ML18019A821
| ML18019A821 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/15/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NLS-86-155, NUDOCS 8605210011 | |
| Download: ML18019A821 (4) | |
Text
CPSL Carolina Power 5 Light Compttny MAY LS Iggg SERIAL: NLS-86-155
.p(
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.
1 - DOCKET NO.50-000 TURBINE SYSTEM MAINTENANCEPROGRAM
Dear Mr. Denton:
Carolina Power 4 Light Comparty hereby submits additional information concerning the Turbine System Maintenance Program for the Shearon Harris Nuclear Power Plant (SHNPP).
This informatiort is being submitted in response to Safety Evaluation Report (SER) License Condition No. I. Based on discussions with your staff, this information should be sufficient <o delete this license condition.
The turbine rotors in the SHNPP Low Pressure Turbines are of the partial integral rotor design manufactured by Westinghbuse.
The inspection intervals for these rotors were calculated using the Westinghouse method described in Topical Report MSTG-l-P, 3une 1981.
These calculated inspectice intervals, which assure that a crack willnot exceed one-half critical crack size, were found to be greater than 57 years.
These are significantly greater than the normal Westinghouse maintenance schedule of five years.
In addition, the rotor specific probabiiip and missile reports provide inspection intervals for maintaining P 1 values less than 10 which are also signiftcantly Rreater than the normal Westinghouse maintenance schedule.
These reports are based on Westinghouse Topical Reports WSTG-I-P, May 1981; WSTG-2-P, bray 1981; and WSTG-3-P, 3u7y 19&0.
ln either case, these methods bound rotor inspectioh intervals to values greater than normal Westinghouse inspection maintenance recommendations.
The SHNPP Technical Specification, Section 6 willbe revised to establish a Turbine System Maintenance Program in accordance with vendor recommendations.
Based on this Technical Specification and the information provided above, CPRL requests that SER License Condition No.
1 be deleted.
lf you have any questions on this subject or require additional information please contact me.
t Yours very truly, 8605~0.$ ~ eg0g g 5 PDR ADOCK 05000400 PDR 3HE/pgp (38253DK)
S. R im erman ager Nuclear Licensing Section ceo Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-RII)
Mr. Travis Payne (KUDZU)
Mr. Daniel F. Read (CHANGE/ELP)
Wake County Public Library Mr. Wells Eddleman Mr. 3ohn D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)
Dr. 3. H. Carpenter (ASLB)
Mr. 3. L. Kelley (ASLB)
Mr. E. 3. Sullivan (NRC-PAEB) et 1 Feyeltevilte Street
~ P. O. Bo<<1551
~ Rete<gh. N. C, 27602
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS Continued c.
Secondar Mater Chemistr Continued 6."
A procedure identifying (a) the authority responsible for the interpretation of the data and (b) the sequence and timing of administrative events required to initiate corrective action.
d.
Backu Method for Determinin Subcoolin Mar in A program that will ensure the capability to monitor accurately the Reactor Coolant System subcooling margin.
This program shall include the following:
1.
Training of personnel, and 2.
Procedures for monitoring.
e.
Post-Accident Sam lin A program that will ensure the capability to obtain and analyze, under accident conditions, reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere
- samples, The program shall include the following:
1.
Training of personnel, 2.
Procedures for sampling and analysis, and 3.
Provisions for maintenance of sampling and analysis equipment.
f.
Ins ections of Mater Control Structures A program to implement an ongoing inspection program in accordance with Regulatory Guide 1.127 (Revision 1, March 1978) for the main and auxiliary dams, the auxiliary separating dike, the emergency service water intake and discharge
- channels, and the auxiliary reservoir channel.
The program shall include the following:
2.
The provisions of Regulatory Guide 1.127, Revision 1, to be implemented as a part of plant startup operations.
Subsequent inspections at yearly intervals for at least the next 3 years.
If adverse conditions are not reveafed by these inspections, inspection at 5-year intervals will be performed.
g.
Turbine Rotor Ins ection A program to implement an ongoing inspection of the low pressure turbine rotor.
The program shall be based upon:
2.
Vendor recommendations for low pressure turbine rotor inspection intervals and procedural guidelines, and
'sing vendor methodology to recalculate the inspection interval if cracking in -the rotor is ever found.
SHEARON HARRIS " UNIT 1 6-19
INSTRUMENTATION 3/4. 3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.
APPICABILITY:
MODES 1, 2", and 3*.
ACTION:
With one throttle valve or one governor valve per high pressure turbine steam line inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam line(s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.
SURVEILLANCE RE UIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.
4.3.4.2 The above required Turbine Overspeed Protection System shall be demonstrated OPERABLE:
a.
At least once per 31 days by direct observation of the movement of each of the following valves through at least one complete cycle from the running position:
b.
l.
2.
3.
4.
Four high pressure turbine throttle valves, Four high pressure turbine governor valves, Four low pressure turbine reheat stop valves, and Four low pressure turbine reheat intercept valves.
At least once per l8 months by performance of a CHANNEL CALIBRATION on the Turbine Overspeed Protection
- Systems, aQ C.
At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of valve seats,
- disks, and stems and verifying no unacceptable flaws or excessive corrosion.
If unacceptable flaws or excessive corrosion are found, all other valves of that type shall be inspected.
- Not applicable in MODE 2 or 3 with all main steam isolation valves and bypass valves in the closed position and all other steam flow paths to the turbine isol ated.
SHEARON HARRIS - UNIT 1 3/4 3-93
ADMINISTRATIVE CONTROLS UNIT STAFF UALIFICATIONS (Continued 1.8-11 (Am.20), 1.8-12 (Am.17), and 1.8-13 (Am.17), for comparable positions, except for the Manager-Environmental and Radiation Control who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.. The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifica-tions of the supplemental requirements specified in Sections A and C of Enclo-sure 1 of the March 28, 1980, NRC letter to all licensees.
- 6. 4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Director-Harris Training Unit and shall meet or exceed the requirements and recommendations of the September 1979 draft of ANS 3. 1, with the exceptions and alternatives noted on FSAR pages 1.8-8 (Am.20), 1.8-9 (Am.17), 1.8-10 (Am.22), 1.8-11 (Am.20), 1.8-12 (Am.17), and 1.8-13 (Am.17), and Appendix A of 10 CFR Part 55 and the supplemental require-ments specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.
6.5 REVIEW AND AUDIT 6.5.1 SAFETY AND TECHNICAL REVIEWS 6.5. 1. 1 General Pro ram Control 6.5.1.1.1 A safety and a technical evaluation shall be prepared for each of the following:
a.
All procedures and programs required by Specification 6.8, other procedures that affect nuclear safety, and changes thereto; b.
All proposed tests and experiments that are not described in the Final Safety Analysis Report; and c.
All proposed changes or modifications to plant systems or equipment that affect nuclear safety.
6.5. 1.2 Technical Evaluations 6,5.1.2.1 Technical evaluations will be performed by personnel qualified in the subject matter and will determine the technical adequacy and accuracy of the proposed activity. If interdisciplinary evaluations are required to cover the technical scope of an activity, they will. be performed.
6.5.1.2.2 Technical review personnel will be identified by the responsible Manager or his designee for a specific activity when the review process begins.
6.5. 1.3 uglified Safet Reviewers 6.5. 1.3.1 The Plant General Manager shall designate those individuals who will be responsible for performing safety reviews described in Specification 6. 5. l. 4.
SHEARON HARRIS " UNIT 1 6-7