ML20044G618

Application for Amend to Licenses DPR-44 & DPR-56,consisting of TS Change Requests 92-06,93-03 & 93-04 Re Removing Ref to Svc Platform Hoist,Correcting Typo in Transformer Setpoint Tolerance & Switch Recalibration

ML20044G618
Person / Time
Site:	Peach Bottom
Issue date:	05/25/1993
From:	Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20044G619	List: ML20044G618 ML20044G632
References
NUDOCS 9306040017
Download: ML20044G618 (9)

Text

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PIIILADELPIIIA ' ELECTRIC COMPANY 10 CFR 50.90' o

NUCLEAR GROUP HEADQUARTERS 955-65 CHESTERBROOK BLVD. May 25, 1993 WAYNE. PA 19087-5691 Docket Nos. 50-277 (215) 640am 50-278 '

License Nos. DPR-44 DPR-56 STATION SUPPORT DEPARTMENT l U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 ,

SUBJECT:

Peach Bottom Atomic Power Station, Units 2 and 3 Technical Specification Change Request

Dear Sir:

Philadelphia Electric Company (PECo) hereby submits Technical Specification Change Requests (TSCR) 92-06, 93-03 and 93-04, in accordance with 10 CFR 50.90, requesting changes to Appendix A of the Peach Bottom Atomic Power Station (PBAPS)

Operating Licenses.

TSCR's 92-06, 93-03 and 93-04 are proposed administrative changes concerning the following: removal of references to the ,

Service Platform Holst (92-06); correction of a typographical error concerning the Emergency Transformer Degraded Voltage relay setpoint tolerance (93-03) and; recalibration of pressure switches using reactor thermal power instead of turbine first stage pressure (93-04).

Attachment 1 to this letter describes the proposed changes-and Attachment 2 contains the revised Technical Specification <

pages.

If you have any questions concerning this submittal, please contact us.

Sincerely, u .

• • * * ^' """ " ' ** '

• 620042 Licensing Section

Enclosures:

Affidavit, Attachment 1, Attachment 2 cc: T. T. Martin, Administrator, Region I, USNRC J. J. Lyash, Senior Resident Inspector, PBAPS, USNRC W. P. Dornsife, Commonwealth of Pennsylvania 9306040017 930525-O' )

PDR ADOCK 05000277 P PDR k{,

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COMMONWEALTH OF PENNSYLVANIA:

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COUNTY OF CHESTER  :

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G. R. Rainey, being first duly sworn, deposes and says. ,

That he is Vice President of Philadelphia Electric Company, the applicant herein; that he has read the attached Technical Specification Change Requests (TSCR's) 92-06, 93-03 and 93-04 for changes to the Peach Bottom Facility Operating Licenses DPR-44

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and DPR-56, and knows the contents thereof: and that the statements and matters set forth therein are true and correct to

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the best of his knowledge, information and belief.

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Vice President

'i Subscribed and sworn to beforemethish day of 1993.

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'i ATTACHMENT 1 l i

'l PEACH BOTTOM ATOMIC POWER STATION i UNITS 2 AND 3 -!

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Docket Nos. 50-277 50-278

'l License Nos. DPR-44 DPR-56 TECHNICAL SPECIFICATION CHANGE REQUEST ~

92-06

" Service Platform Hoist" 93-03

" Emergency Transformer Degraded Voltage Relay Tolerance" 93-04

" Basis Change for the Turbine Control Valve Fast Closure and Turbine Stop Valve Closure Scram Signal Bypass Setpoint" Supporting Information for Changes

Docket Nos. 50-277

. 50-278'

_t License Nos..DPR-44 DPR-56 i

Philadelphia Electric Company (PECo),. Licensee under Facility Operating License DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3'respectively, requests that the Technical Specifications contained in Appendix A to the Operating Licenses be amended. Proposed changes to the Technical Specifications are indicated by vertical bars in the margins of the pages contained in Attachment 2 and listed here:

TSCR 92-06; 226, 229 TSCR 93-03; 71b (Table 3.2.B)

TSCR 93-04; 39, 49, 50 The proposed changes concern the deletion of references to the Service Platform Hoist (TSCR 92-06); the correction of a typographical error involving the Emergency Transformer Degraded Voltage Relay setpoint tolerance (TSCR 93-03); and a basis change for establishing.the scram signal bypass setpoint, for Turbine-Control Valve Fast Closure (TCVFC) and Turbine Stop Valve Closure-(TSVC).

License proposes that the changes be effective as of.the '

issuance date of the license amendments.

Description of Change Licensee proposes the following changes:

TSCR 92-06 (1) Delete the wording "or the service platform hoist", and add the word "or" in Limiting i Condition for Operation (LCO) 3.10.A.4, page'226, to read:

"If the frame-mounted auxiliary hoist or the monorail-mounted auxiliary hoist is to be used for handling fuel with the head off the reactor vessel, the load limit switch on the hoist to be used shall be set at s 400 lbs."

1 (2) Delete item #5 on 3.10 BASES, A. Refueling I Interlocks, page 229.

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Docket Nos. 50-277

, 50-278 License Nos.'DPR-44 DPR-56 (3) Delete Surveillance Requirement 4.10.A.3, page 226. (Unit 3 only)

This requirement was in effect during the period prior to completion of tensioning the reactor vessel head bolts for Unit 3 Cycle 8 refueling outage.

(4) Delete asterisk and corresponding footnote in second paragraph of 3.10 BASES, A. Refueling '

Interlocks, page 229. (Unit 3 only)

This requirement was not in effect during the period prior to completion of tensioning the reactor vessel head bolts for Unit 3 Cycle 8 refueling outage.

TSCR 93-03 (1) Add a minus sign to the setpoint tolerance of the ,

Emergency Transformer Degraded Voltage Relay. The Trip Level Setting for Trip Function " Emergency t Transformer Degraded voltage (Inverse time -

voltage). (CV-6)" on Table 3.2.B, page 71b should r read:

87% (15%) of

• Rated Voltage.

Tests at 2940 volts in 30 seconds (110%) .

TSCR 93-04 (1) Revise note 4 on Notes for Table 3.1.1, page 39, to read:

" Bypassed when reactor thermal power is less than 30% of rated as indicated by turbine first stage  ;

pressure." '

(2) Revise wording of last paragraph in BASES Section 3.1, page 49, to read:

" Turbine stop valve closure occurs at 10% of. valve closure. Below 30% of rated reactor thermal power

Docket Nos. 50-277

. 50-278 License Nos. DPR DPR-56 the scram signal due to turbine stop valve closure is bypassed because the flux and pressure scrams are adequate to protect the reactor."

1 (3) Revise the last sentence of the first paragraph of a BASES Section 3.1 (cont'd), page 50, to read:

"This scram signal is also bypassed when reactor thermal power is less than 30% of rated as indicated by turbine first stage pressure." >

Safety Discussion TSCR 92-06 The proposed change is intended to clarify the Technical Specifications by removing references to the Service Platform Hoist. The Service Platform Hoist and its associated load i sensing switches have been removed since 1985. Additionally, the refueling interlock circuit which prevents the operation of the  ;

Service Platform when its hoist is loaded has been altered by- a modification 5221. Because the Service Platform Hoist no longer ,

physically exists, the Technical Specifications will be revised by deleting references to it. Deletion of those references will t enhance safety by eliminating confusion in interpreting the Technical Specifications.

TSCR 93-03 The proposed change is intended to correct a typographical error that has existed since the issuance of amendment numbers 97 (Unit 2) and 99 (Unit 3) to the Technical Specifications. The typographical error involves the setpoint tolerance of the Emergency Transformer Degraded Voltage Relay (87% (15%) vs. 87%

(+5%)).

By letter dated April 11, 1984 the NRC transmitted the approved amendments 97 and 99 in response to a PECo application for amendment to the PBAPS Technical Specifications. Upon I receipt of the approved amendments it was discovered that a typographical error, that originated with the amendment I application, existed on page 71b. PECo notified the NRC by j letter dated June 25, 1984, of the typographical error and 1

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. Docket-Nos. 50-277'

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. 50-278 License Nos. DPR-44 i DPR-56' requested the NRCJto reissue page 71b, which to date remains outstanding. Recent conversations with the NRC staff concluded with a recommendation that a new TSCR be submitted to address the >

typographical error.

The PBAPS Plant Operation Review Conmittee (PORC) has developed PORC Position #60 to interpret the Technical Specifications until an approved TSCR can be obtained. The proposed change is administrative only and corrects a r typographical error. This request has no impact on safety.

TSCR 93-04 TSCR 93-04 proposes.a change in the basis for which the TCVFC and TSVC scram signal bypass setpoints are established.

Currently, the PBAPS Technical Specifications are worded ambiguously in that the 30% power setpoint used for the TCVFC and TSVC scram bypass setpoint could be interpreted as 30% rated turbine- power instead of the correct basis of 30% rated reactor thermal power. General Electric Company's (GE) Service Information Letter-(SIL) 423 recommended that licensees review-their Technical Specifications to insure that the correct: power bases were clearly stated. Upon review of the PBAPS Technical Specifications it was determined that the wording was ambiguous.

The proposed change will enhance safety by removing the ambiguous wording thereby eliminating confusion when interpreting the ..

Technical Specifications. 't No Sionificant Hazards Consideration Licensee proposes that this application does not involve 1 significant hazards considerations for the followin tnasons:

i) The proposed chance does not involve a sianificant increase in the probability or consecuences of an accident previous 1v evaluated R TSCR 92-06 proposes to delete references to the Service  !

Platform Hoist due to the fact that it has been l physically removed from service. Deletion lof these I references will enhance safety by providing clarity j when interpreting the Technical Specifications. l TSCR 93-03 proposes to correct a typographical error 'l regarding the setpoint tolerance of the Emergency H l

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Docket Nos. 50-277  ;

50-278

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License-Nos. DPR-44 DPR-56 Transformer Degraded. Voltage Relay. Correction of this typographical error will enhance safety by eliminating confusion in interpreting the Technical Specifications.

TSCR 93-04 proposes to change the basis, based on GE SIL 423, for which the bypass setpoint for the Turbine Stop Valve Closure and the Control Valve Fast Closure scram signals are established.

Because the above proposed changes are administrative ,

in nature, they do not affect the initial conditions cn .

precursors assumed in the Updated Final Safety Analysis '

Report Section 14. These changes do not decrease the effectiveness of equipment relied upon to' mitigate the previously evaluated accidents.

Therefore, there is no increase in the probability or consequences of an accident previously evaluated.

ii) The proposed chance does not create the possibility of-a new or different kind of accident from any previously evaluated.

The proposed changes do not make any physical changes to the plant or changes to operating procedures.

Therefore, 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.

Therefore, the proposed changes do not create the possibility of a new or different kind of' accident from any previously evaluated, iii) The proposed chance does not involve a sionificant reduction in a maroin of safety.

The proposed changes are administrative in nature and are intended to provide clarification or eliminate confusion when interpreting the Technical .

Specifications. The proposed changes do not adversely j affect the assumptions or sequence of events used in-any accident analysis.

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Docket Nos. 50-277

. 50-278 .

License Nos. DPR-44 DPR-56 Therefore, the p~roposed changes do not involve a ,

reduction in any margin of safety.

Environmental Impact 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'51.22(c)(9). The proposed changes do not  :

involve any systems or equipment that have a direct relationship with the environment. The changes involve: the deletion of references to the Service Platform Hoist; the correction of a typographical error concerning the Emergency Transformer Degraded Voltage Relay setpoint tolerance and; a change in the basis for establishing the bypass'setpoint for the Turbine Stop Valve Closure and Control Valve Fast Closure scram signals as discussed in the previous section.

The Application involves no significant change in the types or significant increase in the amounts of any effluent that may be released offsite and there will be no significant increase iii  ;

individual or cumulative occupational radiation exposure.

Conclusion The Plant Operations Review Committee and the Nuclear Review Board have reviewed the proposed changes and have concluded that they do not involve an unreviewed safety question: and that they.

are not a threat to the health and safety of the public.

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