ML18004A450
| ML18004A450 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/06/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NLS-86-270, NUDOCS 8608130267 | |
| Download: ML18004A450 (6) | |
Text
REQUL RY INFORi'1ATION DISTRIBUT SYSTEN (RIDS>
ACCESSION NBR: 8608130267 DOC. DATE: 86/08/06 NOTARIZED: NO, DOCHET 0 FACIL: 50-400 Shearon Harris Nuclear Power Plant>
Unit i. Carolina 05000400 AUTH. NANE AUTHOR AFFILIATION ZINNERI'JANE S. R.
Carolina Power Zc Light Co.
REC IP. NANE RECIPIENT AFFILIATION DENTONp H. R.
Office of Nuclear Reactor Regulationi Director <post 851125
SUBJECT:
Forwards addi info re fire protections clarifying 840716 response to Question 410. 25 5 850926 response to NRC Guestion 410. 53a on associated circuitsi per 860714 request.
DISTR IBUT'ION CODE:
A006D COPIES RECEIVED: LTR ENCL SI ZE:
TITLE: OR/Licensing Submittal: Fire Protection NOTES:Application for permit renewal filed.
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l9BS SERIAL: NLS-86-270 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 FIRE PROTECTION - ADDITIONALINFORMATION
Dear Mr. Denton:
Following conversations with members of your staff on 3uly 10, 1986, Carolina Power R Light Company was requested to clarify our responses to NRC Question 010.25 dated 3uly 16, 1980 (NLS-81-297) and NRC Question 010.53a dated September 26, 1985 (NLS-85-300).
Attachment 1 provides our revised responses.
Should you have any questions concerning this letter, please contact Mr. Patrick P. Carier at (919) 836-8165.
Yours very truly, PPC/vaw (0019PPC)
Attachment cc:
Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-RII)
Wake County Public Library S.. Zim erman ger Nuclear Licensing Section Sb080b pgR Bb p,gOcy, 0 pop 08>~0Pb7 o50004 0
F 411 Fayettevitte Street o P. O. 8ox 1551 o Raleigh, N. C. 27602 yb I(l
Attachment 1 to NLS-86-270
NRC estion OI0.25 From a comparison of the list entitled "Systems Required for Plant Shutdown in Case of a Fire," in the applicant's submittal with the list contained in Table 7.0.1-2 of the FSAR, entitled "Instrumentation and Control, AuxiliaryControl Panel (ACP)," it appears that some of the systems required for safe shutdown willnot be controlled from the ACP in the event of a fire in the Control Room. Therefore, show that sufficient personnel are available to safely shut the plant down in the event of all fires which require operation from the ACP. Provide summaries of procedures to confirm the number of personnel required.
In addition, discuss by what measures the people at the ACP willcommunicate with those people performing necessary functions at other locations throughout the plant.
~CPRL it In the event of a fire requiring the evacuation of the Control Room, the Auxiliary Control Room willbecome the Safe Shutdown Control Center.
The number of personnel necessary to safely shut down the plant from the ACP is described in the Shearon Harris operating procedure entitled "Safe Shutdown in Case of Fire or Control Room Inaccessibility." This procedure states that five persons are needed to coordinate the shutdown effort. Adequate staffing is specified by the Shearon Harris Technical Specifications, Table 6.2-1, "Minimum Shift Crew Composition."
During a fire emergency, communications willbe provided by the use of sound powered telephones, portable radios, and normally installed plant PA and phone systems.
(4019PPC/crs)
~d I
NRC estion 010.53a Your response to Question 010.28 regarding associated circuits appears to be ambiguous, in part.
In order to clarify your response, please provide the following information:
aR With regard to associated circuits having a common power source, you stated that power feeder(s) from buses, power centers and motor control centers are provided with breakers or fuses to isolate fire-induced electrical shorts so as to prevent tripping of or damage to the power source.
Show that you have considered suitability of the interrupting devices in accordance with the criteria of Section Il.b.2 of the letter forwarded to you on October 18, 1983 (also attached herein as Appendix B pages 0 and 5).
~Ri RR
- Section 8.3.1.1.2.11 of the Shearon Harris FSAR provides a description of the electric circuit protection system provided. Allelectrical equipment is designed and manufactured to applicable ANSI, NEMA, IEEE, and other industry standards.
With regard to associated circuits, a breaker coordination study has been performed for the Shearon Harris Nuclear Plant and periodic testing shall be performed to demonstrate that the scheme remains within the design criteria. The plant design does not include 6.9KV common power source safe shutdown associated circuits. The plant design, however, does include 080V and 120V common power source safe shutdown associated circuits.
Periodic testing willbe performed for these breakers as follows: Every 18 months 10 percent of each class of breaker (i.e., 080V switchgear, 080V molded case, 120V molded case) willbe tested.
Safe Shutdown 6.9KV breakers willbe tested to ensure the overall coordination is maintained and willbe tested at the frequency and percentage as stated above.
The testing for 080V switchgear willconsist of verification of the protective relay setpoints.
The testing of molded case circuit breakers willconsist of verification that the breaker drift is within the specifications allowed by the manufacturer.
For each circuit breaker found which fails to meet the acceptance criteria specified above, an additional 10 percent of that class of breaker willbe tested until no further failures are encountered or all of the circuit breakers in the class covered by the subject study are tested.
(4019PPC/crs
)