ML20199F211

Suppl to 1985 Annual Rept

ML20199F211
Person / Time
Site:	Haddam Neck, 05000000
Issue date:	12/31/1985
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20199F155	List: B11990, Forwards Suppls to Annual Rept Re Changes in Jumpers,Listed Leads & Bypasses Made to Operable Sys in 1985 ML20199F211 ML20199F224
References
NUDOCS 8606240224
Download: ML20199F211 (9)

Text

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r Attachment 1 Connecticut Yankee Atomic Power Company Haddam Neck Plant r

Supplement to Annual Report l

May,1986 8606240224 860529 PDR ADOCK 05000213 PDR R

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Index Jumper-Lifted Lead-Bypass (3-LL-B) Changes 1

! 3-LL-B Number 3-LL-B Title 85-5 NIS Channel 34 Load Runback j 85-8 NIS Channel 34 Load Runback l 85-11 NIS Channel 34 Load Runback i

j 85-12 NIS Channel 34 Load Runback 85-29 NIS Channel 34 Load Runback 85-32 NIS Channel 34 Load Runback 4

J 85-38 NIS Channel 34 Load Runback 85-40 NIS Channel 34 Load Runback 35-42 NIS Channel 33 Load Runback i

j 85-45 DH-TV-1842A Temporary Piping 85-49 Steam Generator Steam Sample Piping and Feed System Piping i

i 85-53 Installation of Temporary Power Supply to Trailer #14 85-54 Installation of Temporary Power Supply to Trailer #16A 85-55 Installation of Temporary Power Supply to Trailer #21 85-56 Installation of Temporary Power Supply to Trailer #22 i 85-57 Installation of Temporary Power Supply to Trailer #25 85-58 Installation of Temporary Power Supply to Trailer #26 85-59 Installation of Temporary Power Supply to Trailer #29

) 85-60 Installation of Temporary Power Supply to Trailer #30  ;

! 85-61 Installation of Temporary Power Supply to Trailer #34 85-62 Installation of Temporary Power Supply to Building #15 1

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3-LL-B Number 35-5 3-LL-B Number 85-5, entitled "NIS Channel 34 Load Runback", is complete.

Description of Change An electrical jumper was installed on Nuclear Instrumentation System (NIS)

Channel 34 load runback circuit. The jumper has been removed.

Reason for Change The bypass was necessary because the circuit was producing spurious signals which could have resulted in an undesirable inadvertent turbine load runback.

Safety Evaluation The only safety analysis which credits the operation of the circuit being bypassed is the dropped rod. The latest rod drop analysis is documented in the Cycle 5 modification of control rod bank B. This analysis was performed to determine the effect of reducing the size of control rod bank B. The analysis took credit for the turbine load cutback and rod withdrawal block features, however those features were assumed to be actuated by the rod bottom bistables. Therefore this bypass did not affect the assumptions made in the safety analysis.

This bypass did not disable any channels which provide protection for high nuclear flux. It only prevented one of the four NIS channels from initiating a turbine runback and blocking automatic rod withdrawal. It cannot, of itself, cause a transient. The only event that this bypass could affect is a rod drop which does not actuate any rod bottom bistable and is not sensed by any of the other three operable nuclear channels. Because of the temporary nature of this change, this event is considered to be highly unlikely.

Although credited in the dropped rod safety analysis, the dropped rod protective circuits are not part of any Technical Specifications (T.S.). However, the T.S.

permit one excore detector to be taken out of service. Since taking one excore detector out of service would have the same effect as this bypass on the dropped rod protection, no degradation in dropped rod protection exists beyond that allowed by T.S. Since the plant administratively controls removing an excore detector from service that would take more than one dropped rod channel out of service, three of the dropped rod channels remain in service. Because of the above assessments, this temporary bypass does not create the possibility of an accident or malfunction of a dif ferent type than any evaluated previously.

The bypass does riot constitute an unreviewed safety question as defined in 10CFR$0.59(a)(2). ,

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3-LL-B Numbers 85-8,85-11,85-12,85-29,85-32,'85-38, and 85-40 The above 3-LL-B changes, each entitled "NIS Channel 34 Load Runback", are complete.

See 3-LL-B Number 85-5. ,

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3-LL-B Number 85-42 3-LL-B Number 85-42, entitled "NIS Channel 33 Load Runback", is complete.

Description of Change An electrical jumper was installed on NIS Channel 33 load runback circuit. The jumper has been removed.

Reason for Change The bypass was necessary to replace a failed light source on NIS Channel 33.

Safety Evaluation See 3-LL-B Number 85-5.

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3-LL-B Number 85-45 3-LL-B Number 85-45, entitled "DH-TV-1842A Temporary Piping", is complete.

Description of Change Temporary piping was installed from valve DH-V-316B to valve DH-V-316C. The piping has been removed.

Reason for Change The temporary piping was installed to allow for testing of valve DH-TV-1842A without causing the valve stem leakoff header relief valve to lif t.

Safety Evaluation 3-LL-B Number 85-45 addressed running one-half inch tubing from DH-V-316B to DH-V-316C. This enabled an operational test of DH-TV-1842A. Connecticut Yankee Technical Specifications (T.S.) state that when one or more isolation valve listed in Table 3.11-1 is inoperable, maintain at least one isolation valve operable in each affected penetration that is open. Valve DH-V-1842B was the isolation valve considered operable as required in T.S.

The tubing used was 316 stainless steel, .065 inch wall thickness and pressure rated at 2500 lb. The pressure rating of the line in which DH-TV-1842A is located is 150 lb. Therefore, the pressure issue was adequately addressed. An operator was stationed at DH-V-316B to isolate the jumper in case a problem developed. Adequate protection of the piping system was ensured by relief valve DH-RV-1841.

This jumper does not constitute an unreviewed safety question per the criteria contained in 10CFR50.59(a)(2).

3-LL-B Number 85-49 J-LL-B Number 85-49, entitled " Steam Generator Steam Sample Piping and Feed System Piping", is complete.

Description of Change Temporary tubing was installed on each steam header and a feed line, as well as temporary coolers which used service water for cooling the samples. The temporary tubing and coolers have been removed.

Reason for Change This change was necessary to determine the total amount of moisture carry over present in the steam exiting the steam generators.

Safety Evaluation This temporary modification involved installing tubing necessary to sample steam from each steam header simultaneously instead of sequentially as allowed by plant configuration. It also allowed for sampling feedwater through a much shorter length of pipe than currently available. These samples were cooled through temporary sample coolers using service water. The operability of plant systems or equipment is not affected by this temporary modification and does not constitute an unreviewed safety question per the criteria contained in 10CFR50.59(a)(2).

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3-LL-B Number 85-53 3-LL-B Number 85-53, entitled " Installation of Temporary Power Supply to Trailer #14", is complete.

Description of Change A jumper was installed on BUS 6 position 10C. This jumper has been removed.

Reason for Change i This jumper allowed temporary power to be installed to 9 trailers and a j temporary fabrication shop located in south trailer city.

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Safety Evaluation i

The new 480 volt loads to be added to BUS 6, position 10C are the fabrication i shop (Building #15) and the following 9 trailers:

1. 21 - Nuclear Support Services

1. 22 - Coast to Coast j # 29 - Flagg

1. 30 - Flagg a

1. 25 - Cummings i

1. 26 - Flagg

1. 16A - Myrock i # 14 - Flagg i #34 - Mark Controls i

I The installation of temporary power for trailers will exert a load on BUS 6 that is within the existing designed protection scheme for the breaker at position 10C. BUS 6, position 10C serves as separation and isolation between class and non-class equipment.

l The installation of temporary power has no effect on plant safety-related j equipment. The use of jumpers evaluated above does not constitute an unreviewed safety question per the criteria contained in 10CFR50.59(a)(2).

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1 i 3-LL-B Numbers 85-54, 8 5-55, 85-56, 85-57, 85-58, 85-59, 35-60, 85-61, and 85-p2_

The above 3-LL-B changes, each identified in the index, are complete.

, Description of Changes All of these temporary power supplies were associated with BUS 6 position 10C,

, and they have been removed.

Reason for Changes l

1 See 3-LL-B Number 85-53.

Safety Evaluation i See 3-LL-B Number 85-53.

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