ML19350A162

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Submits Proposed Changes Resulting from Investigation to Determine If Failure of Noncategory I (Seismic) Equipment Could Result in Flooding or Release of Chemicals That Could Jeopardize Safe Shutdown,In Response to
ML19350A162
Person / Time
Site: Yankee Rowe
Issue date: 01/20/1975
From: Vandenburgh D
YANKEE ATOMIC ELECTRIC CO.
To:
Office of Nuclear Reactor Regulation
References
WYR-75-9, NUDOCS 8102120153
Download: ML19350A162 (8)
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Text

{{#Wiki_filter:5 s. Reguiairsy Dd.et file. 7.r.,som. ei7 3es.,oi, m 7to-3 9 0-073 9 YANKEi ATOMIC ELECTRIC COMPANY WrR,5-9 ~, 20 Turnpoke Road Westborough, Massachusetts 01581 ,bgL. ANKEE ~ . _N January 20, 1975 / / \\j '~ United States Atomic Energy Commission 5, Washington, D. C. 20545 Attention-Directorate of Licensing Y

Reference:

(a) License No. DPR-3 (Docket No. 50-29) (b) USAEC letter to YAEC dated 12/17/74 (c) USAEC letter to YAEC dated 8/8/72 4 x (3\\ (d) YAEC letter to USAEC dated 9/8/72 L,Cf. n

Enclosures:

(1) Figure 1 lite Building Arrangement (2) Figure 2 - Primary Auxiliary Building ar { d h Diesel Generator Building g y (@ A

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(3) Figure 3 - Ground Floor Turbine Room (4) Figure 4 - Turbine Room Elevations M

Dear Sir:

m In response to Reference (b), we conducted an investigation at the Yankee Rowe plant to determine whether the failure of any non-Category I (seismic) equipment could result in flooding or release of chemicals that could jeopardize safe shutdown of the facility. This investigation was carried out ;n accordance with the AEC criteria entitled, " Guidelines for Review of Non-C3tegory I Systems Whose Failure Could Cause Flooding of Safety Related Equ!ptent". This report discusses the results of the investigation, the temporary protective measures which were determined necessary; a time sch=Aule for completion of the permanent modifications and an inspection prograa which has been instituted and will remain in force until the permanent modifi-cations have been completed. GENERAL INFORMATION The Yankee Nuclear Power Station was not designed to the seismic criteria now in effect; consequently, the piping systems are classified as safety Related or non-safety related rather than by a seismic category. All of the applicable non-safety related systems in Reference (b) were included in our investigation, specifically: 802 f/oRic2o(53

United States Atomic Energy Commission January 20, 1975 Attn: Directorate of Licensing Page Two Service Water Demineralized water Condensate Drains Feedwater Heating Boiler Condensate Reactor Building Cooling Water Make-up Circulating Water Potable Water Fire Protection PLANT SHL"rDCWN The Turbine Building and Primary Auxiliary Building contain safety related equipment required for safe shutdown of the plant. Heat removal can be provided by the equipment located in either building. These buildings are separated as shown in Figure 1; therefore, simultaneous flooding of both buildings from a single pipe rupture is not possible. The Control Room and Switchgear Room are located in the Turbine . Building and the emergency diesel generator and safety injection pumps ' are located in the Diesel Generator Building with interconnecting cables between the two buildings. TURBINE BUILDING The Switchgea'. Room and Control Room, shown on Figure 4, are located in_thel Turbine Building at El. 1037'-8", and 1052'-8", respectively. The floor of the Turbine Building is at ground level, El.1022'-8". Flooding of.the Switchgear Room cannot occur, unless the entire Turbine Building were flo'ded to a depth greater than 15 feet. This is considered a highly o unlikely event because of the many doors and openings to the outside. In addition, submergence of non-safety related equipment in the Tu1bine Building - would result in equipment trips and thereby alert the operator to the mal-funttion. PRIMARY AUXILIARY BUILDING Service. water, component cooling water, demineralized water, and heating system condensate is~ routed through a room in the lower level of the Primary - Auxiliary Building. This room is shown on Figure 2. A rupture of any of - these systems, which results'in a water depth in excess of one foot could flood'out Motor Control Center 4 add prevent operation of the charging . pumps,-which are needed for_ heat removal,~and the purification pumps, which are needed for post-IOCA, long term recirculation. While the heat removal function of the charging pumps could be provided by equipment in the Turbine-Building,_longLterm recirculation could not. Therefore, the purification pumps must remain functional. DIESEL GENERA'IOR BUILDING LThe Diesel Generator Building contains the three diesel generators _ and Emergency. Buses l1, 2 and 3, which are required in the event of a loss - of offsite power, and the safety injection system which is required for both shutdown and the design basis accident-(LOCA). -No non-category I p w e s

/ b United States Atomic Energy Cocrdssion January 20, 1975 Attn: Directorate of Licensing Page Three piping of any size passes through this building and flooding is not considered-a possibility. The connecting door between Primary Auxiliary Building and the Diesel Generator Building is maintained in a closed position since it is equipped with an automatic door closer. DESCRIPTICU CF-REQUIRED CHA!GES Flooding of vital areas will be prevented by the following modi- -fications: 1. Sufficihnt openings will be provided in the Primary Auxiliary Building to prevent the flooding of Motor Control Center 4. 2. Redundant alarms will be installed in the floor su=p to alert the Centrol Room operators of increasing water level in the ' Primary Auxiliary Building. Means will be provided to guarantee that leakage under the

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connecting door between the Primary Auxiliary Building and the Diesel Generator Building cannot impair the operability of the 480V switchgear comprising-Emergency Buses 1, 2 and 3. At present,:several alternatives _are being considered which include door seals, drainage paths, berms, etc. The details of this modification will be suteitted as soon as the design is finalized. It is anticipated that this information will be available.within the 30 day period allotted. SCHEDUI.E OF CHANGES - The schedule for cocpletion of-Items'1 thru 3 is expected to be: Item 1 April 30,'1975 Item 2- . April 30, 1975 =Itc : 3' March.1, 1975 Until the above modifications are completed, YAEC intends to: 1. ' Provide an audible addition to the, existing high' sump level alarm which is located in'the Primary Auxiliary Building.. I 2. Initiate an hourly inspection by plant personnel... This . inspect _on is to include verification of the closed position ~ of the southwest. inter-connecting door. ' 3.. Instruct Control Room operators that-changes in the service water flow may be the result-of a rupture. CHEMICALST All chemicals used-in the: plant are stored either'in the: Water ' Treatment Room or in a warehouse; these are shown on" Figure 1...Thus,- w

( l January 20, 1975 United States Atomic Energy Commission i Attn: Directorate of Licensing Page Four a pipe rupture in a non-safety related system could not cause the release of chemicals which would prevent safe shutdown of the plant. We trust the above information is responsive to your letter and, of course, we are prepared to discuss this matter at your convenience. Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY k D. E. Vandenburgh Vice President TWG/kg-Enclosures 4 9 h -a--- -,o* n ..+-,. w sry.g _

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