ML19210A390

Tech Specs Change Request 41 to Amend DPR-50,App A,To Prevent Steam Generator Tube Degeneration by Controlling Contamination of Secondary Coolant

ML19210A390
Person / Time
Site:	Three Mile Island
Issue date:	10/29/1976
From:	Arnold R METROPOLITAN EDISON CO.
To:
Shared Package
ML19210A381	List: ML19210A380 ML19210A390
References
NUDOCS 7910290616
Download: ML19210A390 (8)

Text

.METROPOLITAN EDISON COMPANY JERSEY CENTRAL PCWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Soecification Change Request No. h1 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A 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 A are also included.

FETROPOLITAN EDISON COMPANY

/s/ R. C. Arnold By Vice President-Generation 29th October Sworn and subscribcd to me this day of , 1976./s/ L. L. Lawyer Notary Public 1A69 047 g,910.,9 o C,/ b

-v.

..Metropolitan Edison Company (Met-Ed)

Three Mile Island Nuclear Station Unit I (TMI-1)

Docket No. 50-289 Operating License No. DPR-50 Technical Specification Change Recuest No. h1 The Licensee requests that the attached section 3.17 be added and race h-10 replace the corresponding existing Technical Specification page.

Reasons for Procosed Change To prevent steam generator tube degradation by controlling contamination of the steam generator secondary coolant.

Safety Analysis Justifyine Protosed Chance This change request imposes more restrictive limits on the steam generator secondary coolant. Therefore, no unreviewed safety question is involved.

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'.TABLE OF CONTENTS P, age.Section TECHNICAL SPECIFICATIONS 1-1 1 1)EFINITIONS 1-1 1.1 RATED POWER 1.2 REACTOR OPERATING CONDITIOh1

, 1-1 1-1 1.2.1 COLD SHUTDOWN 1-1 1.2.2 HOT SHUTDOWN 1-1 1.2 3 REACER CRITICAL

-1.2.h HOT STANDBY 1 1-1 1.2 5 POWER OPERATION 1-1 1.2.6 REWELING SHUTDOWN 1-2 1.2 7 REFUELING OPEATION 1-2 1.2.8 REFUELING INTERVAL 1.29 STARTUP.1-2 l-2 1.2.10 TAVG 1-2 1.2.11 HEATUP-COOLDOWN MODE 1-2 1.2.12 STATION, UNIT, PLANT, AND FACILITY l-2 1.3 OPERABLE 1.h PROTECTIVE INSTRUMENTATION IDGIC 1-2 1; 2 1.h.1 INSTRUMENT CHANNEL 1-2 1.h.2 REACTOR PROTECTION SYSTEM

, 1-3 1.h.3 PROTECTION CHANNEL 1.h.h REACTOR PROTECTION SYST M IDGIC 1-3{ENGINEERED SAFETY FEATURES SYSTEM l-3 1.k.5 1.k.6 DEGREE OF REUNDANCY 1-3 1.5 INSTRUMENTATION SURVEILLANCE 1-3 l-3 1.51 TRIP TEST 1-3 152 CHANNFL TEST 1.5.3 INS %UMENT CHANNEL CHECK 1-3 1 5.h INSTRUMENT CHAICTEL CALIBRATION 1h 1h 1.55 HEAT BALANCE CHECK 1.5.6 HEAT BALANCE CALIBRATION 1L 1.6 POE 3 DISTRIBUTION 1-5" 1.6.1 QUADRANT POWE TILT 1-3 1.6.2 REACTOR MWE IMBALANCE l-5 1.7 CONTAINMENT INTEGRITY 1-5 2 SAFETY LIMITS AND LIMITING SAFETY SYSTM SETI'INGS 2-1 2.1 SAFETY LIMITS, REACTOR CORE 21 2.2 SAFETY LIMITS, REACTOR SYSTm PRESSURE 2_k 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTION g TRUMENTATION 2-3 , 3 LIMITING CONDITIONS FOR CP9ATIE 31 1469'049 (31 REAC'ICR C00LA';T SYe"g j.1 ,'3 1.1 OPEATIONAL COMNNE:f S 3-1%3.1.2 PRESSURI7.ATION, HEATUP, AND C00LDOWN LIMITATIONS 3- 3 i i

...-(Pages 3-61 thru 3-66 pending approval of Tech. Spec.

Change Request 7) 1469 050.3-61

.(Pages 3-67 +-uru ~7_65 pendir,E SPProval of Tech Spec. ch , equest 19)

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'.3.17 SECONDARY WATER CHDCSTRY Apolicability Applies to secondary system water chemistry during hot standby, startup, and power operation.

Objective , To prevent steam generator tube degradation by controlling contamination of the steam generator secondary coolant.

Specification (Refer to Table 3.17-1) 3.17.1 With the total cation conductivity of the final feedwater to any steam generator exceeding its steady state limit but within its transient limit, restore the conductivity to within its steady state limit within 2h hours; or, be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.3.17 2 With the total cation conductivity of the final feedvater to any steam generator exceeding its transient limit, initiate action immediately to restore the conductivity to within its steady state limit within h hours; or, be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3.17.3 With the pH of the final feedwater to any steam generator exceeding its stecdy state limits but within its transient limits; restore the pH to its steady state limits within 2h hours; or, be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3.17.h With the pH of the final feedvater to any steam gecerator exceeding its transient limits, initiate action immediately to restore the pH to its steady state limits within k hours; or, be in hot shutdown

within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

lt Bases', Contamination of the steam generator secondary coolant may cause tube degradation and impair tube integrity. Generally, the most severe contamination results from condenser inleakage of caustic forming impurities that may accumulate on the secondary side of the steam generator, or on the high heat flux surfaces of the steam generator tubes and can lead to the potential for intergranular stress corrosion crucking.

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• ., , Mcnitoring of the condenser condensate by cation conductivity is an effective means of detecting condenser tube inleakage. The leakage rate can then be determined by comparing the anion concentration in the condensate with the anion concentration in the condenser cooling water.The cation conductivity of the steam generator final feedwater vill indicate how effectively the condensate polishing units are removing contaminants and can indicate need for polisher regeneration.

Since full flow condensate polishing is employed, no limit is assigned to the condenser condensate. Monitoring of this parameter vill identify condenser tube leakage. Monitoring the total solids in the final feedvater is not accurate at the low levels that exist in once through steam generators operated with volatile treatment schemes.

Cation conductivity is a more sensitive means of determining the concentrations of contaminants at these low levels.

In addition, known corrosive and scaling contaminants can be monitored during periods of increased cation conductivity in order to determine the extent of condenser leakage and steam generato" contamination.

I Controlling the secondary water chemistry within the specified limits

'will control the potential accumulation of corrosive impurities in the steam generator and minimise tube degradation. These limits provide reasonable assurance that the conditions in the steam generator will minimize the potential for tube degradation during all conditions

!of operation. and postulated accidents. These measures ensure the

'continued protection of the steam generator tubing which is an essential part of the reactor coolant pressure boundary.

The terms " Steady State" and " Transient", as used in this section, apply to chemistry parameters rather than to plant operating

'conditions.

!TABLE 3.17-1 Total Cation Conductivity (umho/cm)

Final Feedvater 0 at 25 C Steady State Limit

<05 Transient Limit

< l.0 25*C Steady State Limit 9 2 < pH < 9.6 Transient Limit 9.0 5,pH 5.9.8

.3_85)kb

'.., TABLE h.1-3 (Continued)

Item Check Frequency 11.Sodium Thiosulphate Concentration Quarterly and after Tank each makeup I ~1 ,2^19 Condenser Partition Partition Factor Once if primary /

Factor secondary leakage developes, i.e.: Gross Beta-Garrn on secondary side of OTSG is ,g greater than 2 x 10 micro curies per cc anu evidence of fission products is present 13 Final Feedvater a.Cation Conductivity Continuous monitor once per 2h hour period if monitor is not operable. (h) b.pH Continuous menitor once per 2h hour period of monitor is not operable.(h)

(1) When radioactivity level is greater than 10 percent of the limits of Specification 3.1.h, the sampling frequency shall be increased to a minimum of 5 times per veek.

(2) ~E determination vill be started when the 15 minute gross degassed beta-gamma activity analysis indicates greater than 10 pCi/=1 and vill be redetermired each 10 uCi/ml increase in the 15 minute gross degassed beta-gamma activity analysis. A radio chemical analysis for this purpose shall consist of a quantitative measurement of 95 percent of radionuclides in reactor coolant with half lives of >30 minutes.

(3) When the 15 minute gross degassed activity increases by a factor of two above background, an iodine analysis will be made and performea thereafter when the 15 minute gross degassed beta-gamma activity increases by 10 percent.(L) Not required with the reactor sub-critical.

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