ML20141D634
| ML20141D634 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/24/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20141D638 | List: |
| References | |
| NUDOCS 9706270289 | |
| Download: ML20141D634 (10) | |
Text
, ps@h
[
el UNITED STATES s
j NUCLEAR REGULATORY COMMISSION
~{
%,. ;... /g WASHINGTON, D.C. 206 6 0001 l
g PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 197 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated April 11, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
/
9706270289 970624 PDR ADOCK 05000272 P
PDR a
\\
l.
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.197, are hereby incorporated in the i
license. The licensee shall operate the facility in accordance with the Technical Specifications.
J 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i 64 J
. Stolz, Direc P ject Directorate -
Divisjon of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of Issuance:
June 24, 1997 t
t 6
4
ATTACHMENT TO LICENSE AMENDMENT NO.197 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 6-11a 3/4 6-11a B 3/4 6-3 B 3/4 6-3 t
/
\\
._..._._m..
.__._.m.._
.-_. _. _._- =>._ _ _..._.._ _ _ _ _ _
i 4
CONTAINMENT SYSTEMS 1
SURVEILLANCE REQUIREMENTS (Continued) i At least once per 31 days by:
a.
aj-1.
Starting (unless already operating) each fan from the control room in low speed.
{
2.
Verifying that each fan operates for at least 15 minutes in low 7
speed.
l 1
3.
Verifying a cooling water flow rate of greater than or equal to 2550 gpm to each cooler.-
l j
b.
At least once per 18 months by verifying that on a safety injection test signals i.s 1.
Each fan starts automatically in low speed.
}
l 2.
The automatic valves and da,mpers actuate to their correct positions and that the cooling water flow rate to each cooler l
is greater than or equal to 2550 gpm.
1 l
i f
1 4
l 4
i t
SALEM - UNIT 1 3/4 6-11a Amendment No. 197 a
N i
CONTAINMENT SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM i
The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.
3/4.6.2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the spray additive system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA. The limits on NaOH minimum volume and concentration, ensure that 1) the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) corrosion ef fects on componente within containment are minindzed. The contained water volume limit includes an allowance for water not usable because of tank discharge line location o's other physical characteristics.
These assumptions are consistent with the iodine removal efficiency assumed in the accident analyses.
3/4.6.2.3 CONTAINMENT COOLING SYSTEM l
The OPERABILITY of the containment cooling system ensures that adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions.
3/4.6.3 CONTAINMENT' ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containmentatmosphe(ewillbe. isolated from the outside environment in the event of a release of radicactive material to the containment atmosphere,or pressurization of the containment. Containment isolation within the time.
limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations: (1) stationing a dedicated individual, who is in constant communication with the control room, at the valve controls, (2) instructing this individual to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside th'9 containment.
/
. SALEM - UNIT 1 B 3/4 6-3 Amendment No.197
~
$*%,k UNITED STATES p
NUCLEAR REGULATORY COMMISSION
'f WASHINGTON, D.C. 20566-0001 s...../
PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.180 License No. DPR-75 1.
The Nuclear Regulatory Commission (tfie Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated April 11, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's
' rules. and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; I
C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health ahd safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.- Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
/
_ _. _ _ ~ _. _.
._y
\\
i
. (2) Technical Specifications and Environmental Protection Plan The Tebhnical Specifications contained in Appendices A and B, as revised through Amendment No.180, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION I
n F. Stolz, Dire r
2 oject Directorate 1-2 Divisjon of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation 4
Attachment:
Changes to the Technical Specifications j
Date of Issuance:
June 24, 1997 4
I i
/
ATTACHMENT TO LICENSE AMENDMENT N0.180 FACILITY OPERATING LICENSE NO. DPR-75 4
DOCKET NO. 50-311 1
Revise Appendix A as follows:
Remove Paaes Insert Paaes i
j 3/4 6-13 3/4 6-13 B 3/4 6-3 B 3/4 6-3 i
1 W
4 b
k I
5 i
4 4
a 1
1
/
I
-.. -..... -..~..
i CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l At least once per 31 days by:
a.
i 4
1.
Starting (unless already operating) each fan from the control room in low speed.
l 2.
Verifying that each fan operates for at least 15 minutes in low l
speed.
3.
Verifying a cooling water flow rate of greater than or equal to 2550 gpm to each cooler.
l b.
At least once per is months by verifying that on a safety injection test signal:
1.
Each fan starts automatically in low speed.
{
2.
The automatic valves and d,ampers actuate to their correct positions and that the cooJing water flow rate to each cooler is greater than or equal to 2550 gpm.
l t
f 4
/
/
SALEM - UNIT 2 3/4 6-13 Amendment No.180
- -. ~.... - - - -.
- -. _.... -. _. -. ~. - -
_.,. _ _. ~ - -.. _ - ~ ~ -. _ -. - ~ _. - ~ _ -
a i
CONTAINMENT SYSTEMS i
4 BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 4
j.
3/4.6.2.1 CONTAINMENT SPRAY SYSTEM t
)
The OPERABILITY of the containment spray system ensures that containment i
depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant lower containment leakage rate are 1
consistent with the assumptions used in the accident analyses.
The containment spray system and the containment cooling system are redundant to each other in providing post accident cooling of the containment atmosphere.
However, the containment spray system also provides a mechanism for removing iodine from the containment atmosphere and therefore the time l
requirements for restoring an inoperable spray system to OPERABLE status have 4
been maintained consistent with that assigned other inoperable ESF equipment.
i 3/4.6.2.2 SPRAY ADDITIVE SYSTEM
{
The OPERABILITY of the spray additive system ensures that sufficient NaOH i
is added to the containment spray in the event of a LOCA. The limits on NaOH minimum volume and concentration, ensure that 1) the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) j corrosion effects on components within containment are minimized. The i
contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
These assumptions are consistent with the iodine removal efficiency assumed in the accident analyses.
f 3 /4. 6. 2. 3 CONTAINMENT COOLING SYSTEM i
4
}
The OPERABILITY {of the containment cooling system ensures that adequate heat removal capacity is available when operated in conjunction with the, containment spray systems during post-LOCA conditions.
i
~
The containment cooling system and the containment spray system are i
redundant to each other in providing post accident cooling of the containment j
atmosphere. As a result of this redundancy in cooling capability, the allowable out'of service time requirements for the containment cooling system have been appropriately adjusted. However, the allowable out of service time requirements for the containment spray system have been maintained consistent i
I with that assigned other inoperable ESF equipment since the containment spray system also provides a mecha'nism for removing iodine from the containment
{
S atmosphere.
a 4
J u
/
SALEM - UNIT 2 B 3/4 6-3 Amendment No. N
,_