ML19031A506
| ML19031A506 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/15/1976 |
| From: | Mittl R Public Service Electric & Gas Co |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19031A506 (7) | |
Text
1-"-*
OPS~G*
Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/622-7000 March 15 1 1976
~~~
Director of Nuclear Reactor Regulation "f~t !if/
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ATTENTION:
Mr. B. J. Youngblood, Chief s*)'
ii[.ilj~1 tp,
'{v Environmental Projects
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B:a.r,i.c. No. 2
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Division of Reactor Licensing\\."-\\
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- U. S. Nuclear Regulatory Commission
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Gentlemen:
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PROPOSED ENVIRONMENTAL TECHNICAL SPECIFICATION f~T~*
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SALEM NUCLEAR GENERATING STtT~ON
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- DOCKET NOS. 50-272 AND @-3_l~
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We have reviewed the "proof and review" copy of the s~;+*~**'--~*- >:'::;:;'.)!
Environmental Technical Specification (ETS) transmitted""'*to ::U'.s~%>'
on January 12, 1976.
Attached are our comments and suggested changes to the proposed ETS.
Many of these comments have been discussed verbally with your staff and we trust that our comments will be incorporated in the final version of the ETS.
We also wish to propose that implementation of the required impingement (Section 3.1.2.2) and entrainment (Section 3.1.2.3) studies take place only after the license application thermal rating of 3350 MWt (Unit No. 1) is achieved.
We propose that specifications be changed to require that both studies be initiated within 10 days after full power operation of the Unit No. 1 license application thermal rating is reached.
Limitation of the minimum one year required studies at low thermal power levels would not allow for factoring in the complete impact of the thermal plume on the impingement and entrainment studies.
Futhermore, the last paragraph of the specification for impingement studies implies that data should be analyzed only after full power operation is achieved.
The concept of implementing the impingement and entrainment studies at a defined reactor power level has been discussed with your staff and we understand that this proposal is agreeable, in principle, to NRC.
The Energy People
Dir. of Nuc. Reactor Regulation 3-15-76 We also propose that the following paragraph, similar to a paragraph in the specification for impingement studies, be added to the specification for entrainment studies.
"After one year of full power operation of Unit 1, the entrainment data should be analyzed.
Suggested changes in sampling frequency shall be submitted for review and approval by the staff prior to implementation".
The above change is recommended to provide for a consistent approach on the entrainment and impingement studies.
If you wish* further clarification on the ETS or our comments, please contact Mr. R. P. Douglas of our staff.
Very truly yours, r~~-
R. L. Mittl General Manager - Projects Engineering and Construction Department
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PAGE NO.
iii iii iii l.l-4 l.l-5 l.l-5 2.l-l 2.l-3 2.l-5 2.2-3 2.3-22 e
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CORRECTIONS AND COMMENTS
~i~*j:-.,.. 1.*i, 1.\\',:**~:::_~~.c'1 PROPOSED ENVIRONMENTAL TECHNICAL SPEC IFIGATrONs*------
SALEM NUCLEAR GENERATING STATION COMMENT Delete Table No.
3.2-2 Re-number Table No.
3.2-3 to read Table No. 3.2-2 Re-number page 3.2-lO
- to read 3.2-8 Delete Item 22 Radiological Review Point Re-number Item 24 to read Item 23 Re-number Item 25 to read Item 24 Delete the work shell in the fourth and sixth sentences under monitoring requirement Delete the word shell in the fourth and sixth sentences under monitoring requirement Delete the word shell in the fifth sentence under monitoring requirement See attach~d suggested rewrite of page 2.2~3 See attached revised version of Table 2.3-4 No longer referenced in the tex*t.
Re-numbering is necessary since Table 3.2-2 is deleted.
Re-numbering is necessary since Table 3.2-2 is deleted.
No longer referenced in the text.
(ditto)
(ditto)
Each condenser shell has a single inlet or each condenser has two shells.
(ditto)
- (ditto)
The free clorine residual is not monitored at the location of the final heat exchanger.
As *indicated in the Salem FSAR, a. common radiation monitoring system for the plant vent and containment is used.
PAGE NO.
3.2-5 3.2-8 3.2-9 3.2-9a 3.2-lO 3.2-ll Fig. 3.2-1 5.6-5 5.6-9
~ CORRECTIONS AND COMMEN~
PROPOSED ENVIRONMENTAL TECHNICAL SPECIFICATIONS SALEM NUCLEAR GENERATING STATION COMMENT Delete silver zeolite and replace with TEDA impregnated charcoal Delete *** and footnote ***
~elete Table 3.2-2 Delete Table 3.2-2 Delete Table 3.2-2 Re-number page 3.2-10 to read 3.2-8 Re-number page 3.2-11 to read 3.2-9 Add location 281 Delete location 181 Change 3.8 picocuries per liter to 4.8 picocuries per liter in Paragraph 2 See attached revised
. version of Table 5.6-1 REASON We do not plan to use silver zeolite for the operational program.
No longer mentioned in text.
(ditto)
(ditto)
Necessary because of deletions above.
(ditto)
Monitoring Station 181 has been relocated to 2Sl.
Typographical error.
Lower Limit of Detection (LLD) should be changed to Minimum Detec*tion Level (MDL) to be consistant with the text.
NCA/EAL/RPD:mj 3-12-76 2 -
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- 2.2.2 however, to maintain the free chlorine residual discharged to the river at 0.1 mg/liter or less.
The circulating water will be chlorinated by controlled injection of sodium hypochlorite into the intake water to the condensers.
Three of
. the twelve intakes are chlorinated at a time as a group.
The period of chlorination will be no greater than 30 minutes and will be done 3 times per day.
The rate of sodium hypochlorite addition is controlled. to maintain
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a 1.0 _mg/lit.er free chlorine residual or less at the condenser outlet.
The discharge is diluted with.unchlorinated water and the free chlorine residual of the discharge to the riv~r will therefore be less than 0.1 mg/liter.
The service water system will be chlorinated at a frequency not to exceed I
3 times a day for periods of no greater than 30 minutes, and not at the same time as the Circulating Water System. It will be determined that the free clorine residual will be l.Omg/liter or less at the outlet of the I
final heat exchanger.
Consequently the concentration at the discharge to the river will.be less than O.lmg/liter.
SUSPENDED SOLIDS
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. Objective:
To insure that suspended solids released from Non-Radioactive Chemical Waste Disposal System ara controlled and will not have an adv*erse effect on the natural aquatic environment of the receiving waters.
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TABLE 2.3-4
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SALCM STATION GASEOUS WASTE SYSTEM LOCATION OF PROCESS ANO EFFLUENT MONITOns M~D SJ\\MPLEns,R~OUIREO ov TECHNICAL SPECIFICATIONS Groh Radfat1on Auto Conttol lo Continuous S;1mp~o Monitor.
Proccu Strcom or Rclcoso Poln\\
Alann lsolilti_,n V<ilv1:
St;1t1on Nol.lo G.:n Waste Gas Decay Tanks x
X*
Condenser Air Removal System x
x x
x Phnt Ven~
x xb x
x Building Ventilotion Systems Reactor Containment Building (whenever xd x
there is flow) x x
x Auxiliary Building and Radwaste Areaa Xe x
fuel Handling & Storage Building0
. Xe x
Turbine Gland Seal Condenser a
.Xe x
Waste Gas Discharge l1ne x
x x*
aSince these process streams or building ventilation systems are routed to the plant vent, the need for a continuous monitor at the individual discharge point to the main exhaust duct is eliminated. One continuous monitor at the final release point is sufficient.
b.
1 Continuous y monitored.
Also includes continuous iodine, noble gas and particulate monitors which are in.
service during waste gas decay tank releases* and.containment.purging operations.
c Grab sample stations from which monthly gas samples (Table 2.3-2) are to be taken. Also, grab samples should be. taken and measured to determine.the process stream or building ventilation system source whenever an unexplained increase is indicated by the plant vent sampler-monitors.
dTnsludu continuoye noble aas monitor which monitor this locat;ion at all times other than waste gas decay tank Mca~vte,...ent I
Particulato x
x
- x x
x x
x x
x x
x x
x x
H*J Alp~11 x
x x
- x*
x
- x x
x x
x x.
x e
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TABLE 5.6-1
!!.'VtRO~~'TAL P.An!OLOCICAL MONITO!tNC PROGRAM SL~.ARY Name of Facility ----------- Docket No. -----
Location of "Facility Reporting Period -----
Medium or Pathway Sampled (Unit of Measurement)
Air Particulates (pCi/e13)
.Ftab pCi/kg (dry.~ight)
Analysis and Total Nuciber of Analyses Performed I!
416 y
32 137Ca 140 lla
. 89Sr 40 90Sr 40 y
B 137~11 1J4Ce Minimum Detectable All Level.*
(MDL) !./
0.003.
0.003 0.003 0.002 0.0003..
80 so*
(County. State)
Indicator Location9 Lo-::ction with llighest Annual Xean Me3n b/
Name Mean b/
Range-y Distance and Direction Range-k/
0.08 (200/312)
Middletown 0.10 (5/52)
(0.05-2.0) 5 miles 340*
(0.08 -: 2.0) o.os (4/24)
Smithville 0.08 (2/4)
(0.03-0~13) 2.S miles 160*
(0.03 - 0.13) 0.03 (2/24)
Podunk 0.05 (2/4)
(O. 01-0. 08) 4.0 miles 2?0.
(0.01 - 0.08)
!/ Minimum Detect~ble Level (MDL) is defined as :Jb where db is defined ae the standard deviation of the background count.
b/ Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses.
sJ Nonroutine reported measurements are defined in *sec.tion 5.6.2b.
!1J Noter The example data are provided for illustrative purposes only.
Control Locations Mean b/
Rnnge-~/
0.08 (8/104)
(0.05-1.40)
MDL 0,02 (1/8)
MDL MDL 90 (1/4)
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- 1-.::::';ier of t\\onroutine Reported Keasure::ients 1
4 1
0 0
0 0