ML20077S469

License Change Request 94-08 to Licenses DPR-44 & DPR-56, Revising TS Tables 3.7.1 & 3.7.4 to Reflect Reduction in Number of Primary Containment Power Operated Outboard Valves for TIP Probes,Per PBAPS Mod P00068

ML20077S469
Person / Time
Site:	Peach Bottom
Issue date:	01/13/1995
From:	Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20077S472	List: ML20077S469 ML20077S487
References
NUDOCS 9501240106
Download: ML20077S469 (8)

Text

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Etttlen Support Drcrtment

.. . 10 CFR 50.90 PECO ENERGY = fry;T;"Le,,

965 Chesterbroor Boulevard Wayne. PA 19087-5t/41 January 13,1995  ;

1 Docket Nos. 50-277 l 50-278 Ucense Nos. DPR-44 DPR-56 U. S. Nuclear Regulatory Commission t ATTN: Document Control Desk Washington, D.C. 20555

SUBJECT:

Peach Bottom Atomic Power Station, Units 2 and 3 Facility Operating Ucense Change Request 94-08

Dear Sir:

PECO Energy Company hereby submits Ucense Change Request (LCR) 94-08, ,

in accordance with 10 CFR 50.90, requesting changes to Appendix A of the Peach Bottom Atomic Power Station (PBAPS) Facility Operating Ucenses.

The proposed changes are necessary to support PBAPS Modification P00068, which will upgrade .the major components of the Traversing in-core Probe (TIP) .

System. Attachment 1 to this letter describes the proposed changes and Attachment 2 contains the revised Technical Specifications pages.

J if you have any questions concerning this submittal, please contact us.  ;

Sincerely, 0- .

G. A. Hunger, Jr.fe Director - Ucensing i

Enclosures:

Affidavit, Attachments  !

I cc: T. T. Martin, Administrator, Region I, USNRC W. L Schmidt, Senior Resident inspector, PBAPS, USNRC R. R. Janati, Commonwealth of Pennsylvania 0

90 C 6 rl: o 40gi l 95o124olo6 95o113 L l PDR ADOCK o5ooo277 \

P PDR -

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COMMONWEALTH OF PENNSYLVANIA  :

SS.

COUNTY OF CHESTER  :

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W. H. Smith, Ill, being first duly sworn, deposes and says:

That he is Vice President of PECO Energy Company; the applicant herein; that he has read the attached License Change Request (LCR 94-08) for changes to the r

Peach Bottom Facility Operating Licenses DPR-44 and DPR-56, and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.

L /

Vice PresidgHt 4

Subscribed and sworn to before me this /3'40 day of ww 1995.

, J({EIMu N6ta Public FM.ns Seal T +c J+

My Cmyrassa Ext.mJJy 10 995

i ATTACHMENT 1 9

PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 4

Docket Nos. 50-277 50-278 License Nos. DPR-44 DPR-56 Facility Operating License Change Request 94-08

" Traversing in-core Probe System Upgrade" Supporting information for Changes

c, .

.PECO Energy Company (PECO Energy), Ucensee under Facility Operating Ucenses ,

DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and i 3 respectively, requests that the Technical Specifications (TS) contained in Appendix A -!

to the Operating Ucenses be amended. Handwritten proposed changes to pages 181 i and 186 are contained in Attachment 2.

The proposed changes revise Tables 3.7.1 and 3.7.4 to reflect a reduction in the~-

number of primary containment power operated outboard valves for the Traversing in- i core Probe (TIP) probes, and a redesignation of the containment penetration numbers j

. for the TIP ball, shear, and check valves. The proposed changes are a result of  !

PBAPS Modification P00068.

4 Ucensee proposes that the changes be approved as soon as possible, with f implementation to occur upon completion of Modification P00068.

Description of Chanaes >

Ucensee proposes the following changes:

1) Table 3.7.1, " Primary Containment isolation Valves," TS page 181. (Units 2 and 3)  :

1 Revise the number of power operated outboard valves for the Traveling In-core .

Probe from 5 to 3. j

2) Table 3.7.4, " Primary Containment Testable Isolation Valves," TS page 186.

(Unit 2 only) .

i a) Revise the Penetration Numbers of the TIP Ball and Shear Valves from  !

35A to E, to 35E to G. i b) Revise the Penetration Number of the SV-109; Check Valve from 35F to i 35D.

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3) Table 3.7.4, " Primary Containment Testable Isolation Valves," TS page 186. i (Unit 3 only) a) Revise the Penetration Numbers of the TIP Ball and Shear Valves from  !

35A to E, to 35E to G.

'l b) Revise the Penetration Number of the SV-109; Check Valve from 35F to l 35C.  ;

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Discussion of Chances Proposed Change 1) The proposed change from five isolation valves to three is a result of the design of the new system. Because the new system only requires three-drive units and isolation valves instead of five, the remaining two isolation valves will no longer be used. '

Proposed Changes 2 and 3) These proposed changes are needed to accurately describe the containment penetrations that will be used by the new drive units and  ;

their associated valves.

Modification P00068 will replace the major components of the TIP System including the drive control units, the indexers, and the drive mechanisms. The existing five TIP systems will be replaced with a new state-of-art system consisting of three drive units, six Indexers, [(three 6-path and three 15-path), (one 6-path and one 15-path for each drive unit)], and a flux mapping and control console. The upgraded TIP system will add a second indexing mechanism per drive unit. The second indexing mechanism will permit configuration of the system to adapt for detector or drive mechanism failure thereby adding system redundancy. The existing gamma TIP detectors will be reused in the new drives. The two unused TIP tubing containment penetrations will be capped.

The new system is located inside and outside of containment. Outside containment are all the drive units, 6-path transfer indexers, isolation valves, and electronics that are required to obtain a flux map and calculate the different functions required by the system software. The heart of the TIP system console is the host computer system.

The host computer contains all the electronics, software, and interfaces to

, communicate with the Man-Machine Interface (MMI) console, drive units, and plant computer. The in-containment components consist of the 15-path indexer (see Figure 1).

The new system is equipped with a manual control panel which can be used to ,

withdraw the TIP detectors in the event of a controller failure. It also contains self test l features which monitor internal cabinet temperature, power supply voltages, and software timing to minimize the effect of any malfunction. The new equipment has the same failure modes as the existing system. It has been tested and qualified to applicable industrial and militery standards for electromagnetic interference and radio- )

frequency interference.

The new system will provide improved reliability and added redundancy by allowing a complete flux mapping if a detector or drive failure were to occur. The new system has a response time equal to the old one, an improved MMI, and improved reliability.

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No Significant Hazards Consideration Licensee proposes that this application does not involve significant hazards consideration for the folichig reasons:

i) . The oronosed chanos does not involve a sionEcant incrosse in the orobability or conaam- of an amir4 ant oreviousiv evaluatad.

I The TIP system does not serve as an initiator or coimibutor to any accidents  ;

previously evaluated. The system provides a means of calibrating the Local Power Range Monitors and supports thermal limit calculations. The new l system performs the same function as the old one. It will provide improved ,

reliability and added redundancy by allowing a complete flux mapping if a .

detector or drive failure were to occur.

installation of Modification P00068 and its operation will not degrade any active  !

or passive equipment that responds to an accident. These changes do not j

decrease the effectiveness of equipment relied upon to mitigate the previously i evaluated accidents. j Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

ii) The prooosed chanoes do not create the oossibility of a new or d4ferent kind of j accident from any oreviousiv evaluated.

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This modification is considered an enhancement to the TIP system and does not serve as an initiator or contributor to any of the accidents previously  ;

evaluated. The proposed changes do not introduce a new mode of plant  !

operation. The new system, like the old one, is designed to keep the ball i valves closed upon reset of the Primary Containrntnt isolation System (PCIS) logic. The new TIP control console will respond to a PCIS isolation signal in the  !

same manner as the old system.

l Implementation of the proposed changes will not affect the design function or configuration of any component or introduce any new operating scenarios or failure modes or accident initiation.

Modification P00068 will'not impair or prevent safety systems from performing their safety function. It will not make any changes to the design function of the i TIP system. The classification of the TIP ball and shear valves and their control circuitry will not change as a result of this modification. ,

Therefore, the proposed changes do not create the possibility of a new or i different kind of accident from any previously evaluated. j l

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,. l lii) The orooosed chances do not involve a sionificant reduction in a maroin of-safety, The TIP system does not serve as an initiator or contributor to any accidents .

evaluated in the SAR. Modification P00068 is considered an enhancement to the existing TIP syn, tem and does not change its design function. The reduction '

in the number of cont @ ment penetrations from five to three does not represent a reduction in a margin of safety because of additional indexers in the new system.- The proposed changes do not adversely affect the assumptions or -

sequence of events used in any accident analysis.

Therefore, the proposed changes do not involve a significant reduction in a margin of safety. .

EnvironmentalImpact Assessment An environmental impact assessment is not required for the changes proposed by this  :

application because the changes conform to the criteria for " actions eligible for categorical exclusion" as specified in 10 CFR 50.22(c)(9).

The proposed change supports Modification P00068 which upgrades the major components of the TIP system. This application involves no significant change in the i types or significant increase in the amounts of any effluent that may be released offsite, and there will be no significant increase in individual or cumulative occupational i radiation exposure. -

Conclusion The Plant Operations Review Committee and the Nuclear Review Board have reviewed -

these proposed changes and have concluded that they do not involve an unreviewed .

safety question and that they are not a theeat to the health and safety.of the public. ,

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