ML20072B953

Application for Amend to License DPR-34,consisting of Proposed Changes to Tech Specs Updating Inservice Insp & Testing Programs

ML20072B953
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/22/1983
From:	Lee O PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20072B947	List: ML20072B946 ML20072B953 ML20072B963
References
NUDOCS 8303080096
Download: ML20072B953 (9)

Text

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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of the Facility Operatin', License)

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of ) Docket No. 50-267

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PUBLIC SERVICE COMPANY OF COLORADO )

Application for Amer.dment to Appendix A of. Facility Operating License License No. DPR-34 0F THE PUBLIC SERVICE COMPANY OF COLORADO FOR THE FORT S7 VRAIN NUCLEAR GENERATING STATION This application for Amendment to Appendix A of Facility Operating License, License No. DPR-34, is submitted for NRC review and approval.

Respectfully submitted, PUBLIC SERVICE COMPANY OF COLORADO By S/0. R. Lee

0. R. Lee, Vice President KELLY, STANSFIELD & 0'DONNELL Bryant O'Donnell Robert E. Thompson Public Service Company Building Denver, Colorado 80202 Attorneys for Applicant B303000096 830222 PDR ADOCK 05000267 p PDR

STATE OF COLORADO )

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CITY AND COUNTY OF. DENVER)

0. R. Lee, being first duly sworn, deposes and says; That he is Vice President of Electric Production of Public Service Company of Colorado, the Licensee herein; that he has read the foregoing Application for Amendment to Appendix A of Facility Operating License and knows the contents thereof, and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.

S/0. R. Lee

0. R. Lee Subscribed and sworn to before me this 22 8E day of February, 1983.

Witness my hand and official seal.

My commission expires: OcXo8 69- Q /983 .

- ('N , (j' e mour- \)y

• Jr l No'tary )ublic /

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ATTACHMENT 1

SUMMARY

OF THE CHANGES TO THE TECHNICAL SPECIFICATIONS l

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Attachmint 1 Page 1

1. CHANGES BETWEEN PROPOSED PLANT TECHNICAL SPECIFICATIONS AND CURRENT TECHNICAL SPECIFICATIONS Section 2.18 Surveillance Interval Clarified definition.

Section 5.0 Surveillance Requirements Added .the in-service inspection (ISI) surveillance requirements implementation criteria.

SR 5.1.2 Reserve Shutdown System Surveillance .

(Ref. PSC Letter P-80014) .

a) Added test of the RSS quick disconnect valves and monitoring of ACM valve actuation gas pressure.

b) Unchanged c) Unchanged d) Editorial change.

e) Unchanged f) New requirement for examination of pipe sections which require disassembly and reassembly within the refueling penetrations.

g) New requirement to test the operability of the reserve shut-down system remote controls.

Basis - Added description of ACM valve actuation system and sur-veillance testing limitations.

SR 5.2.1 f:RV and PCRV Penetration Overpressure Protection Surveillance

(Ref. PSC Letter P-80014)

Changed title to be more accurate.

I j a) PCRV safety valve test frequency modified from each year at shutdown to at each refueling, but not to exceed every five years.

New requirement added for examination of PCRV containment l- tank closure bolting and for tank leak testing.

b) Modified to stagger PCRV penetration safety valve testing.

c.1) New requirements for instrument-testing.

c.2) New requirements for instrument testing associated with the PCRV overpressure protection system.

c.3) New requirement for instrument testing associated with the l PCRV penetration overpressure protection system shutoff I valves.

Basis - Clarified testing description.

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Attachment 1 Page 2

. SR 5.2.2 Tendon Corrosion and Anchor Assemblies Surveillance (Ref. PSC Letter P-80034)

Changed title to be more accurate, and clarified specification.

a) Modified to reflect that all corrosion protected wire samples are not 15 feet in length.

b) Editorial change, c) New requirement for examination of prestressing anchor as-semblies.

Basis - Added description of anchor assemblies check.

SR 5.2.3 Tendon Load Cell Surveillance (Ref. PSC Letter P-80034) a) Requirement for load cell reference check unchanged; format change only.

b) New requirement added for testing the load cell alarm cir-cuit.

SR 5.2.4 PCRV Concrete Structure Surveillance (Ref. PSC Letter P-80034)

Changed title to be more accurate.

a) Crack pattern mapping requirement unchanged; format change only, b) Added a new requirement for PCRV deformation and deflection monitoring, originally required for design verification in the FSAR.

c) New requirement for visual examination of the PCRV support structure.

Basis - Expanded monitoring description.

SR 5.2.5 Liner Specimen Surveillance (Ref. PSC Letter P-80034)

Basic requirement unmodified, but the specimen removal frequency was changed from calendar years to refueling cycles.

Basis - Editorial changes.

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Attachment 1 Page 3 SR 5.2.11 Primary Reactor Cooling Radioactivity Surveillance Corrected typographical error.

SR 5.2.16 PCRV Closure Leakage Surveillance (Ref. PSC Letter P-80014) a) Frequency of PCRV primary and secondary closure leakage testing modified from monthly to quarterly, and from after

, an increase.in pressurization gas flow to after an unantici-pated increase in pressurization gas flow.

b) Unchanged c) New requirement for testing of core support floor and sup-port column pressure monitoring instruments.

d) New requirement for testing isolation valves associated with pressurizing, purging, and venting PCRV closures.

e) New requirement for testing check va'ves in HTFA purge lines.

f) New requirement for testing check valves in HTFA or refueling penetrations.

Basis - Added bases for the new requirements.

SR 5.2.17 Helium Circulator Pelton Wheels (Ref. PSC Letter P-80064)

- Deleted SR 5-2.18 Helium Circulators Surveillance i

(Ref. PSC Letter P-80064 and P-82430)

Added " Surveillance" to the title, changed format, and modified

. examination requirements for helium circulators, after the first examination.

l Basis - Editorial changes only.

SR 5.2.22 pGX Graphite Surveillance (Ref. PSC Letter P-80034)

Editorial change to reflect that destructive techniques are used i to examine the graphite specimens.

I f Basis - Editorial changes only.

Attachm:nt 1 Page 4 SR 5.2.25 Core Suoport Block Surveillance (Ref. PSC Letter P-80034)

New Technical Specification.

SR 5.2.26 Region Constraint Devices Surveillance (Ref. PSC Letter P-80034) .

New Technical Specification.

SR 5.2.27 Helium Shutoff Valve Surveillance (Ref. PSC Letter P-80064)

- New Technical Specification.

SR 5.2.28 PCRV Penetrations and Closures (Ref. PSC Letter P-82430)

New Technical Specification.

SR 5.3.1 Steam / Water Dump System Surveillance (Ref. PSC Letter P-80064)

Changed title to be more accurate, and changed format.

-Al so , modified frequency for steam / water dump tank level indicators functional test from monthly to quarterly, and added new requirements for testing tank pressure and temperature instruments.

Basis'- Added bases for the new requirements.

SR 5.3.2 Main and Hot Reheat Steam Stop Check Valves Surveillance i

(Ref. PSC Letter P-80064)

Full stroke testing deleted from SR 5.3.2 since it is already specified in SR 5.3.4.

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Attachment 1 Page 5 SR 5.3.3 Bypass and Pressure Relief Valves Surveillance (Ref. PSC Letter P-80064)

Changed title to be more accurate, and testing of main steam bypass valves was deleted from SR 5.3.3 since it is already specified in SR 5.3.4.

Basis - Editorial changes only.

SR 5.3.4 Safe Shutdown Cooling Valves, Surveillance (Ref. PSC Letter P-80064)

The testing frequency was modified from twice annually to annually, and a new requirement was added for testing normally closed check valves required to open for actuation of the safe shutdown cooling mode of plant operation.

Basis - Individual valve testing requirements are further de-tailed in the Basis for SR 5.3.4.

SR 5.3.9 Safety Valves Surveillance (Ref. PSC Letter P-80064)

- New Technical Specification.

SR 5.3.10 Secondary Coolant System Instrumentation Surveillance (Ref. PSC Letter P-80064)

New Technical Specification.

SR 5.3.11 Steam Generator Bimetallic Weld Surveillance (Ref. PSC Letter P-82430)

New Technical Specification.

SR 5.4.1 Reactor Protective System and Other Critical Instrumentation and Control Checks, Calibrations, and Tests Reformatted Tables 5.4-1, 5.4-2, 5.4-3, and 5.4-4.

SR 5.9.1 Environmental Radiation, Surveillance Reauirements Reformatted Tables 5.9-1, 5.9-2, and 5.9-3.

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Attachment 1 Page 6

2. CHANGES BETWEEN PR0p0 SED PLANT TECHNICAL SPECIFICATIONS AND DRAFT TECHNICAL SPECIFICATIONS INCLUDED IN PSC PRELIMINARY SUBMITTALS a) Various Technical Specifications have been modified compared to the preliminary Public Service Company draft submittal in order to clarify the specified frequency of examinations and tests. The original intent, however, is preserved. This applies to: SR 5.1.2.g, SR 5.2.1.a and c, SR 5.2.2.a and c, SR 5.2.4.b and c, SR 5.2.5, SR 5.2.14, SR 5.2.16.d and e, SR 5.2.18.b, SR 5.2.26, and SR 5.3.9.

b) SR 5.2.1.b has been modified to specify more accurately the surveillance requirements for PCRV penetration overpressure protection rupture discs.

c) Valve testing specified in SR 5.2.1.c.2 of the preliminary submittal has been deleted from this Technical Specification, since it is already covered in the scope of SR 5.2.16.

d) The requirement for testing and calibration of instruments which monitor moisture in the core support floor and columns has been deleted from proposed SR 5.2.16.c since it is not practical to perform without physical plant modifications.

e) The req;irement for testing and calibration of reheater strainer pressure drop and circulator protective screen ,

pressure drop have been deleted from proposed SR 5.3.10.c since these instruments are currently being removed from the plant by an approved Change Notice. ,

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