ML17291B026
| ML17291B026 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/18/1995 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17291B027 | List: |
| References | |
| NUDOCS 9509220253 | |
| Download: ML17291B026 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20SS&0001 ASH NGTON PUBLIC POWER SUPPLY SYST M
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50-0 5
L OJC MEN 0
C OP IN IC S
Amendment No.
141 License No.
NPF-21 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Washington Public Power Supply System (licensee) dated January 14,
- 1992, as supplemented by letters dated February 10,
- 1995, and August 16, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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; 0.
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 Speci-fications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-21 is hereby amended to read as follows:
9509220253 950918 PDR ADQCK '05000397 P
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3.
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
141 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
This amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J
es W. Clifford, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date* of Issuance:
SePtember 18, 1995
TTACHMENT TO LICENS AMENDMENT MENDMENT NO.
141 TO FACI ITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix A Technical Specifications and the bases section with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE 3/4 4-4 3/4 8-16 INSERT 3/4 4-4 3/4 8-16
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Y REACTOR COOLANT SYSTE
~JET PUMP LIMITING CONDITION FOR OPERATION 3.4.1.2 All jet pumps shall be OPERABLE.
BTTICABI TT:
OPNNATIONAI CONOITIONB I 2 2.
~T~ON:
With one or more jet pumps inoperable, 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 />.
SURVEILLANCE RE UIREMENTS NOTES The provisions of Specification 4.0.4 are not applicable provided the surveillance is:
1.
Performed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the associated recirculation loop is in operation.
2.
Performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 25X of RATED THERMAL POWER.
These notes are applicable to both surveillance 4.4. 1.2. 1 and 4.4. 1.2.2.
4.4. 1.2. 1 Each of the above required jet pumps shall be demonstrated 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 determining recirculation loop flow, total core flow and diffuser-to-lower plenum differential pressure for each jet pump and verifying that no twodof the following conditions occur when both recirculation loops are operating.
a.
The indicated recirculation loop flow differs by more than 10X from the established flow control valve position-loop flow characteristicp for two recirculation loop operation.
b.
The indicated total core flow differs by more than 10X from the established total core flow value derived from two recirculation loop flow measurements.
c.
The indicated diffuser-to-lower plenu d fferential pressure of any individual jet pump differs from establi~hed two recirculation loop operation patterns by more than 20X.
4.4. 1.2.2 During single recirculation loop operation, each of the above required jet pumps shall be demonstrated 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 that no two of the following conditions occur:
a.
The indicated recirculation loop flow in the operating loop differs by more than 10X from the established single recirculation flow control valve position-loop flow characteristics:
b.
The indicated total core flow differs by more than 10X from the established total core flow value derived from single recirculation loop flow measurements.
c.
The indicated diffuser-to-lower plenum differential pressure of any individual jet pump differs from established single recirculation loop patterns by more than 20X.
WASHINGTON NUCLEAR UNIT 2 3/4 4-4 Amendment No. QB, 141
lI I
ELECTRICAL POWER SYSTEMS D.C.'OURCES -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, Division 1 or Division 2, and, when the HPCS system is required to be OPERABLE, Division 3, of the D.C. electrical power sources shall be OPERABLE with:
a 0 b.
C.
Division l.
125 2.
250 3.
224 4.
125 5.
250 6.
224 Division 1.
125 2.
f24 3.'25 4.
224 Division 1.
125 2.
125 1, consisting of:
volt battery Bl-l.
volt battery B2-1.
volt batteries BO-1A and B0-1B.
volt full capacity charger Cl-1.
volt full capacity charger C2-1.
volt full capacity chargers CO-1A and C0-1B.
2, consisting of:
volt battery Bl-2.
volt batteries BO-2A and B0-2B.
volt full capacity charger Cl-2.
volt full capacity chargers CO-2A and C0-28.
3, consisting of:
volt battery Bl-HPCS.
volt full capacity charger Cl-HPCS.
APPLICABILITY:
OPERATIONAL CONDITIONS 4, 5 and ".
ACTION:
a.
With less t%an the Division 1 and/or Division 2 battery and/or charger of the above required D.C. electrical power sources
- OPERABLE, suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.
b.
With Division 3 battery and/or charger of the above required D.C.
electrical power sources inoperable, declare the HPCS system inoperable and take the ACTION required by Specification 3.5.2 and 3.5.3.
c.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE UIREMENTS 4.8.2.2 At least the above required battery and charger shall be demonstrated OPERABLE per Surveillance Requirement
- 4. 8. 2. 1.
When handling irradiated fuel in the secondary containment.
WASHINGTON NUCLEAR " UNIT 2 3/4 8-15
ELECT ICAL POWER SYSTEMS 3 4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS S
R BUTION OPERATING LIMITING CONDITION FOR OPERATION 3.8.3. 1 The following power distribution system divisions shall be energized with tie breakers open between redundant buses within the unit:
a.
A.C. Power Distribution 1.
Division 1, consisting of:
a) 4160-volt bus SH-7.
b) 480-volt bus SL-71 and SL-73.
c) 480-volt HCC's 7A, 7A-A, 7B, 7B-A, 7B-B, 7F.
d) 480-volt Power Panel PP-7A-B.
e) 120/208-volt 38 Power Panels PP-7A-G, PP-7A-A-A.
f) 120/240-volt 18 Power Panels PP-7A-A,.PP-7A-F, PP-7A-E, and PP-7A.
2.
Division 2, consisting of:
a) 4160-volt bus SH-8.
b) 480-volt bus SL-81 and SL-83.
c) 480-volt HCC's 8A, 8A-A, 8B, 8B-A, 8B-B, 8F.
d) 480-volt Power Panel PP-8A-B.
e) 120/208-volt 38 Power Panels PP-BA-G, PP-BA-A-A.
f) 120/240-volt 18 Power Panels PP-8A-A, PP-BA-F, PP-BA-E, and PP-BA.
3.
Division 3, consisting of:
a) 4160-volt tgs SH-4.
b) 480-volt 38 Engine
& Gen.
Aux. loads Power Panel.
c) 120/240-volt 18 Power Panel PP-4A.
d) 480-volt MCC 4A.
D.C.
Power Distribution 1.
Division 1, consisting of:
a) 125-volt D.C. Main Distribution Panel Sl-l.
b) 125-volt VDC Motor Control Center MC-S1-1D.
c) 125-VDC Instr.
and Control NSSS Bd. Distr. Panel DP-S1-1A.
d) 125-VDC Remote Shutdn. Distr. Pnl. DP-Sl-lD.
e) 125-VDC Diesel Gen.
1 Dist. Pnl. DP-S1-1E.
f) 250-VDC Hain Distribution Panel S2-1.
g) 250-VDC Motor Control Center MC-S2-1A, Part A and Part B.
h) f24-VDC Power Panel DP-SO-A.
i) 125-VDC Critical Swgr. Dist. Pnl. DP-Sl-1F 2.
Division 2, consisting of:
a) 125-volt D.C. Hain Distribution Panel S1-2.
b) 125-volt VDC Hotor Control Center MC-S1-2D.
c) 125-VDC Instr.
and Control NSSS Distr. Panel DP-S1-2A.
d) 125-VDC Critical Swgs.
& Remote Shutdn. Distr. Pnl.
DP-S1-2D.
e) 125-VDC Diesel Gen.
2 Dist. Pnl.
DP-S1-2E.
f) i24-VDC Power Panel DP-SO-B.
3.
Division 3, consisting of 125-volt D.C.
HPCS distribution panel.
I I'ASHINGTON NUCLEAR UNIT 2 3/4 8-16 Amendment No.
141