ML20237E966

Amends 216 & 216 to Licenses DPR-32 & DPR-37,respectively, Revising TS to Allow Use of Temporary Jumper Line for Providing SW to CCW Heat Exchangers While Maint Performed on Existing SW Supply Piping

ML20237E966
Person / Time
Site:	Surry
Issue date:	08/26/1998
From:	Kuo P NRC (Affiliation Not Assigned)
To:
Shared Package
ML20237E969	List: ML20237E966 ML20237E972
References
NUDOCS 9809010346
Download: ML20237E966 (11)

Text

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION 4

WASHINGTON, D.C. - %

VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 216 License No. DPR-32 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated June 19,1998, as supplemented on July 14,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the

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Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and i

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

4 9909010346 980826 l

PDR ADOCK 05000280 P

PDR J

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attEchment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:

(B)-

Technical Specifications l

The Technical Specifications contained in Appendix A, as revised through Amendment No. 216, are hereby incorporated in the license. The Ncensee shall operate the facility in accordance with the Technical Specifications.

3.

Further, Facility Operating License No. DPR-32 is hereby amended to add condition 3.0 to read as follows:

I O. The use of a temporary, seismic, non-missile protected supply line to provide service water to the component cooling heat exchangers required by TS 3.13, to facilitate maintenance activities on the existing SW supply line, shall be in accordance with the bases and compensatory measures (including a Contingency Action Plan) provided in the licensee's submittal dated June 19,1998 (Serial No.98-327).

4.

This license amendment is effective as of its date of issuance and shall be implemented l

within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION l

%l' w~

l P & sin Kuo, Acting Director h roject Directorate 11-1 l

Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Attachments:

f

1. Page 5a of License DPR-32

2. Changes to the Technical Specifications l,

Date of issuance: August 26, 1998 l

l l

1

-Sa-l K. Secondarv Water Chemistrv Monitorina Proaram The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shallinclude:

1. Identification of a sampling schedule for the critical parameters and control points for these parameters;

2. Identification of the procedures used to quantify parameters that are critical to control points; i

3. Identification of process sampling points;

4. Procedure for the recording and management of data;

5. Procedures defining corre'ctive actions for off control point chemistry conditions; and

6. A procedure for identifying the authority responsible for the interpretation of the data, and the sequence and timing of administrative events required to initiate corrective action.

L. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Nuclear Security Personnel Training and Qualifications Program, including amendments and changes made pursuant to 10 CFR 50.54(p). The approved Nuclear Security Personnel Training and Qualifications Program consists of a document withheld from public disclosure pursuant to 10 CFR 2.790(d) identified as "Surry Power Station Nuclear Security Personnel Training and Qualifications Program" dated September 15,1980. The Nuclear Security Personnel Training and Qualifications Program shall be fully implemented in accordance with 10 CFR 73.55(b)(4), within 60 days of this approval by the Commission. All security personnel shall be qualified within two years of this approval.

M. The design of the reactor coolant pump and steam generator supports may be revised in accordance with the liensee's submittals dated November 5,1985 (Serial No.85-136), December 3,1985 (Serial No. 85-136A), and January 14,1986 (Serial No. 85-136C).

N. Deleted by Amendment No. 203.

O. The use of a temporary, seismic, non-missile protected supply line to provide service water to the component cooling heat exchangers required by TS 3.13, to facilitate maintenance activities on the existing SW supply line, shall be in accordance with the bases and compensatory measures (including a Contingency Action Plan) provided in the licensee's submittal dated June 19,1998 (Serial No.98-327).

4. This license is effective as of the date of issuance, and shall expire at midnight on May 25,2012.

I FOR THE ATOMIC ENERGY COMMISSION Original signed by A. Giambusso A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Enclosure Appendix A-Technical Specifications DSte of issuance: May 25,1972 Surry - Unit 1 Amendment No. 216

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NUCLEAR REGULATORY COMMISSION i

a WASHINGTON, D.C. 30606 4001 l

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f VIRGINIA ELECTRIC AND POWER COMPANY l

DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 216 License No. DPR-37 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Virginia Electric and Power Company (the licensee) dated June 19,1998, as supplemented on July 14,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as~ amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied, i

r

. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:

(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 216, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

Further, Facility Operating License No. DPR-37 is hereby amended to add condition

'3 0 to read as follows:

O. The use of a temporary, seismic, non-missile protected supply line to provide service water to the component cooling heat exchangers required by TS 3.13, to facilitate maintenance activities on the existing SW supply line, shall be in accordance with the bases and compensatory measures (including a Contingency Action Plan) provided in the licensee's submittal dated June 19,1998 (Serial No.98-327).

4.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

[A vc Pa'o-Tsin Kuo, Acting Director

.i Project Directorate Il-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Attachments:

1. Page 6a of License DPR-37

2. Changes to the Technical Specifications Date ofissuance:

August 26, 1998 e

i

4

.. K. Secondarv Water Chemistrv Monitorina Prooram The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shallinclude:

1. Identification of a sampling schedule for the critical parameters and control points for these -

parameters;

2. Identification of the procedures used to quantify parameters that are critical to control points;

3. Identification of process sampling points;

4. Procedure for the recording and management of data;

5. Procedures defining corrective actions for off control point chemistry conditions; and

6. A procedure for identifying the authority responsible for t,he interpretation of the data, and the sequence and timing of administrative events required to initiate corrective action.

L. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Nuclear Security Personnel Training and Qualifications Program, including amendments and changes made pursuant to 10 CFR 50.54(p). The approved Nuclear Security Personnel Training and Qualifications Program consists of a document withheld from public disclosure pursuant to 10 CFR 2.790(d) identified as "Surry Power Station Nuclear Security Personnel Training and Qualifications Program" dated September 15,1980. The Nuclear Security Personnel Training and Qualifications Program shall be fully implemented in accordance with 10 CFR 73.55(b)(4), within 60 days of this approval by the Commission. All security personnel shall be qualified within two years of this approval.

M. The design of the reactor coolant pump and steam generator supports may be revised in accordance with the liensee's submittals dated November 5,1985 (Serial No.85-136), December 3,1985 (Serial l

No. 85-136A), and January 14,1986 (Serial No. 85-136C).

N. Deleted by Amendment No. 203.

O. The use of a temporary, seismic, non-missile protected supply line to provide service water to the component cooling heat exchangers required by TS 3.13, to facilitate maintenance activities on the existing SW supply line, shall be in accordance with the bases and compensatory measures (including a Contingency Action Plan) provided in the licensee's submittal dated June 19,1998 (Serial No.98-327).

4. This license is effective as of the date of issuance, and shall expire at midnight on January 29,2013.

FOR THE ATOMIC ENERGY COMMISSION Original signed by Roger Boyd/for A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Enclosure Appendix A -

Technical Specifications D:te of issuance: January 29,1973 Surry - Unit 2 Amendment No. 216 L

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 216 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 216 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:

Remove Pages insert Pages TS 3.7-20 TS 3.7-20 TS 3.14-1 TS 3.14-1 TS 3.14-4 TS 3.14-4 TS 3.14-5 1

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TS 3.14-1 l-3.14 CIRCULATING AND SERVICE WATER SYSTEMS Applicability Applies to the operational status of the Circulating and Service Water Systems.

1 -

Obiective l

l To' define those limiting conditions of the Circulating and Service Water Systems necessary to assure safe station operation.

Specification A. The Reactor Coolant System temperature or pressure of a reactor unit shall not exceed 350 F or 450 psig, respectively, or the reactor shall not be critical unless:

l. The high level intake canal is filled to at least elevation +23.0 feet at the high level i

intake structure.

2. Unit subsystems, including piping and valves, shall be operable to the extent of being able to establish the following:

Flow to and from one bearing cooling water heat exchanger.

a.

l

b. Flow to and from the component cooling heat exchangers-required by Specification 3.13.

• l

3. At least two circulating water pumps are operating or are operable.

l

4. Three emergency service water pumps are operable; these pumps will service both units simultaneously.

For the purpose of performing inspections, cleaning and repairs associated with the SW supply piping to the component cooling water heat exchangers (CCHXs), a temporary 30" seismic, non-missile protected pipe jumper will be provided to supply SW flow to the CCHXs required by TS 3.13. The basis for using the temporaryjumper is provided in the licensee's submittal dated June 19,1998 (Serial No.98-327). The use of the temporary jumper as the sole SW supply to the CCHXs is permitted two times only for i

a duration of up to 35 days during each of two Unit I refueling outages (Surry Unit 1

(

refueling outages SI-R-15 and SI-R-16). If non-essential SW isolation is required l

during the pipe repair activities, it will be accomplished consistent with design basis l

requirements by using operator (manual) action to close the SW isolation valve in the temporary jumper within the time constraints established by the Station Abnormal Procedures. If the temporaryjumper becomes inoperable as the sole SW supply to the CCHXs during either 35-day period, the requirements of Specification 3.0.1 shall apply. Upon completion of the work associated with the second 35-day period, this footnote will no longer be applicable.

l Amendment Nos. 216 and 216 1

4

...h '.

TS 3.14-4 l

1 l

including replacement of an Emergency Service Water pump without forcing dual unit j

1 outages, yet limits the amount of operating time without the specified number of pumps.

When one Unit is in Cold Shutdown and the heat load from the shutdown unit and spent i

l fuel pool drops to less than 25 million BTU /HR, then one Emergency Service Water pump i

1 may be removed from service for the subsequent time that the unit remains in Cold Shutdown due to the reduced residual heat removal and hence component cooling requirements.

A minimum level of +17.2 feet in the High Level Intake canal is required to provide design flow of Service Water through the Recirculation Spray heat exchangers during a loss-of-coolant accident for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the water level falls below +23' 6",

' signals are generated to trip both unit's turbines and to close the nonessential Circulating and Service Water valves. A High Level Intake canal level of +23' 6" ensures actuation prior to canal level falling to elevation +23'. The Circulating Water and Service Water isolation valves which are required to close to conserve Intake Canal inventory are periodically verified to limit total leakage flow out of the Intake Canal. In addition, passive vacuum breakers are installed on the Circulating Water pump discharge lines to i

assure that a reverse siphon is not continued for canal levels less than +23 feet when Circulating Water pumps are de-energized. The remaining six feet of canal level is provided coincident with ESW pump operation as the required source of Service Water for heat loads following the Design Basis Accident.

To facilitate inspection, cleaning and repair of the SW supply line to the CCHXs, a temporary, seismic, non-missile protected SW supply line (jumper) will be used as discussed in the temporary footnote to TS 3.14.A.2.b. The temporary jumper is required since service water is supplied to the CCHXs by a single concrete-encased line. To remove the SW supply line from service for extended maintenance, an alternate temporary SW supply path is required to support the operation of the CCHXs during the maintenance activities. The basis for using the temporary SW supplyjumper to the CCHXs is provided in the licensee's submittal dated June 19,1998 (Serial No.98-327). The use of the Amendment Nos. 216 and 216

TS 3.14-5 l

temporary jumper as the sole SW supply to the CCHXs is only permitted for a duration of up to 35 days during each of two Unit I refueling outages (Surry Unit I refueling outages SI-R-15 and SI-R-16) and shall be operated in accordance with the compensatory measures (including a Contingency Action Plan) provided in the letter referenced above and in the Operating License. The only automatic function in the normal supply line when Unit 1 is in COLD SHUTDOWN or REFUELING SHUTDOWN is provided by the SW supply MOVs which close on low Intake Canal level. If non-essential SW isolation is 1

required during the time the jumper is in service, it will be accomplished consistent with 1

design and licensing bases requirements by using operator (manual) action to close the SW isolation valve in the temporary jumper within the time constraints established by the

)

l Station Abnormal Procedures.

i Refere'nces:

UFSAR Section 9.9 Service Water System UFSAR Section 10.3.4 Circulating Water System UFSAR Section 14.5 Loss-of-Coolant Accidents, Including the Design Basis I

Accident i

l i

I i

l Amendment Nos. 216 and 216 u_____-----______-_----------_--__-

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