ML20032B194
| ML20032B194 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 10/27/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20032B193 | List: |
| References | |
| TAC-46812, NUDOCS 8111050205 | |
| Download: ML20032B194 (4) | |
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SAFETY EVALUATION BY THE OFFf[jfNUCLEARREACTORREGULATION RD.ATD TO AMENDMENT NO. 7 TO LICENSE NPF-9
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DUKE POWER COMPANY INTRONCTION 4
By letter dated August 12, 1981, the licensee requested certain revisions to the-McGuire Nuclear Station Unit i Technical Specifications, Appendix A, to License HPF-9. These revisions are:
1.
Revised setpoints and surveillance requirements to selected
' Engineered Safety Features Actuation System instrumentation.
4 2.
Correction to the measurement range of the Unit Vent Hoble Gas Effluent Monitor.
1 3.
Revised surveillance rer;uirenents for certain fire detection l
instrumentation.
4.
Revised surveillance requirements for hydrogen nonitort.
5.
Revision to listings of hydraulic and mechanical snubbers.
6.
Revised response time and test current value for a circuit j
breaker.
7.
Revised surveillance requirements fee monitoring Chemical l
Treatment Pond radionuclide inventory.
F 8.
Clarification to Special Test Program exceptions.
In addition the ifcensee noted a printing error on pages 6-12 and 6-13.
EVALUATION The McGuire Nuclear Station utilizes the standard Westinghouse-PWR Technical Spec-ifications which have been developed to reflect the McGuire design. The following discussion refers to~ the revisions surr.arized above.
i 1.
The. intent of the technical Specification requirement for RWST low level at Westinghouse plants is to insure that automatic, switchover t
to recirculation will be initiated when the low level setpoint is t
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reached. The current Technical Specification setpoint of 2.120 inches initiates a status alarm provided to alert the operator of a specific plant condition so that manual actions e-v be initiated if deternined to be necessary. Refer to item 10(a) in Table 3.3-3, 3.3-4 and 3.3-5.
The proposed setpoint of 2.90 inches corresponds to the point where automatic switchover occurs.
l and thus is the setpoint for which a Technical Specification requirement is appropriate.
i Automatic switchover to r'ecirculation at McGuire Unit I should occur with a mininum of 73,431 usable gallons of RWST volume i
remaining. This corresponds to a setting of 80 inches which we find to be acceptable. The licensee has stated that the pro-posed setpoint of 2.90 inches includes sufficient margin (10 inches) to account for the effects of instrument drift and instru-ment inaccuracies. Based on our review and discussion with the licensee, we conclude that the revision 'is acceptable.
NOTE: That portion of the licensee's request regarding item 7(f) of Table 3.3-3, Auxiliary Feedwater Suction Pressure. was addressed in Amendment Ho, 3 to llPF-9, L
August 28, 1981.
l 2.
As a result of a Tl11 Action Plan requirement the ringe of thgnoble gas effluent monitor on the unit vent was extended to 104 Irrad/hr.
An editorial oversight resulted in entering an incorrect measurement range in Table 3.3-6.
This oversight has been corrected.
3.
The proposed change to the fire detection instninentation specifica-tion 4.3.3.7.1 is to revise the surveillance requirement for fixed 4
tenerature/ rate-of-rin fire d6tectors. The surveillance require-
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ment would retain the sane test procedure and frequency contained in the standard Technical Specifications. However, the number of detec-tors would be based on a sample because the surveillance test require-ment is a destructive test. Strict compliance to the standard Tech-nical Specifications would require replacement of all of the fire detectors affected every six months.
l The licensee's request for a fire detection system surveillance change is based on 'the fixed temperature / rate-of-rise detectors being destroyed as a resuit of the surveillance test. The proposed change incorporates a sanplino procedure wherein two non-restorable detectors are selected out of every hundred or fraction thereof, and removed every five years for testing at an independent laboratory.
If a failure does occur, then j
two additional deteci..s are removed for testing. This surveillance i
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' l procedure is consistent with the specifications in the National Fire Protection Association (NFPA) Code 72E, " Standard On Automatic Fire Detectors."
Based on our review of the proposed change and of the NFPA Standard 1
No 72E we ctinclude the survei1%nce change is acceptable.
4.
The intent of the Technical Specification surveilhnce requirement
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j for hydrogen monitors (4.6.4.1) is to assure operab*1ity of the j
i monitor. A channel calibration using a sample gas demonstrates the required operability. The proposed revision provides clarification involving only a change in specific details of the channel calibra-tion.
Based on our review, we conclude that the revision is acceptable.
5.
The proposed review consists of correction of typographical errors, j
addition or deletion of snubbers and in general updating tabular information in Table 3.7-4a and 4b.
Based on our review and requirment that the technical specification conform with the as-installed plant equipment, we conclude that the revision is acceptable.
6.
The proposed review consists of corrections in Table 3.8-1 to reflect the as-installed KRA-22 primary breaker.
Based on our review and requirement that the technical specification j
conform with the as-installed plant equipment, we conclude that the revision is acceptable.
7.
The proposed revision to surveillance specification 4.11.1.5 consists of editing and clarification of sampling and analysis methodolgy. The revision does not involve a change to the maximum amount or type of radioactivity permitted in the Chemical Treatment Pond.
Based on our review we conclude that the revision is acceptable.
8.
The licensee notes that the special test numbers appearing in speci-fication 7.0 do not reflect the Safety Evaluation Report Supplement No. 4 but rather a more recent October 10, 1981 document. This is an editorial and clarification change and we find it acceptable.
As a result of an administration error, pages 6-12 and 6-13 were issued containing the same sections with different requirements. Pages 6-12 and 6-13 are reissued to correct this error.
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. EHVIR0.NMEllTAL C0tJSIDERAT10ll We have determined that the acendment does not authorize a change in effluent types or total amounts nor an increase in power icvel and will not result in an/ signifi-cant environrental inpact. Having made this determination, we have further concluded that the amer.dnent involves an action which is insignificant from the standpoint of environmental impact and, pursaant to 10 CFR Section 51.S(d)(4), tnat an environrental inpact statement or negative declaration and environmental inpact appraisal need not be prepared in connection with the issuance of this amendment.
C0liCLUS10tl We have concluded, based on the consideration discussed above, that: (1) because the anendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the anendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be con-ducted in conpliance with the Comission's regulations and the issuance of this amend-ment will not be inimical to the comon defense and security or to the health and safety of the public.
Date: October 27, 1981 omce >
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