ML17191A916

Amends 169 & 164 to Licenses DPR-19 & DPR-25,respectively, Will Change Several TS Values to Reflect Design Values.Ts Values Affect 125/250 Vdc Electrolyte Temp

ML17191A916
Person / Time
Site:	Dresden
Issue date:	10/08/1998
From:	Rossbach L NRC (Affiliation Not Assigned)
To:
Shared Package
ML17191A917	List: ML17191A916 ML17191A918
References
NUDOCS 9810150180
Download: ML17191A916 (9)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555--0001 COMMONWEAL TH EDISON COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION. UNIT 2

. AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

169 License No. DPR-19

1.

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

A.

The application for amendment by the Commonwealth Edison Company (the licensee} dated May 18, 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 1 O CFR Chapter I;

8.

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.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2} of Facility Operating License No. DPR-19 is hereby amended to read.as follows:

(.. :

9810150180 981008 11

• ]

1 PDR ADOCK 05000237 1: __,__,__,__:!'_:. ~----- -----*-. ---~J?R --------, _U __ ____,

_)

'.:. (2)

Technical Specifications.

The Technical Specifications contained in Appendix A, as revised through Amendment No.

169, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 8, 1998 FOR THE NUCLEAR REGULA TORY COMMISSION

~*

L-.(1~

Lawrence W. Rossbach, Project Manager Project Directorate 111-2 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 COMMONWEAL TH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 164 License No. DPR-25

1.

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

A The application for amendment by the Commonwealth Edison Company (the

. licensee) dated May 18, 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 1 O 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 1 O CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi~tions as indicated in the attachment to this license amendment and paragraph 3.B. of Facility Operating License. No. DPR-25 is hereby amended to read as follows:

---

~-*-

-~-,.

~.. *-

e B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.

• f 64, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.

Attachment:

Changes to the Technical Specifications Date of Issuance: October 8, 1998 FOR THE NUCLEAR REGULA TORY COMMISSION Lawrence W. Rossbach, Project Manager Project Directorate 111-2 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NOS. 169 AND 164 FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR-25 DOCKET NOS. 50-237 AND 50-249 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3/4.3-9 3/4.3-9 3/4.4-3 3/4.4-3 3/4.8-5 3/4.8-5 3/4.9-13 3/4.9-13

.. REACTIVITY CONTROL Scram Accumulators 3/4.3.G 3.3 - LIMITING CONDITIONS FOR OPERATION 4.3 - SURVEILLANCE REQUIREMENTS G. Control Rod Scram AccumuJators All control rod scram accumulators shall be OPERABLE.

APPLICABILITY:

OPERATIONAL MODE(s) 1, 2 and 5ca>.

ACTION:

1.

In OPERATIONAL MODE 1 or 2:

a.

With one control rod scram accumulator inoperable, within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s:

1)

Restore the inoperable accumulator to OPERABLE status, or

2)

Declare the control rod associated with the inoperable accumulator inoperable.

b.

With the provisions of ACTION 1.a above not met, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c.

With more than one control rod scram accumulator inoperable, declare the associated control rods inoperable and:

G. Control Rod Scram Accumulators Each control rod scram accumulator shall be determined OPERABLE at least once per 7 days by verifying that the indicated pressure

. is ~ 940 psig unless the control rod is fully inserted and disarmed, or scrammed.

a In OPERATIONAL MODE 5, this Specification is applicable for the accumulators associated with eac;:h withdrawn control rod and is not applicable to control rods removed per Specification 3. 10.1 or 3. 1 O.J.

DRESDEN - UNITS 2 & 3 3/4.3-9 Amendment Nos. 169 & 164

).

. STANDBY LIQUID CONTROL SYSTEM SLCS 3/4.4.A FIGURE 3.4.A-1 SODIUM PENTABORATE SOLUTION TEMPERATURE REOIJIREMENTS

. 15>

140 13>

Accepa~e Q>erating Rarge C1) 110

• ~ 100 f?

C1)

9)

c.

E m C1)

I-70 fl)

5) 40

~v I

5 10 DRESDEN - UNITS 2 & 3

/

/

V"

/

/

/

15 3/4.4-3

/ v

/

/~

~ v 25 35 40 Amendment Nos.

169.& 164

. PLANT SYSTEMS 3.8-LIMITING CONDITIONS FOR OPERATION C.. Ultimate Heat Sink The ultimate heat sink shall be OPERABLE with:

1.

A minimum water level at or above elevation 501 ft 6 in. Mean Sea Level, and

2.

An average water temperature of ;!;95°F.

APPLICABILITY:

OPERATIONAL MODE(s) 1, 2, 3, 4, 5 and*.

ACTION:

With the requirements of the above specification not satisfied:

1.

• In OPERATIONAL MODE(s) 1, 2 or 3, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

In OPERATIONAL MODE(~) 4 or 5 declare the diesel generator cooling water system inoperable and take the ACTION

• required by Specification 3.8.B.

3.

In OPERATIONAL MODE*, declare the diesel generator cooling water system inoperable and take the ACTION required by Specification 3.8.B. The provisions of Specification 3.0.C are not applicable.

UHS 3/4.8.C 4.8 - SURVEILLANCE REQUIREMENTS C.

Ultimate Heat Sink The ultimate heat sink shall be determined OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the average water temperature and water level to be within their limits.

When handling irradiated fuel in the secondary containment, during CORE AL TERATION{s), and operations with a potential to drain the reactor vessel.

DRESDEN - UNITS 2 & 3 3/4.8-5 Amendment Nos. 169 & 164

. ELECTRICAL POWER SYSTEMS D.C. Sources - Operating 3/4.9.C 3.9-LIMITING CONDITIONS FOR OPERATION 4.9 - SURVEILLANCE REQUIREMENTS

2.

With one of the above required 125 volt station batteries and/or chargers inoperable, within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s1c1, either restore the inoperable equipment to OPERABLE status, or place an OPERABLE corresponding alternate 125 volt battery (with an OPERABLE full capacity charger) in service.

3.

Y'ith the provisions of either ACTION 1

. or 2 above not met, be in at least HOT

• SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.

With any Category A parameter(s) outside the limit(s) shown in Table 4.9.C-1, the battery may be considered OPERABLE provided that its associated charger is OPERABLE, and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> all the category B measurements

. are taken and found to be within their allowable values, and provided all Category A and B parameter(s) are restored to within limits within the next 6 days.

• 5.

With any Category B parameter(s) outside the limit(s) shown in Table 4:9.C-1, the battery may be considered OPERABLE p"rovided that the Category B

. parameters are within their allowable **

values and provided the Category B paramete'r(s) are restored to within the limit(s) within 7 days.

c.

The average electrolyte temperature of all connected cells is above 65°F.

3. At least every 18 months by verifying that:

a.

The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration.

b.

The cell-to-cell and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

c.

• The resistance of each cell-to-cell and terminal connection is

d 50 x 10*5 ohms or => 20 % above

• baseline connection resistance, whichever is higher.

d.

The battery chargers will supply a load equal to the manufacturer's rating for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.

At least every 18 months, by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actua*1 or simulated emergency loads for design duty cycle when the battery is subjected to a battery service test.

c With Unit 2 and 3 in OPERATIONAL MODE{s) 1, 2 or 3, each 125 volt battery may be inoperable for. up to a maximum of seven days per operating cycle for maintenance or testing* provided the alternate 125 volt battery is placed into service and is OPERABLE. If it is determined that a 125 volt battery need be replaced as a result.of maintenance or testing, a specific battery may be inoperable for an additional seven days provided the alternate 125 volt battery is placed into service and is OPERABLE. With the other Unit in MODE{s) 4 or 5, operations may continue with one of the two 125 volt battery systems inoperable provided the alternate 125 volt battery is placed into service and is OPERABLE.

DRESDEN - UNITS 2 & 3 3/4.9-13 Amendment Nos. 169 & 164