Change Page 14, Subsection 2.2.3. , pH ; change the pH range referenced in the Bases from "6.0 to 9.0" to "5.0 to 10.0."
Reason for _ Requesting Change The reason for requesting the subject change is to make the Technical Specifications more closely reflect the actual pH conditions of the Susquehanna River. From recent sampling of the river in the vicinity of TMI-1, it appears that these conditions are more accurately represented by the range 5.0 to 10.0.
Environmental Analysis Justifying Change Because the proposed change merely serves to correct some data in the basis for a Specification, it does not constitute a change to the Technical Specification and will not cause any adverse effects to the environment. (Note: The change Specification derived from this changed Basis is addressed in the above Change Request.)
Cost-Benefit Analysis Supporting Change No additional costs will result directly from implementation of the proposed change. The benefits are as described in the above Change Request.
- TECHNICAL SPECIFICATION CHANGE REQUEST NO. 18.c. -
Proposed Change Page 45, Section 4.2.1, objective. Delete " dissolved oxygen" from the second sentence.
Reason for Requesting Change The Specification of Section 4.2.1 does not require that dissolved oxygen in the river water discharge be monitored (this requirement was removed during the draf t stage of the Technical Specifications) ;
therefore, this change is being requested so that the Technical Specifications can be made more internally consistent.
Environmental Analysis _ Justifying Change Because the proposed change merely serves to make the Technical Specifications more consistent and does not actaally change any of the requirements of those specifications, it will not cause any adverse effects to the environment.
Cost-Benefit Analysis Supporting Change No additional costs and no benefits will result from implementation of the proposed change in that all the requirements of the Technical Specifications will remain the same.
1459 277
- TECHNICAL SPECIFICATION CHANGE REQUEST NO. 18.d. -
Proposed Change Page 47, Section 4.2.1, Bases. Delete the third paragraph.
Reason for Requesting Change The Specification of Section 4.2.1 does not require that dissolved oxygen in the river water discharge be monitored; therefore, there is no need to have dissolved oxygen referenced in the Bases of this section and removal of this reference would serve to make the Technical Specifications more internally consistent.
Environmental Analysis Justifying Change The environmental Analysis is the same as for Change Request No.18.d.
above.
Cost-Benefit Analysis Supporting Change The cost-benefit analysis is the same as for Change Request No. 18.d.
above.
1459 278
- LT -
Eases The posteperational aquatic chemical surveillance program of the Susquehanna River in the vicinity of the Three Mile Island Nuclear Station vill begin upon the issuance of an operating license. This program is designed to provide quantitative informatien on chemical discharges frcm the plant. Chlorine discharge concentrations are monitored centinually by installed plant instrumentaticn.
It is expected that there vill be no significant difference in the concentration of heavy metals between the plant river water intake and discharge. Potential changes in concentrations of heavy metals due to passage of water through the plant could result from discharge of neutralized regenerant vastes, cerrosion of river water piping or leakage of corrorien inhibitors. The metals selected for =cnitoring vere selected based on metals kncvn to be in the river, materials used in the ccustructicn of river water syste=s and the ecmposition of the corrosion inhibitor used in the closed cooling systems. Since no significant increase in concentrations of heavy metals is expected, the measurement downstream is unlikely to be of value in defining the chemical plume.
1 The only significant addition of dissolved solids to plant effluent is the discharge of neutralized regenerant vastes from the cycle makeup demineralizers. In addition, dissolved solids are concentrated in cooling tower blevdown due to evaporatien loss in the ecoling towers. Since limits are placed on discharge of dissolved solids by Specificatien 2.3.2 and concentrations are acnitored en a minimum veekly frequency during plant operation, the inclusion of this parameter with the postoperaticnal surveillance progra= after a period of 1 - 3 years is censidered unnecessary.
There is expected to be no significant addition of suspended solids to the plant discharge. A period cf 1 - 3 years inclusion of th.s parameter within the postoperational surveillance program is con-sidered sufficient to justify efficiency and reliability of plant 1459 279
h5 -
chemically mialyzed for drift minerals.
This progra= vill be continued for two years.
Bases Since so=e potential exists for damage to area vegetation frca cooling tower drift and since the actual effect is unkncvn, specific report levels, protection limits, or the need for such =easures cannot be determined at this time. The study described herein vill provide information needed to establish a protection limit or report level er to establish that the =easurement of the drift effect is unnecessary due to insignificant i= pact.
Measurement of species composition, relative abundance , and relative dc=inance vill determine changes in the natural vegetative cc=munity that may be due to plant operation. Increases or decreases in cer-tain species should beccme evident if they do in fact occur. Examina-tion of vegetation for physical disorder 3 vill indicate if salt damage is cecurring with respec', to actual injury or death of plants.
This information vill be supplemented by analyses to determine con-centrations of certain minerals in the plant material.
h.2 Chemical h.2.1 Aquatic Objective To define operational surveillance or special studies of aquatic chemical effects derived frcm the station. The che=ical parameters of this study will include chlorine, heavy metals , suspended solids I and dissolved solids. Alkalinity is related to the pH of the water and may be included if deemed necessary in checking pH =enitcring at the river water discharge.
Specification The aquatic chemical surveillance program shall be conducted as follows:
1459 280
2.0 LIMITING CONDITIONS FOR OPERATION 2.2.3 pH Monitoring Requirement .
Objective Objective The purpose of this specification is to limit The purpose of this specification is to ensure the pH of plant discharges to values which compliance with Specification 2.2.3 will produce no harmful effects to the Susquehanna River.
Speci ficat ion Specification The pH, as measured at the plant discharge and A determination of the pH of the contents of each at the waste neutralizing tank prior to release, tank of neutralized regenerant vastes will be shall have a value of not less than 6.0, nor made prior to release using installed instru-more than 9.0, except that during those periods mentation. All necessary adjustments to meet the when the intake pH is greater than 9.0, the plant specification vill be made prior to initiation of discharge pH shall not exceed the intake pH, and the release. If the installed instrumentation is that during those periods when the intake pH is out of service, the necessary analyses will be less than 6.0, the plant discharge pH uhall not performed prior to initiating the discharge using be less than the intake pH. laboratory instrumentation. An analysis for pH vill be performed on a sample taken from the plant river water discharge during the release of each tank of regenerant vastes, or at weekly intervals as a minimum frequency.
--- Bases Bases b
LJ7 The pH of the Susquehanna River as measured in Discharge of neutralized regenerant vastes is the
'I) the vicinity of Three Mile Island is variable only normal plant operation which could cause a and values spanning almost the entire range change in the pH of the discharge since all sumps p)
CO
2.0 LIMITING CONDITIONS FOR OPERATION Bases (Cont'd) Bases (Cont'd) 5
- from 5.0 to 10.0 have been recorded. Limiting and drains which are potential receivers of the pH of discharge to the normal range of chemicals are collected in this tank.
values insures that no pH related damage to lk river ecosystems or biota vill result.
The limits on the pH of the vaste neutralizing tank dischar6e vill prec] 2de sizable changes in the pH of the discharge to the river. For example, adding 300 gpm of pH 9 0 neutralizing tank discharge to a pH 8.0 stream at 17,250 gpm would raise its pH a calculated 0.06 unit ,
assuming no buffering action.
2.3 RADI0 ACTIVE DISCHARGES 2.3.1 Liquid Effluents Monitoring Requirements Applicability Applies to the controlled release of radio-O active liquids from TMI Unit 1.
Objective Objective To define the limits and conditions for the To ensure that radioactive liquid releases controlled release of radioactive effluents from the facility are within the limits of
} to the environs to ensure that these releases Specifications 2.3.1 a through e.
sg)
N CD N
r j' e t
f L' e /j[:o. .
,; *o s '
l L..
- Q"l ~
\y\
QY ;s'..,N.. , , : p'-)l' j UNITED STATES OF AMERICA ' ,'
NUCLEAR REGULATORY COMMISSION k~0Y)s..V 6- 2
IN THE MATTER OF DOCKET No. 50-289 OPERATING LICENSE NO. DPR-50 METROPOLITAN EDISON COMPAff This is to certify 4 hat a copy of Technical Specification Change Request No.18 to Appendix $ of the Operating License for Three Mile Island Nuclear S tation, Unit 1, dated August ??.,1975, and filed with the U.S. Nuclear Regulatory Commission Augus : 21, 1975, has this 21st day August, 1975, been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania, and of Dauphin County, Pennsylvania, by deposit in th- United States Mail, addressed as follows:
Mr. Weldon B. Arehart, Chairman Mr. Charles P. Hoy, Chairman Board of Supervisors of Board of County Commissioners of Ldadonderry Township Dauphin County R.D. #1, Geyers Charch Road Dauphin County Courthouse Middletown, Pennsylvania 17057 Harrisburr, Pennsylvania 17120 METROPOLITAN EDISON COMPANY By ) L Vice Preir/ident-Generation 1459 283 8972