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Corrected TS Pages 3-21,4-5a,4-9,4-38 & 6-3 to Amends 211 & 212 to License DPR-50.Pages Failed to Reflect Previously Approved Changes Granted in Amends 203 & 204 in Case of Amend 211 & 207 in Case of Amend 212
	ML20209D665
Person / Time
Site:	Three Mile Island
Issue date:	07/08/1999
From:	; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20209D634	List: ML20209D629; ML20209D637; ML20209D665;
References
	NUDOCS 9907130194
	Download: ML20209D665 (5)
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, 3.3 EMERQEEC.Y CDRE COOLING. RFA._CIQ.R BUILDING.EMERQENCY COOLJNG .

AND REACTOR BUJ.LDING.S; a.Q S.YSIEMS i

( Aeolicability

. Applies to the opc.ti m status of the emergency core cooling, reactor building emergency cooling,

! and reactor building spray systei,2 Obiective l-l To define the conditions necessary to assure immediate availability of the emergency core cooling, -

l reactor bui! ding emergency cooling and reactor building spray systems.

Soecification 3.3.1 The reactor shall not be made critical unless the following conditions are met:

3.3.1.1 Iniection Systems

a. The borated water storage tank shall contain a minimum of 350,000 gallons of.

water having a minimum concentration of 2,500 ppm boron at a temperature not less than 40 F. If the boron concentration or water temperature is not within limits, restore the BWST to OPERABLE within 8 hrs. If the BWST volume is not within limits, restore the BWST to OPERABLE within one hour.

Specification 3.0.1 applies.

b. Two makeup pumps are operable in the engineered safeguards mode powered from independent essential buses. Specification 3.0.1 applies.

c. Two decay heat removal pumps are operable. Specification 3.0.1 applies.

d. Two decay heat removal coolers and their cooling water supplies are operable.

(See Specification 3.3.1.4) Specification 3.0.1 applies.

l

e. Two BWST level instrument channels are operable.

f. The two reactor building sump isolation valves (DH-V6A/B) shall be remote-manually operable. Specification 3.0.1 applies.

3.3.1.2 Core Flooding System

a. Two core flooding tanks each containing 940 30 ff of borated water at 600 25 f psig shall be available. Specification 3.0.1 applies.

b. Core flooding tank boron concentration shall not be less than 2,270 ppm boron.

c. The electrically operated discharge valves from the core flood tank will be assured i open by administrative control and position indication lamps on the engineered l safeguards status panel. Respective breakers for these valves shall be open and

! conspicuously marked. A one hour time clock is provided to open the valve and l

remove power to the valve. Specification 3.0.1 applies.

9907130194 990709 PDR ADOCK 05000289 P PDR Amendment No.2I ,98 ,MS,203,211 3-21 Corrected by letter dated July 8, 1999 u

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4.4.4 Hydroaen Recombiner Systr Anolicability Applies to the testing of the hydrogen recombiner and associated controls.

Obiective ,

To verify that the hydrogen recombiner and associated controls are operable. -

4.4.4.1 Snecification

a. Perform a system functional test for the hydrogen recombiner each refueling interval by verifying that the reaction chamber gas temperature is maintained 21200*F for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b. Visually examine the hydrogen recombiner enclosure and verify there is no evidence of abnormal conditions each refueling interval. *

c. Perform a resistance to ground test for each heater phase each refueling interval and verify that the resistance to ground for any heater phase is it 10,000 ohms.

Bases The surveiliance program described above provides high assurance that the hydrogen recombiner system will be available to perform its post-LOCA function of maintaining the containment hydrogen concentration below 4.1 volume percent.

This system is not credited to mitigate any accident analyzed in Chapter 14 of the TMI-1 FSAR. The frequency of the surveillance of the hydrogen recombiner system is based on the safety significance of the system. TMI-1 FSAR Section i 6.5.3.1 indicates that the hydrogen recombiner system is not required until 9.8 days following a LOCA. This is adequate time to place a hydrogen recombiner in service.

4-38 (Page 4-38a deleted)

Amendnent No. 57, J55, J7),198 Corrected by letter dated July 8,1999

. 6.3 LLNIISTAFF QIJMJEICATJI.aNS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI /ANS 3.1 of 1978 for comparable positions unless otherwise noted in the Technical Specifications.

Licensed operators shall also meet the requirements of 10 CFR Part 55. Individuals who do not meet ANSI /ANS 3.1 of 1978, Section 4.5, are not considered technicians or maintenance personnel for purposes of determining qualifications but are permitted to perform work for which qualification has been demonstrated.

6.3.2 The management position responsible for radiological controls shall meet or exceed the qualifications of Regulatory Guide 1.8 of 1977. Each radiological controls technician /supervi or shall meet or exceed the qualifications of ANSI-N 18.1-1971, paragraph 4.5.2/4.3.2, or be formally qualified through an NRC approved TMI-l Radiation Controls training program. All radiological controls technicians will be qualified through training and examination in each area or specific task related to their radiological controls functions prior to their performance of those tasks.

6.3.3 The Shift Technical Advisors shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in unit design, response and analysis of transients and accidents 6.4 I_ RAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the '

direction of the plant training manager and shall meet or exceed the requirements and recommendations of Regulatory Guide 1.8 of 1977. Licensed operator training shall also meet the requirements of 10 CFR Part 55.

6.4.2 A training program for the Fire Brigade shall be maintained and shall racet or exceed the requirements of Section 600 of the NFPA Code .

6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL The Vice President of each division within GPU Nuclear, Inc. shall be responsible for ensuring the preparation, review, and approval of documents required by the activities described in 6.5.1.1 ;

through 6.5.1.5 within his functional area of responsibility as assigned in the GPU Nuclear, Inc. !

Review and Approval Matrix. Implementing approvals shall be performed at the cognizant manager level or above.

6-3 Amendment Nos. 41, 32, 5 5, "'7, 92,128,131,132,139,1-7h-20h212 Corrected by 1etter dated July 8, 1999

ML20209D665

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