ML19260A052

Tech Specs Change Request 38 to Amend DPR-50,App a Re Addl Safeguards Against Damage to Stored Spent Fuel or Sys & safety-related Equipment in Event of Spent Fuel Cask Drop Accident

ML19260A052
Person / Time
Site:	Three Mile Island
Issue date:	09/21/1976
From:	Arnold R METROPOLITAN EDISON CO.
To:
Shared Package
ML19260A045	List: ML19260A044 ML19260A052
References
NUDOCS 7910290681
Download: ML19260A052 (8)

Text

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METROPOLITA'I EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technien1 Srecification Chansre Recuest No. 38 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.

ME'"ROPOLITAN EDISON COMPANY 9 fg By i Vice President-Generation Sworn and subscribed to me this day of @ ,

1976. /

Notaff Public

12 .-N,~,,, ~3 i NP?' 514" Espres fe^s, !$, IE/3

.7910290.h/

Fbtropolitan Edison Company (Met-Ed)

Three N11e Island Nuclear Station Unit 1 (Met-Ed)

Operating License No. DPR-50 Docket No. 50-289 i Technical Specification Change Recuest Replace page 3-55 and 3-56 with the attached replacement pages 3-55, 3-56 and 3-56a, and add figures 3.11-1, 3.11-2 and 3 11-3.

Reasons for Proposed Change

. To provide additional safeguards against the possibility of damage to stored spent fuel or syste=s and equip = rat important to safety in the event of a spent fuel cask drop accident.

Our letter GQL 0215 of February 14, 1976 forwarded a detailed evaluation of a postulated spent fuel cask drop accident. Tbis change request addresses those corrective actions outlined in that letter.

Safety Analysis Justifyice Proposed Change This change request imposes more restrictive limits on spent fuel cask covement. Therefore, no unreviewed safety question is involved.

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i 1479 064 J

0 0 3.11 HANDLING OF IRRADIATED FUEL Aonlicability Applies to the operation of the fuel handling building crane when within the confines of Unit 1 and there is any spent fuel in storage in the Unit 1 fuel handling building.

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, Objective i

To define the lift conditions and allowable areas of travel when loads to be lifted and transported with the fuel handling building crane are

in excess of 15 tons or between 5 to 15 tons or consist of irradiated fuel elements.

Suecification 3.11.1 Spent fuel elements having less than 120 days for decay l of their irradiated fuel shall not be loaded into a spent fuel transfer cask in the shipping cask area.

3.11.2 The key operated travel interlock system for automatically

! limiting the travel area of the fuel handling building crane shall be imposed whenever loads in excess of 15 tons are to be lifted and transported with the exception of fuel handling I

bridge maintenance.

1 3.11 3 a. The lower surface of all loads in excess of 15 tons shall be administratively limited to an elevation six inches or

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less above the concrete surface at the nominal 3h8 ft-0 in. elevation in the fuel handling building.

b. During movement of the cask between the carrier and the

, top of the "B" spent fuel pool, the cask vill be restricted l to the transfer path shown in Figures 3 11-1. Administrative l procedures and visual aids will be used to control the cask to the prescribed path. During this transfer the cask lifting yoke shall be oriented in the North-South direction.

c. During transfer of the cask to and from the cask loading pit, the cask vill be restricted to the transfer path l shown in Figure 3.11-2. Administrative procedures will i be used to ensure that all lateral movements of the cask l are performed at slow bridge and trolley speeds. During l this transfer the cask lifting yoke shall be oriented in j the East-West direction.

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' d. The Cask decontamination vill be restricted to the shaded areas designated in Figure 3.11-3.

1479 065 3-55

GD GD 3.11.4 Loads in excess of hook capacity shall not be lifted, except for load testing.

3.11 5 Fol]oving =odifications or repairs to any of the load bearing members, i

the crane shall be subjected to a test lift (f 125 perceat of its

! rated load.

l, Bases This specification vill limit activity releases to unrestricted areas resulting

- from damage to spent fuel stor-d in the spent fuel storage pools in the postulated I event of the dropping of a hewry load from the fuel handling building crane.

When a loaded spent fuel transfer cask is moved out of the decontamination pit

area and along-the centerline of the spent fuel pool's vest vall to the receiving /

, shipping area (Figure 9-18, Section 9), it has a potential drop of 43 feet which is 13 feet greater than its design basis drop. An analysis (1) was performed assuming that the cask and its entire contents of the fuel assemblies are sufficiently damaged as a result of dropping the cask, to allow the escape of all noble gases and iodine in the gap. This release was assumed to be directly to the atmosphere and to occur instantaneously. The site boundary doses resulting from this accident are 5.25 R. whole body and 1.02 R to thyroid, and are within the limits specified in 10 CFR 100.

Specification 3.11.1 required that spent fuel, having less than 120 days decay post-irradiation, not be leaded in a spent fuel transfer cask in order to ensure that the doses resulting from a highly improbable spent fuel transfer l cask drop would be within those calculated above, i

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! Specification 3.11.2 requires the key operated interlock system, which auto-l matically limits the travel area of the fuel handling crane while it is lifting l and transporting the spent fuel shipping cask, to be imposed whenever loads in excess of 15 tons are to be lifted and transported while there is any spent fuel in storage in the spent fuel storage pools in Unit 1. This automatically l

l ensures that these heavy loads travel in areas where, in the unlikely event of a load drop accident, there vould be less possibility of this event resulting l in any damage to the spent fuel stored in the pools or doing any unacceptable structural damage to the spent fuel pool structure. As described in FSAR Section 9 71.1, the shipping cask area is designed to withstand the drop of t the spent fuel shipping cask from an elevation of 3k9 ft. without unacceptable damage to the spent fuel pool structure.

Specification 3.11.3.a ensures that the lover surface of any heavy load never

. gets higher than six inches above the concrete surface of the 3h8 ft-0 in.

E elevation in the fuel handling building (nominal elevation 3h9 ft-0 in. )

l thereby keeping any i= pact force from an unlikely load drop accident within acceptable limits.

Specification 3.11.3.b and 311.13d restricts the cask transfer path such that a single cask drop accident would not result in unacceptable damage to engineered safeguard circuits located below the cask transfer pr.th.

L l Specification 3.11.3.c restricts the cash transfer path to and from the cask

! loading pit so that the cask vill be tipped in a direction away from the "B" spent fuel pool in the event of a cask drop on the edge of the pool vall.

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j (1) FSAR, Supplement 2, Part VII 9 066 l, 3-So i

t Specification 3.11.4 ensures that the prope-c capacity crane hook is used for lifting and transportin6 loads thus reducing . le probability of a load drop accident.

Following modification or repai-s, specification 3.11.5 confirms the load rating of the crane.

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