ML20203B051

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

ML20203B051
Person / Time
Site:	Three Mile Island
Issue date:	02/02/1999
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20203B048	List: ML20203B042 ML20203B051
References
NUDOCS 9902100198
Download: ML20203B051 (6)

Text

,. _. . . _ . . _ . . . . , . _ . _ _ . _.-. _...._ _. _ _.. _ _ _ _. _ _ _ _ _ ~ _ _ _ _ _ _ . _ .

4

• l ll 4 9

1 i

1 i

1 i

'l J

I Proposed Technical Specification Revised Pages  ;

1 1

.i l

l 1

i a

1 4

KO 9 P.

j I

,l 1

l l

O TABLE OF CONTENTS Section Eggg 3.16 ' SHOCK SUPPRESSORS (SNUBBER _S) 3-63 3.17 - REACTOR BUILDING AIRTEMPERATURE 3-80 3.18 FIRE PROTECTION (DELETED) . 3-86 3.19 . CONTAINMENT SYSTEMS 3-95 3.20 - SPECIAL TEST EXCEPTIONS (DELETED) 3-95a 3.21 RADIOACTIVE EFFLUENT lhSTRUMENTATION (DELETED) 3-%

3.21.1 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION (DELETED) 3-%

3.21.2 - RADIOACTIVE GASEOUS PROCESS AND EFFLUENT 3-%

MONITORING INSTRUMENTATION (DELETED) 3.22 RADIOACTIVE EFFLUENTS (DELETED) 3-%

3.22.1 LIQUID EFFLUENTS (DELETED) 3-%

3.22.2 GASEOUS EFFLUENTS (DELETED)' 3-%

3.22.3 SOLID RADIOACTIVEWASTE(DELETED) 3-%

3.22.4- TOTAL DOSE (DELETED) 3-96 3.23 RADIOLOGICAL ENVIRONMENTAL MONITORING (DELETED) 3-%

3.23.1 MONITORING PROGRAM (DELETED) 3-%

3.23.2 LAND USE CENSUS (DELETED) 3-%

3.23.3 INTERLABORATORY COMPARISON PROGRAM (DELETED) 3-%

3.24 REACTOR VESSELWATER LEVEL 3-128 4 SURVEILLANCE STANDARD _S 4-1

-4.1' OPERATIONAL SAFETY REVIEW 4-1

'4.2 REACTOR COOLANT SYSTEM INSERVICE INSPECTION 4-11 4.3 TESTING FOLLOWING OPENING OF SYSTEM (DELETED) 4-13 4.4 REACTOR BUILDING 4-29 4.4.1 CONTAINMENT LEAKAGETESTS 4-29 4.4.2 ' STRUCTURALINTEGRITY 4-35 4.4.3 DELETED 4-37 4.4.4 LYDROGEN RECOMBINER SYSTEM 4-38 4.5 EMERGENCY LOADING SEOUENCE AND POWER TRANSFER. 4-39

- EMERGENCY CORE COOLING SYSTEM AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING 4.5.1 ErdERGENCY LOADING SEQUENCE 4-39 4.5.2 - EMERGENCY CORE COOLING SYSTEM 4-41 4.5.3 REACTOR BUILDING COOLING AND ISOLATION SYSTEM 4-43 4.5.4 ENGINEERED SAFEGUARDS FEATURE (ESF)

SYSTEMS LEAKAGE 4-45 4.6 EMERGENCY POWER SYSTEM PERIODIC TESTS 4-46 4.7- REACTOR CONTROL ROD SYSTEM TESTS 4-48 4.7.1 CONTROL ROD DRIVE SYSTEM FUNCTIONAL TESTS 4-48 4.7.2 CONTROL ROD PROGRAM VERIFICATION 4-50

-iii-Amendment 72, S!, !a",129,137, ! ",147, !"*,191,197,195, L

- _. - - . - .~ .- - - - . - - - _ _- -..

Basej The Auxiliary and Fuel Handling Building Air Treatment System (part of the Auxiliary and Fuel Handling Building Ventilation System - References I and 2), consists of four banks of exhaust  !

filters (AH-F2A, B, C, and D) and two sets of fans (AH-E-14A and C, and AH-E14B and D) which l take the exhaust air from both the Auxiliary Building and the Fuel Handling Building and discharge I it to the Auxiliary and Fuel Handling Building exhaust stack. The air normally passes through all four filter banks when either set of fans is in operation. l This system is not nuclear safety related. When available, it can he used to reduce the off-site dose releases; however, no credit was taken for this system in the analyses of the Waste Gas Tank Rupture (WGTR) Accident (Reference 4) or Maximum Hypothetical Accident

' (Reference 3), or for any other events releasing radioactivity through the Auxiliary Building.

The dose consequences resulting from any of these events will be less than the 10 CFR 100 limits with or without system operation.

The in-place testing criteria for the HEPA and carbon adsorber banks, and the laboratory testing for the carbon adsorbers shall be performed in accoaxlance with the test methods of l

l ANSI /ASME N510-1980.

l Note: The Fuel Handling Building ESF Air Treatment system controls the release resulting from a postulated speat fuel accident in the Fuel Handling Building per Technical l Specification 3.15.4.

l References - j l

(1) UFSAR Section 9.8.2 " Fuel Handling Building Ventilation. System" (2) UFSAR Section 9.8.3 " Auxiliary Building Ventilation System" (3) UFSAR Section 14.2.2.5 " Maximum Hypothetical Accident" l

l (4) UFSAR Section 14.2.2.6 " Waste Gas Tank Rupture" i

i 3-62d i

Amendment No. 55,122,157, 3

~

t

~

4.5.4 ENGINEERED SAFEGUARDS FEATURE (ESF) SYSTEMS LEAKAGE Applicability Applies to those portions of the Decay Heat, Building Spray, and Make-Up Systems, which are required to contain post accident sump recirculation fluid, when these systems are required to be operable in accordance with Technical Specification 3.3.

4 Obiective

)

To maintain a low leakage rate from the ESF systems in order to prevent significant off-site exposures and  ;

dose consequences. '

Specification

~

4.5.4.1 He total maximum allowable leakage into the Auxiliary Building from the applicable portions of the Decay Heat, Building Spray and Make-Up System components as measured during refueling interval tests in Specification 4.5.4.2 shall not exceed 15 gr.Ilons per hour.

4.5.4.2 Once each refueling interval the following tests of the applicable portions of the Decay Heat Removal, Building Spray and Make-Up Systems shall be conducted to determine I leakage:

a. The applicable portion of the Decay Heat Removal System that is outside containment shall be leak tested with the Decay Heat pump operating, except as specified in "b".

b. Piping from the Reactor Building Sump to the Building Spray pump and Decay Heat Removal System pump suction isolation valves shall be pressure tested at no less than 55 psig.

c. The applicable portion of the Building Spray system that is outside containment shall be leak tested with the Building Spray pumps operating and BS-V-1 A/B closed, except as specified in "b" above.

d. The applicable portion of the Make-Up system on the suction side of the Make-Up pumps shall be leak tested with a Decay Heat pump operating and DH-V-7A/B open.

e. The applicable portion of the Make-Up system from the Make-Up pumps to the containment boundary valves (MU-V-16A/D,18, and 20) shall be leak tested with a Make-Up pump operating.

f. Visual inspection shall be made for leakage frem components of these systems.

Leakage shall be measured by collection and weighing or by another equivalent method.

Bases The leakage rate limit of 15 gph (measured in standard room temperature gallons) for the accident recirculation portions of the Decay Heat Removal (DHR), Building Spray (BS), and Make-Up (MU) systems is based on ensuring that potential leakage after a loss-of-coolant accident will not result in off-site dose consequences in excess of those calculated to comply with the 10 CFR 100 limits (Reference I and 2). The test methods prescribed in 4.5.4.2 above for the applicable portions of the DH, BS and MU systems ensure that the testing results account for the highest pressure within that system during the sump recirculation phase of a design basis accident.

References (1) UFSAR, Section 6.4.4 " Design Basis Leakage;" and, Table 6.4-3 " Leakage Quantities to the Auxiliary Building" (2) UFSAR, Section 14.2.2.5(d) " Effects of Engineered Safeguards Leakage During Maximum Hypothetical Accident" 4-45 Amendment No. M7

l ,

1 i

I i

l I

i l

1 l

t l

! l l

ENCLOSURE 2 Certificate of Service for TMI-l TSCR No. 274 )

l l

f I

i r

7

? 4 UNITED STATES OF AMERICA NUCLEARREGULATORY COMMISSION

. i i

IN THE MATTER OF DOCKET NO. 50-289 GPUNUCLEARINC. LICENSE NO. DPR-50  ;

4 CERTIFICATE OF SERVICE This is to certify that a copy ofTechnical Specification Change Request No. 274 Appendix A of the l

Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been '

filed with executives of Londondeny Township, Daiphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department ofI!nvironmental Resources, Bureau of Radiation

{

Protection, by deposit in the United States mail, addressed as follows: I Mr. Danyl LeHew, Chairman Ms. Sally S. Klein, Chairman Board ofSupervisors of Board ofCounty Commissioners Londonderry Township Dauphin County Courthouse R. D. #1, Geyers Church Road Front and Second Streets Middletown,PA 17057 Harrisburg,PA 17101  ;

Director, Bureau of Radiation Protection PA Dept. ofEnvironmental Resources Rachael Carson State Office Building i P.O. Box 8469 j Harrisburg, PA 17105-8469  ;

ATT: Mr. Stan Maingi GPU NUCLEARINC.

V" President and Dirgr, TMI DATE: b/

i