ML19309B891

Tech Spec Change Request 61B to App a of License DPR-50 Re Mods to High Pressure Injection Sys to Ensure Min Acceptable Flow Through Each Leg Should One Pump Fail

ML19309B891
Person / Time
Site:	Three Mile Island
Issue date:	03/31/1980
From:	METROPOLITAN EDISON CO.
To:
Shared Package
ML19309B873	List: ML19309B872 ML19309B874 ML19309B891
References
NUDOCS 8004070306
Download: ML19309B891 (4)

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION-IN THE MATTER OF DOCKET No. 50-289 LICENSE NO. DPR-50.

METROPOLITAN EDISON COMPANY This is to certify that'a copy of Technical Specification Change Request No. 61B to Appendix A of the Operating License for Three Mile Island

, Nuclear Station Unit 1, has, on the date given below, been filed with the U. S. Nuclear Regulatory Commission and been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows: l Mr. Weldon B. Arehart Mr. Harry B. Reese, Jr.

Board of Supervisors of Board of County Commissioners ,

, Londonderry Township of Dauphin County l R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLITAN EDISON COMPANY j l

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B i Vice President Dated: March 31, 1980 i

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LThree, Mile :Islan'd Nuclear Station, Unit .I.'

. Operating License No. DPR-50 '

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, Docket'No. 50-289~

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Technical: Specification Change Request No. 61, Amendment' B

~ ; The [ licensee requests tliat -th'e -attachedichanged pages replace pages h-:

' ' hl, fhih2 of the- Technical Specifications Appendix; A.

' Reasons = for Change Request Amendment

The NRC, in their letter. dated July 1~, 1977, requested all nuclear stations

'which use HPI and/or LPI throttle valves to propose _ changes to the.

e7 technical,spe~cifications to-incorporate surveillance requirements on the

-throttle-valves. ~This amendment is requested because we'are modifying our HPI system to-include. cross connections and cavitating venturies to

-insure a minimum ~ acceptable flow will be injected through each leg should .

• Lone of the HPI pumps fail. .

. Safety Analysis Justifying Change

.This change request increases the surveillance requirements- for the HPI p  : and LPI systems to ~ provide: additional assurance that they will function

as, assumed.in the ECCS analyses. The surveillance assures proper flow and flow distribution to all necessary injection points by periodically checking

, those elements of the HPI nad LPI systems which could adversely affect j; minimum flow and/or correct flow distribution.

LAn exception has b'een taken to the NRC suggested surveillances in one j; instance. No verification of the position stcp is specified for the decay heat throttle valves in that.they are manually operated and do not have .

spositive stops. The intent of the suggested surveillance will' be fulfilled

r. .by verifying.that the valves are locked in the correct throttled position--

. by observatiori of the position indicators.

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Licensee Amendment Fee (10 CFR 170.22)

This-is an. amendment' to 'a change request submitted prior to . impl'ementation of ~

, #10'CFR.170.22.- Therefore, no fee is required.

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h.5 2 DG3GENCY CORE COOLING SYSTEM Applicability Applies to periodic testing requirement for emergency core cooling systems.

Objective To verify that the emergency core cooling systems are operable.

Speci fication h.5 2.1 High Pressure Injection

a. During each refueling interval and following maintenance or modification that affects system flow characteristics, system pumps and system high point vents shall be vented, and a system test shall be conducted to demonstrate that the system is operable.

After a satisfactory test of the emergency loading sequence (4.51),

the M. U. Pump and its required supporting auxiliaries will be started manually by the operator and a test signal vill be applied to the high pressure injection valves MU-V-16A, B, C, D to demonstrate actuation of the high pressure injection system for emergency core cooling operation.

b. The test will be considered satisfactory if the valves have completed their travel and the M. U. Pumps are running as evidenced by the control board component operating lights. Minimum

' acceptable injection flow must be greater than or equal to 500 gpm per HPI pump when RC pressure is equal to or less than 600 psig.

h.5.2.2 Low Pressure Injection

a. During each refueling period and following maintenance or modification

-that affects system flow characteristics, system pumps and high point vents shall be vented, and a system test shall be conducted to demonstrate that the system is operable. The auxiliaries required for low pressure injection are all included in the emergency loading sequence specified in L .5.1.

b. The test will be considered satisfactory if the decay heat pumps listed in h.5.1.lb have been successfully started and the decay heat injection valves and the decay heat supply valves have I

completed their travel as evidenced by the control board component operating lights. Minimum acceptable flow must be greater than or equal to 2700 gpm per injection leg /LPI pump.

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2e .'c.~~.Whenithe; Decay' Heat; System;is required to-be' operable,~ the cor, rect position'of DH-V-19A/B shall beLverified_by observation within four Jhours'of each valve' stroking operation.or valve maintenance, which

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h'.52.3)~Cor'eFlooding'

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< 1a. During _ each . refueling period, -a : system _ test shall be conducted to 1 demonstrate' proper operation of the system.'_During depressurization

offthe Reactor Coolant System,nverification shall be made'that the

check. and -isolation. valves- in- the core flooding tank discharge lines

' operate properly.

.b. The test will b'e considered, satisfactory if-control' board indication

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of core; flood tank level verified that all. valves have opened, k.5 2.h Component Tests'

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a. -At-intervals not to exceed 3 months, the components required for emergency core 1 cooling vill.be tested.

b. The test .will be considered satisfactory if the pumps and fans have been successfully.' started and the _ valves have completed their travel -

as evidenced by the control board ~ component operating lights, and either the station computer-or_ pressure / flow indication.

Bases' Thefemergency-core cooling systems are the principal reactor safety features in ethe . event of.a loss of coolant accident. The removal' of heat from the core pro-p .vided:by these systems _ is . designed'to limit core damage.

' Th'e' low -pressure injectiou pumps are tested singularly for operability by

-opening _the' borated water storage tank outlet-valves and the bypass valves in~

the borated water = storage tank fill line. This allows water to be pumped from the-borated water storage tank through each of the injection lines and back to the tank.

The' minimum acceptable 'HPI/LPI flow assures proper flow and flow split between injection legs.

' With .th'e reactor' shut,down, the valves' in each core flooding line are checked

'for operability by reducing the reactor coolant system pressure until-the

, indicate'd level:in the ' core flood- tanks . verify that the check _ and isolation valves have opened.

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