RC-17-0175, Correction to Amendment No. 170 Request to Revise Technical Specifications to Correct Administrative Error

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Correction to Amendment No. 170 Request to Revise Technical Specifications to Correct Administrative Error
ML18031A763
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 01/31/2018
From: Lippard G
South Carolina Electric & Gas Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RC-17-0175
Download: ML18031A763 (8)
v • d • e


Text

SCE&G@

A SCANA COMPANY Document Control Desk U.S. Nuclear Regulatory Commission Washington, D. C. 20555-0001

Dear Sir I Madam:

George A. Lippard Vice President, Nuclear Operations 803-345-4810 January 31, 2018 RC-17-0175

Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 CORRECTION TO AMENDMENT NO. 170. REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO CORRECT AN ADMINISTRATIVE ERROR

References:

1.

George F. Wunder, NRR, letter to VCSNS, "Issuance of Amendment No. 118 to Facility Operating License No. NPF-12 Regarding Accident Monitoring Instrumentation - Virgil C. summer Nuclear Station, Unit No. 1 (TAC NO.

M88546) Dated November 7, 1994.

This letter requests Nuclear Regulatory Commission (NRC) approval of a correction of a typographical error in the VCSNS Unit 1 Technical Specification (TS), which was inadvertently introduced during License Amendment 118 (Reference 1 ).

This typographical error was neither addressed in the notice to the public, nor reviewed by the NRC, and thus falls within the scope of the guidance provided by SECY-96-238 (ADAMS Accession No. 9611250030 (Legacy Library)) for corrections.

Attachment I describes the typographical error and corrections. Attachment 11 provides the Amendment 170 page as-issued, with the requested correction noted. Attachment Ill contains the corrected Amendment 170 page.

This document contains no new commitments.

If you have any questions about this submittal, please contact Mr. Michael S. Moore at (803) 345-4752.

I certify under penalty of perjury that the foregoing is true and correct.

7 Executed on

,~>£J?

~.LJPPard V. C. Summer Nuclear Station* P. 0. Box 88
  • Jenkinsville, South Carolina* 29065. F (803) 941-9776. www.sceg.com

Document Control Desk RC-17-0175 CR-09-02760 Page 2 of 2 RLP/GAL/wk Attachments:

Attachment I - Description of Technical Specification Typographical Error Attachment II - Marked up Technical Specification Pages 11-Clean Technical Specification Pages c:

K. Kissam J. Addison J.B. Archie N.S.Carns J. H. Hamilton G. J. Lindamood W. M. Cherry C. Haney S. A. Williams K. M. Sutton S. E. Jenkins Paulette Ledbetter NRC Resident Inspector NSRC RTS (CR-09-02760)

File (813.20)

PRSF (RC-17-0175)

Document Control Desk Attachment I RC-17-0175 CR-09-02760 Page 1 of 2 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)

DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 Attachment I Description of Technical Specification Typographical Error

Document Control Desk Attachment I RC-17-0175 CR-09-02760 Page 2 of 2

1. Requested Action Consistent with the information contained in SECY-96-238, Proposed Guidance for Correction of Technical Specification Typographical Errors, South Carolina Electric & Gas (SCE&G) is requesting a correction of a typographical error that was inadvertently introduced into the Virgil C. Summer Nuclear Station (VCSNS) Unit 1 Technical Specification (TS).
2. Typographical Error One typographical error was introduced into the VCSNS TSs during implementation of License Amendment 118 (Reference 1 ). The specification of the error and proposed corrections are described below:

Review of TS Table 3.3-10 revealed an error that is typographical in nature. During the review it was discovered that TS Table 3.3-10 "Accident Monitoring Instrumentation", Item 7 "Reactor Coolant Inlet Temperature - T cold-Wide Range Instrument Loop/Indicator" states Channel E ITE-430/ITR-410.

The Channel E was found not to be in accordance with guidance provided in RG 1.97 and was submitted as Channel E, instead of Channel D, in error under TS change (TSP-930011) and subsequently approved by the NRC as License Amendment 118 (TAC No. M88546). The error was introduced during licensing development of the proposed change to TS Change TSP-930011. TSP-930011 revised TS Table 3.3-10 identifying and incorporating Accident Monitoring Instrumentation into VCSNS TS Item 7 of TS Table 3.3-10.

VCSNS is requesting to change Channel E, to Channel D ITE-430/ITR-410, to comply with RG 1.97.

3. Correction to Affected Pages SECY-96-238 provides guidance to correct inadvertent typographical errors in the TS. The error described above was neither posted in the public notices nor was it reviewed by NRC as part of the license amendment process. Therefore, it may be corrected without a license amendment.

Accordingly, upon approval from the NRC, a corrected TS Page 3/4 3-57 will be issued to all holders of a controlled TS.

Document Control Desk 1 RC-17-0175 CR-09-02760 Page 1 of 2 VIRGIL C. SUMMER NUCLEAR STATION {VCSNS)

DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 Attachment II Marked Up Technical Specification Pages

TABLE 3.3*10 ACCIDENT MONITORING INSTRUMENTATION en REQUIRED MINIMUM c s:

NO.OF CHANNELS

~

INSTRUMENT CHANNELS OPERABLE m

JJ 1..

Reactor Building Pressure.. Narrow Range 2

1

' c Instrument Loop/In di ca tor:

z

-I Channel D IPT-951/IPl-951 Channel. B IPT-952/IPl.. 952

2.

Reactor Building Pressure

  • Wide Range 2

1 Instrument Looptrndica tor:

Channel D IPT-954NIPl*954A Channel E f PT-9548/IPl-9548

3.

Reactor Building Radf ation Level - High Range 2

1 Instrument Loop/Indicator:

Channel A RMG-18

~

Channel B RMG-7

~

4.

Deleted ta)

I Ul

5.

Reactor Building/AHR Sump Level 2

1 Instrument loop/Indicator:

Channel A ILT-1969/ILT-1969 Channel B ll T-1970/ILl-1970

6.

Reactor Coolant Outlet Temperature

  • T Hot-Wide Range 2

1 Instrument Loop/Indicator:

~

Channel A ITE*413/ITl*413 CD Channel A ITE-423/ITl-423

J Channel E lTE-433/JTR-413
a.

3

7.

Reactor Coolant Inlet Temperature* Teold* Wide Range CD 2

1

3 -

Instrument Loopnndlcator:

z

?

Channel E ITE-410/tTl*410

-~

Channel E ITE-420/ITf-420 Channel-E-ITE-430/ITR*410

'-J

\\

0

[QJ

Document Control Desk Attachment Ill RC-17-0175 CR-09-02760 Page 1 of 2 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)

DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 Attachment Ill Clean Technical Specification Pages

TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION

(/)

REQUIRED MINIMUM c

~

NO.OF CHANNELS

~

INSTRUMENT CHANNELS OPERABLE m

0
1.

Reactor Building Pressure - Narrow Range 2

1 c

Instrument Loop/Indicator:

z

-I Channel D IPT-951/IPl-951

....lo.

Channel B IPT-952/IPl-952

2.

Reactor Building Pressure - Wide Range 2

1 Instrument Loop/Indicator:

Channel D IPT-954A/IPl-954A Channel E IPT-954B/IPl-954B

3.

Reactor Building Radiation Level - High Range 2

1 Instrument Loop/Indicator:

Channel A RMG-18 w

Channel B RMG-7

~

4.

Deleted w

I 01

~

5.

Reactor Building/RHR Sump Level 2

1 Instrument Loop/Indicator:

Channel A ILT-1969/ILl-1969 Channel B ILT-1970/ILl-1970

6.

Reactor Coolant Outlet Temperature - T Hot-Wide Range 2

1 Instrument Loop/Indicator:

)>

Channel A ITE-413/ITl-413 3

Channel A ITE-423/ITl-423 CD

J Channel E ITE-433/ITR-413 0...

3

7.

Reactor Coolant Inlet Temperature - T cold - Wide Range 2

1 CD

J Instrument Loop/Indicator:

z

~

Channel E ITE-41O/ITl-410

-~

Channel E ITE-420/ITl-420 Channel D ITE-430/ITR-410

....lo.

~

0

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