ML20083P481
| ML20083P481 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/28/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20083P472 | List: |
| References | |
| NUDOCS 8404200026 | |
| Download: ML20083P481 (3) | |
Text
.
- po* Q*Guq'o, UNITED STATES
'E " -/ t NUCLEAR REGULATORY COMMISSION WASHINGTON, D C. 20555
/
- SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENTS NOS. 96 AND 98 TO FACILITY OPERATING LICENSES NOS. DPR-44 AND DPR-56 PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION, UNITS NOS. 2 AND 3 DOCKETS NOS. 50-277 AND 50-278 INTRODUCTION By letter dated Farch 11, 1983, the Philadelphia Electric Company (PECO or the licensee), made application to amend the Technical Specifications (TSs) for the Peach Bottom Atomic Power Station, Units Nos. 2 and 3, to permit a revision of the definition of " Primary Containment Integrity",
deletions of obsolete references, correction of an error in reference to two smoke detectors, and revisions of the requirements for administrative control of high radiation area access keys.
1 EVALUATION The licensee requested in its March 11, 1983, submittal that their current Technical Specifications be amended to incorporate four changes.
The first change would modify the definition of " Primary Containment Integrity" to permit satisfying the condition of primary containment penetration closure by one of two conditions: closure by an operable automatic containment isolation valve system or closure by at least one manual valve, blind flance, or deactivated automatic volve secured in its closed position. The current TS definition reouires that both conditions be satisfied. However, a Limiting Condition for Operation in Section 3.7.D.2 of the licensee's Peach Bottom Technical Specifications permits the use of manual isolation valves secured in the closed position when automatic isolation valves are inoperable or cannot be shown to be operable. The proposed revision would revise the definition to make it consistent with this current Limiting Condition for Operation. The proposed definition for " Primary Cnntainment Integrity" closely follows the Standard Technical Specifications for Boiling Water Reactors (NUREG-0123, Rev. 3) by. permitting two means to satisfy the closure requirement for primary containment penetrations required to be closed during accident conditions.
Therefore, we conclude that the above revision to Section 1.0 (Definitions) of the Peach Bottom TSs is acceptable.
8404200026 840328 PDR ADOCM 05000277 PDR
. The second proposed change involves deletion of an entry in Table 3.2.B pertaining to modifications to the Low Pressure Coolant Injection (LPCI) Pump Start Timers which have been completed. Since these LPCI Pump Start Timer modifications have been completed, references in the " Remarks" column of Table 3.2.B to the replaced timers are now obsolete. Therefore, we conclude that deletion of this oosolete entry is acceptable.
The third requested change involves deletion of references to two smoke detectors from Table 3.14.C.1.
The licensee indicated that as a result of a field survey and reevaluation conducted during its 10 CFR 50, Appendix R (Fire Protection Program) review, it was determined that the necessary Appendix R safe shutdown equipment was physically located in an area already protected by a smoke detection system. Therefore, these smoke detectors were deleted from the licensee's final design of its smoke detectica system and subsequently removed from service. However, the final design was not reflected in the licensee's application for amendment dated Febiuary 18, 1982. This amendment request was subsequently approved by the Commission with these two detectors added to Table 3.14.C.1.
We conclude that the reauested deletion of references in Table 3.14.C.1 to smoke detectnrs S22A and S180 is acceptable because these detectors, even if in service, do not protect areas containing safe shutdown components or safety-related systems or components as specified in 10 CFR 50, Appendix R, and therefore are not required.
However, we wish to point out that we have not completed our final review and inspection of the licensee's Appendix R program.
Subseouent staff conclusions may require additional revisions to the licensee's Technical Specifications, including addition and/or deletion of smoke detectors.
Finally, the fourth proposed change extends the administrative control of all keys necessary to control access to high radiation areas from the Shif t Super-intendent and Shif t Supervisor to the Senior Health Physicist. This transfer of control and authority over high radiation areas to the Senior-Health Physicist provides better overall control of access to high radiation areas because this individual has a better overall knowledge and current l
status of all radiation levels throughout the plant. This change is in accordance with the Boiling Water Reactor Standard Technical Specifications (NUREG-0123, Rev. 3, Section 6.12.2) concerning high radiation areas. There-fore, based upon the above, we conclude that this change is acceptable.
ENVIRONMENTAL CONSIDERATIONS We have determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we l
have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 951.5(d)(4), that an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of these amendments.
~,..
1
, C0tlCLUSION i
We have 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, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will ~ not be inimical to the common defense and security or to the health and safety of the public.
Dated:
flarch 28, 1984 i
The following NRC personnel have contributed to this Safety Evaluation:
Gerry Gears.
i t
i j
4 m
b 1
t i
1 i
~.
_