ML022340412

Correction of a Technical Specification Typographical Error

ML022340412
Person / Time
Site:	Pilgrim
Issue date:	08/14/2002
From:	Riggs W Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2.02.074
Download: ML022340412 (6)

Text

Entergy Nuclear Operations, Inc.

'c Entergy Pilgrim Station 600 Rocky Hill Road Plymouth, MA 02360 William J. Riggs Director, Nuclear Assessment August 14, 2002 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 Correction of a Technical Specification Typographical Error

REFERENCES:

1. Issuance of Amendment No. 176 to Facility Operating License No DPR-35, Pilgrim Nuclear Power Station, Containment Cooling Ultimate Heat Sink Inlet Temperature (TAC MA1 150),

dated July 28, 1998

2. Proposed Guidance for Correction of Technical Specification Typographical Errors; SECY-96-238, Dated November 19, 1996 LETTER NUMBER: 2.02.074

Dear Sir or Madam:

This letter requests NRC approval of a correction of an inadvertent typographical error in Pilgrim Technical Specifications which was inadvertently introduced during License Amendment 176 (Reference 1).

It was not addressed in the notipe to the public nor reviewed by the NRC and falls within the scope of the guidance provicd'eain SECY-96-238 (Reference 2) for corrections.

Attachment 1 describes the typographical error and correction. Attachment 2 provides a mark-up of Technical Specification page. Entergy will issue change notifications to all holders of controlled copies of Pilgrim Technical Specifications upon receipt of NRC approval of this correction.

202074

Entergy Nuclear Operations,, inc. Letter Number 2.02.074 Pilgrim Nuclear Power Station Page 2 Ifyou have any questions regarding the information contained in this letter, please contact Mr. Bryan Ford (508) 830-8403.

Sincerely, J

Attachments: 1. Description of Technical Specification Typographical Error - (1 page)

2. Marked-up Technical Specification Page Correcting the Typographical Error - (1 page) cc:

Mr. Travis Tate, Project Manager U.S. NRC Region 1 Office of Nuclear Reactor Regulation 475 Allendale Road Mail Stop: 0-8B-1 King of Prussia, PA 19406 U.S. Nuclear Regulatory Commission 1 White Flint North Senior Resident Inspector 11555 Rockville Pike PNPS Rockville, MD 20852 202074

ATTACHMENT 1 DESCRIPTION OF TECHNICIAL SPECIFICATION TYPOGRAPHICAL ERROR

A. REQUESTED ACTION Consistent with the information contained in SECY-96-238, Pilgrim Station is requesting a correction to an inadvertent typographical error that was introduced into the Pilgrim Technical Specification.

B. TYPOGRAPHICAL ERROR A typographical error was inadvertently introduced into the Pilgrim Technical Specification (TS) during License Amendment 176 (Reference 1). The specifics of this error and proposed correction is described below.

TS page 3/4.5-8 Amendment 176 approved TS 4.5.D. with "HPCI system testing shall be as follows."

This Specification is on TS page 3/4 .5-8. During the word processing of this page, "HPCI" was accidentally used instead of "RCIC". With the correction, TS 4.5.D should read as "RCIC system testing shall be as follows:"

This error was not noticed to the public nor approved by the NRC during review and approval of Amendment 176.

The above error was discovered during the use of applicable specifications. This typographical error did not cause any safety issues.

Attachment 2 provides the marked-up TS page with the correction to the typographical error.

C. CORRECTIONS TO THE AFFECTED TECHNICAL SPECIFICATION PAGE SECY-96-238 (Reference 2) provides guidance to correct inadvertent typographical errors in the Technical Specification pages.

The above typographical error was not noticed to the public nor reviewed by the NRC as part of the applicable amendment process. Therefore it may be corrected without a license amendment.

Accordingly, upon approval from the NRC, corrected TS page 3/4.5-8 will be distributed to all holders of controlled Technical Specifications.

1

V.

ATTACHMENT 2 MARKED-UP TECHNICAL SPECIFICATION PAGE CORRECTING THE TYPOGRAPHICAL ERROR TS PAGE 3/4.5-8

LiMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS SYSTEMS D. Reactor Core Isolation Coolinq D. Reactor Core Isolation Coolinq (RCIC)

(RCIC) System System

1. The RCIC system shall be 1. 42!gjsystem testing shall be as operable whenever there is follows:

irradiated fuel in the reactor vessel, reactor pressure is greater than a. Simulated Once/

150 psig, and reactor coolant Automatic Operating temperature is greater than 365°F, Actuation Test Cycle except as specified in 3.5.D.2 below. b. Pump When tested as Operability specified in

2. From and after the date that the 3.13, verify that RCIC system is made or found to the RCIC pump be inoperable for any reason, delivers at least continued reactor operation is 400 GPM at a permissible only during the system head succeeding 14 days unless such corresponding system is sooner made operable, to a reactor providing that during such 14 days pressure of the HPCIS is operable. 1000 psig.

3. If the requirements of 3.5.D cannot c. Motor As Specified be met, an orderly shutdown of the Operated in 3.13 reactor shall be initiated and the Valve reactor shall be in the Cold Operability Al Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. d. Flow Rate at Once/

150 psig. operating cycle verify that the RCIC pump delivers at least 400 GPM at a system head corresponding to a reactor pressure of 150 psig.

The RCIC pump shall deliver at least 400 GPM for a system head corresponding to a reactor pressure of 1000 to 150 psig.

)

Amendment No. 176 3/4.5-8 I