ML18016A364
| ML18016A364 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/18/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML18016A361 | List: |
| References | |
| NUDOCS 9803270010 | |
| Download: ML18016A364 (4) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 IO B
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1.0 D
By letter dated April23, 1997, the Carolina Power & Light Company proposed changes to the plant Technical Specifications (TS) for the Shearon Harris Nuclear Power Plant (SHNPP). The proposed changes willamend the Surveillance Requirements in TS Items 4.3.2.1.1.a, 4.3.2.1 4.b, 4.3.2.1.6.g, 4.3.2.1.10.a, and 4.3.2.1.10.b in Table 4.3.2 of the Engineered Safety Features Actuation System Instrumentation and TS Item 4.7.3.b.3 of the Component Cooling Water System.
The changes willdelete inapplicable notes and add more specific information by incorporating the review findings of Generic Letter 96-01, "Testing of Safety Related Logic Circuits," dated January 1996.
The proposed change to TS Item 4.3.2.1.1.a, "Manual Initiation of Safety Injection," will eliminate an asterisk and its associated note. This note was added by Amendment 63, to the SHNPP license, to permit a one;time surveillance test extension for a safety injection manual switch. The licensee stated that the note was no longer applicable.
The proposed change to TS Item 4.3.2.1.4.b, "Automatic Actuation Logic and Actuation Relays for Main Steam Line Isolation," willadd a new note (Note 4) to perform the Actuation Logic Test on the Steam Line Isolation - Safety Injection Block switches.
These switches arm the Negative
. Steam Line Pressure Rate-High signal, TS Item 4.3.2.1.4.e, when used below the P-11 setpoint.
The test requires verification of proper operation ofthese switches each time they are used.
The licensee stated that the proposed test willblock the generation of a safety injection signal during depressurization.
The proposed change to TS Item 4.3.2.1.6.g, "Steam Line Differential Pressure High in Auxiliary Feedwater System," willadd quarterly testing of Slave Relays with the exception of those relays identified in Note 3. The licensee stated that the relays identified in Note 3 are tested once per 18 months rather than quarterly due to the adverse consequences of testing them while the unit is in operation.
The proposed changes to TS Item 4.3.2.1.10.a, "Pressurizer Pressure, P-11," and TS Item 4.3.2.1.10.b, "Low-LowTavg, P-12," for the Engineered Safety Features Actuation System Interlocks, willadd a monthly Actuation Logic Test and Master Relay Test of the P-11 and P-12 logic circuits. The licensee has modified Table 4.3.2 to indicate that Note 1 is applicable to the new monthly tests.
This willallow the tests to be completed every 62 days on a Staggered Test Basis. The licensee stated that even though these tests are not specified in the current SHNPP 9'803270010 9803i8 pDR moocah os000400 p
2, TS, their review of the current routine test instructions for P-11 and P-12 interlocks indicates that portions of the current routine tests meet the definitions for an actuation logic test and master relay test.
The proposed change to TS Item 4.7.3.b.3, "Surveillance Requirements to Component Cooling Water System (CCW)," willadd test requirements for the sample system heat exchanger CCW valves that are similar to the test requirements for the two isolation valves for the failed gross fuel detector.
The licensee stated that a low CCW surge tank level signal closes the two valves in the gross failed fuel detector system as well as the two valves that supply CCW to the sample system heat exchangers.
These four CCW valves also receive an automatic closure signal from the safety injection signal which is verified operable on an 18-month interval. Thus, this modification will implement the same tests for all four CCW system valves.
The licensee also stated that the proposed TS changes do not result in any physical plant changes or require existing systems to perform a different type of function than they are designed to perform. Except for the change to TS 4.7.3.b.3, all changes affect only the description of the tests and make no changes in actual operation or conduct of the tests.
3.0 In accordance with the Commission's regulations, the State of North Carolina officialwas notified of the proposed issuance of the amendment.
The State official had no comments.
40 NV N
EN A D
I The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (62 FR 33119). Accordingly, the amendment meets the eligibilitycriteria for categorical 'exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 ON Based on the staff review of the licensee's justification for the proposed TS changes, the staff concludes that the changes are consistent with the current SHNPP TS requirements and the guidance of the Westinghouse Standard TS, and are, therefore, acceptable.
Principal Contributor: Subinoy Mazumdar Date:
Nai ch 18, 1998