ML20070K649
| ML20070K649 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/18/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070K647 | List: |
| References | |
| NUDOCS 9407270069 | |
| Download: ML20070K649 (4) | |
Text
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SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ELATED TO AMENDMENT N0.144 TO FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT N0. 126 TO FACILITY OPERATING LICENSE NPF-17 DUKE POWER COMPANY MCGUIRE NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370
1.0 INTRODUCTION
On March 17, 1988, the NRC staff issued a Revised Safety Evaluation Report (RSER) regarding Duke Power Company's (the licensee) conformance to Regulatory Guide (R.G.) 1.97, Revision 2 for McGuire Nuclear Station, Units 1 and 2.
The staff accepted the licensee's deviation from the guidance of R.G. 1.97.
In a submittal dated February 25, 1994, the licensee documented additional deviations from the guidance in R.G. 1.97 and proposed related changes to the McGuire Nuclear Station, Units 1 and 2, Technical Specifications (TS) regarding post-accident monitoring (PAM) instrumentation in TS 3.3.3.6, and TS Tables 3.3-10 and 4.3-7.
2.0 LVALVATIDH The NRC staff has reviewed the licensee's February 25, 1994, submittal which identified deviations and TS changes with regard to the instrumentation that monitors 1) neutron flux, 2) containment hydrogen concentration, 3) diesel generator cooling water heat exchanger nuclear service water flow, 4) containment spray heat exchanger nuclear service water flow, 5) power operated relief valve (PORV) position, 6) PORV block valve position, 7) safety relief valve position, 8) unit vent high-high range noble gas concentration, 9) releases from steam generator safety relief valves or atmospheric dump valves,
- 10) high range containment atmosphere radiation,11) auxiliary feedwater flow, and 12) containment isolation valve position. Our evaluation of the above items is as follows:
1)
The licensee's neutron flux monitoring instrumentation is Category 1, but had not been previously included in the TS. The licensee has added this instrumentation to TS Tables 3.3-10 and 4.3-7.
This addition to TS Tables 3.3-10 and 4.3-7 is acceptable.
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. 2)
The licensee's containment hydrogen concentration monitoring instrumentation is Category 1, but had not been previously included in the TS.
The licensee has added this instrumentation to TS Tables 3.3-10 and 4.3-7.
This addition to TS Tables 3.3-10 and 4.3-7 is acceptable.
3)
The licensee has determined that diesel generator cooling water heat exchanger nuclear service water flow monitoring is required for performing manual actions for which no automatic actions are provided and the licensee has added this instrumentation to TS Tables 3.3-10 and 4.3-7.
The diesel generator cooling water heat exchanger nuclear service water flow monitoring instrumentation is part of the nuclear service water system which is governed by TS 3.7.4 and the Limiting Condition for Operation (LCO) 3.7.4a that allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for restoring one inoperable nuclear service water channel to operable status before the affected unit is taken out of service. The current diesel generator cooling water LC0 3.3.3.6b allows 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for restoring one inoperable flow indicator to operable status.
The licensee revised LC0 3.3.3.6b to be consistent with the requirements of LCO 3.7.4.
This revision is acceptable.
4)
The licensee has determined that containment spray heat exchanger nuclear service water flow monitoring is required for performing manual actions for which no automatic actions are provided and the licensee has added this instrumentation to TS Tables 3.3-10 and 4.3-7.
The licensee has also added PAM instrument labels on the control room nuclear service water flow instrumentation.
The containment spray heat exchanger nuclear service water flow monitoring instrumentation is part of the nuclear service water system which is governed by TS 3.7.4 and the LC0 3.7.4a that allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for restoring one inoperable nuclear service water channel to operable status before the affected unit is taken out of service.
The current containment spray LC0 3.3.3.6b allows 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for restoring one inoperable flow indicator to operable status. The licensee revised LC0 3.3.3.6b to be consistent with the requirements of LC0 3.7.4.
This revision is acceptable.
5)
PORV position indication is considered Type D, Category 2 instrumentation and is not required to be incorporated in the PAM TS.
Therefore, this instrumentation has been deleted from TS Tables 3.3-10 and 4.3-7.
This deletion is acceptable.
6)
PORV block valve position indication is considered Type D, Category 2 instrumentation and is not required to be incorporated in tha PAM TS.
Therefore, this instrumentation has been deleted from TS Tables 3.3-10 and 4.3-7.
This deletion is acceptable.
7)
Safety relief valve position indication is considered Type D, Category 2 instrumentation and is not required to be incorporated in the PAM TS.
Therefore, this instrumentation has been deleted from TS Tables 3.3-10 and 4.3-7.
This deletion is acceptable.
8).
Unit vent high-high range noble gas concentration monitoring is considered Type E, Category 2 instrumentation and is not required to be incorporated in the PAM TS. Therefore, this instrumentation has been deleted from TS Tables 3.3-10 and 4.3-7.
This deletion is acceptable.
l 9)
Monitors of releases from steam generator safety relief valves or atmospheric dump valves (steam relief) are considered Type E, Category 2 instrumentation and are not required to be incorporated in the PAM TS.
i Therefore, this instrumentation has been deleted from TS Tables 3.3-10 and 4.3-7.
This deletion is acceptable.
- 10) High range containment atmosphere radiation is Category 1.
The licensee has made editorial corrections to the instrument numbers that are called out in TS Tables 3.3-10 and 4.3-7.
This is an administrative change only and is acceptable.
11)
In the staf f's RSER, Category 3 condensate storage tank level instrumentation was found acceptable because the safety-related source for auxiliary feedwater is the nuclear service water system.
Auxiliary feedwater flow is considered Type D, Category 2 instrumentation.
Since auxiliary feedwater flow instrumentation is used to monitor the nuclear service water flow rate, the licensee has proposed that auxiliary feedwater flow remain in TS Tables 3.3-10 and 4.3-7.
The licensee also 1
will maintain the PAM labeling on the auxiliary feedwater flow instrumentation in the control room. The staff finds this instrumentation configuration acceptable.
j 12)
R.G. 1.97 recommends that Type A, B, and C instruments designated as Categories 1 and 2 be specifically identified with a common designator on the control panels so that the operator can easily discern that these instruments are intended for use under accident conditions.
The licensee has stated that they have provided each Type A, B, and C instrument-designated as Category 1 with a PAM label, except for containment isolation valve position instrumentation.
The intent of R.G.1.97 in identifying instrumentation in the control room is to provide the operator with identification of a minimum set of instrumentation to monitor during a post-accident situation. The licensee has provided operator training that includes information on the purpose of the containment isolation valve position monitoring instrumentation. This training, along with the awareness that the containment isolation valve position monitoring instrumentation should be operational post-accident, meets the intent of R.G. 1.97.
Therefore, since tha lia nsce's training provides this assurance of operator knowledge, lack of control room labeling of containment isolation valve position instrumentation is acceptable.
. Based on our review of the licensee's submittal, we conclude that the licensee has provided adequate justification for deviations from and exceptions to R.G.1.97, Revision 2, and changes in TS 3.3.3.6 and Tables 3.3-10 and 4.3-7 for the instrumentation that monitors 1) neutron flux, 2) containment hydrogen concentration, 3) diesel generator cooling water heat exchanger nuclear service water flow, 4) containment spray heat exchanger nuclear service water flow, 5) PORV position, 6) PORV block valve position, 7) safety relief valve position, 8) unit vent high-high r ange noble gas concentration, 9) releases l
i from steam generator safety relief valves or atmospheric dump valves,
- 10) high range containment atmosphere radiation,11) auxiliary feedwater flow, and 12) containment isolation valve position.
Therefore, we find the above deviations from R.G.1.97 and the changes to TS 3.3.3.6, and TS Tables 3.3-10 and 4.3-7 acceptable.
3.0 STATE CONSULTATIO_N j
In accordance with the Commission's regulations, the North Carolina State official was notified of the proposed issuance of the amendments.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements.
The NRC staff has determined that the amendments involve no significant increase in the amounts, and no i
significant change in the types, of any effluents that may be released offsite, and that there is no si occupational radiation exposure.gnificant increase in individual or cumulative The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (59 FR 17597 dated April 13,1994). Accordingly, the amendments meet the eligibility criteria 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 amendments.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
B. Marcus Date: July 18, 1994
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