ML20035F008
| ML20035F008 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/16/1993 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-93149, NUDOCS 9304200169 | |
| Download: ML20035F008 (47) | |
Text
. _ -.
j
-t t
- = = = = =
2M Log
-# TXX-93149-L i
File - # 10010 l
3 Ref. # 10CFR50.71(e) i 1UELECTRIC April 16, 1993
-l William JEahill. Jr.
l Guemp lice Pressdent U. S. Nuclear Regulatory Commission i
Attn: Document Control Desk Washington, DC 20555 I
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 FSAR AMENDMENT 88 DESCRIPTION Gentlemen:
Amendment 88 to the CPSES FSAR was transmitted to you under a separate cover letter TXX-93148, dated April 16, 1993.
The attachment to this letter provides
[
~
line-by-line descriptions of the changes in Amendment 88.
FSAR pages which do not have technical changes but are included in'the amendment (because they are i
the opposite side of the sheet from a page that was changed, because the change j
shifted the existing material to another page or because only editorial changes were made on these pages) are not discussed in the attachment.
l I
As has been the TU Electric practice in past FSAR amendments, all changes
[
described in the attachment have been evaluated for relative significance (i.e., the group number 1, 2, 3 or 4 following each change justification as j
discussed in TU Electric letter TXX-88467 dated June 1,1988).
In addition, t
all changes have been reviewed under the TU Electric 10CFR50.59 process and i
found not to include any "unreviewed safety questions."
j t
Amendment 88 includes the following changes previously transmitted to the NRC
[
as advance FSAR submittals or resulted from NRC Requests for Additional Information (RAI):
t
- 1) Revision to FSAR Chapter 9. " Control Room Carpet Requirements", as f
transmitted in TXX-92637, dated December 22, 1992, in response to an i
oral NRC RAI.
l
- 2) Revision to FSAR Chapter 1. " Clarification Regarding Replacement and Testing of Charcoal", as transmitted in TXX-93036, dated January 15, 1993, in response to an NRC RAI.
l
- 3) Revision to FSAR Chapters 13 and 17. " Changes in Organizational
[
Structure", as transmitted in TXX-93102, dated February 26, 1993.
< p r r t*1"i s.
9304200169 930416 4rKiN. Olive Street LB. *I Dalle. Texas 75201
.PDR ADOCK 05000445 K
PDR t
i i
i l
TXX-93149 Page 2 of 2 Also, as described in TXX-92286 dated May 31, 1992, Amendment 88 continued the process of incorporating into the FSAR text the responses to NRC questions t
contained in FSAR volumes XV, XVI and XVII.
\\
r Sincerely, l
)
William J. Cahill, Jr.
BSD/rc Attachment l
c - Mr. J. L. Milhoan, Region IV Resident Inspectors, CPSES (2)
Mr. T. A. Bergman, NRR Hr. B. E. Holian, NRR i
1 i
l l
i 1
1 i
t
Attachment to TXX-93149 l
l April 16, 1993 l
Page 1 of 45 CPSES - FINAL SAFETY ANALYSIS REPORT (FSAR)
AMENDMENT / REVISION 88 DETAILED DESCRIPTION Prefix Page (as smended)
Group Description Table 1.6-1 4
See Sheet No(s) :16 Adds Topical Report WCAP-8776 to FSAR Table 1.6-1.
Q&R Incorporation :
This is an editorial change to ready the Q&R Section for deletion when the updated FSAR is prepared. The addition of this report to the list in Table 1.6-1 l
was inadvertently missed by previous amendments.
This WCAP was deleted as a footnote from the response to 0022.9.
Refer to the justification for Page 0&R 022-34, Change Request No. SA-92-46.1.
Change Request Number
- SA-92-46.2 Commitment Register Number :
Related SER : 6.2.4 SSER :24 6.2.4 SER/SSER Impact
- No 1A(B)-26 3
This change clarifies the periodic testing and l
replacement of charcoal utilized in the charcoal beds of the Engineered Safety Feature (ESF) Filter System.
Correction Clarifies the replacement and testing of the charcoal for ESF Systems in FSAR Amendment 87, based on the requirements of NRC.R.G. 1.52 Revision 2 and ANSI N509-1980 Adsorber beds can be used one more cycle if the test results from the last canister are acceptable and no fire, chemical fumes or toxic gases are released from the area served by this filter units. Adsorber beds will be replaced when either sample fails the test or no representative sample is available for testing, at a time when testing is required.
Change Request Number
- SA-93-16.
Commitment Register Number :
Related SER : 6.5.1 SSER :23 6.5.1 SER/SSER Impact
- No 2.4-44 4
Provides a minor clarification for the Service Water Pump description to provide consistency with design calculation and drawings.
Clarification :
Corrects the Service Water Pump description to state that each pump is designed to operate with a minimum submergence requirement of 4ft - 61n above the be11 mouth flare (El. 757ft) which will results in a minimum water elevation for pump operation of at least 761ft - 61n. The 4ft - 61n is measured from the bottom of the flare, not the impeller. This clarification is consistent with design calculation u.
J
'I Attachment to TXX-93149 April 16. 1993 Page 2 of 45 l
Prefix Page (a_s amended)
Group DescriDtion f
and drawings.
Change Request Number
- SA-92-853.
Commitment Register Numbo :
Related SER : 2.4.4 SSEk :
SER/SSER Impact
- No i
2.4-48 3
Updates analytical results of the impact upon Squaw f
Creek Reservoir due to a postulated Liquid Waste-i Rupture Accident, based on revised effluent concentration limits per the new 10CFR20.
Change Request Number
- SA-91-87.1 Commitment Register Number :
Related SER :
SSER :22 2.4.7 SER/SSER Impact
- No i
Table 2.4-21 3
See Sheet No(s) :03 Updates analytical results of the impact upon. Squaw Creek Reservoir due to a postulated Liquid Waste i
Rupture Accident.. based on revised ffluent l
concentration limits per the new 10CFR20.
Change Request Number
- SA-91-87.2 Commitment Register Number :
Related SER :
SSER :22 2.4.7 SER/SSER Impact
- No l
3.2-5 1
Revises discussion of Structures and Systems of Mixed I
Category.
I Revision Revises sentence to indicate that there is more than one Seismic Category II piping segment located in a j
non-seismic building.
l Change Request Number
- SA-93-4.1 Commitment Register Number :
Related SER : 3.2 SSER :
l SER/SSER Impact
- No l
t 3.2-12 1
Revises discussion regarding piping segments located i
in the Turbine Building which are designated Class 5 i
piping-and classified as Seismic Category II.
i l
Revision Changes discussion to indicate that there is more that one piping segment located in the Turbine Building which is designated Class 5 piping and classified as Seismic Category II..
The applicable piping segments are listed in Section 3.7B.2.8.
Also clarifies that these piping segments are analyzed for seismic qualification and unacceptable interactions with non-Category I structures / components.
Change Request Fumber
- SA-93-4.2 Commitment Register Number :
l Related SER : 3.2 SSER :
l SER/SSER Impact
_:.No i
l
.[
l Attachment to TXX-93149 April 16, 1993 j
Page 3 of 45 l
t Prefix Page l
(as amended)
Group DescriDtion Figure 3.2-1 3
Adds a new symbol for disc-less check valves.
Clarification This is an editorial change to_ provide a user friendly symbol and clarify the as-butit condition.
3 The notes for each affected valve are unchanged in meaning.
Change Request Number
- SA-92-854.1 l
Commitment Register Number :
.j Related'SER : 3.E SSER :
SER/SSER Impact
- No
-j Figure 3.6B-141 2
Add note to drawing indicating that' intermediate c
breaks for stress problem 2-79H may.be eliminated by i
seismic stress analysis.
j Clarification :
Pipe breaks were originally postulated at every.
fitting / weld for non-analyzed high energy lines-2-SB-2-072-1302-5, 8-SB-2-030-302-5 and 8-HD-2-069-302-5 in accordance with FSAR Section 3.6B and Standard Review Plan 3.6.2 requirements. These pipe segments were recently seismically analyzed (stress problems
{
SB-2-79H and SB-2-79G) with pipe break locations postulated based on stress-levels (only terminal breaks were postulated).
Several intermediate breaks which were previously postulated at every fitting / weld can therefore be eliminated. These intermediate l
break locations will be retained since no j
hardware protection'is required and th; l
engineering records for walkwdown j
results/ target evaluations of the effects of 1
these can be retained.
Change Request Number
- SA-93-3.1 l
Commitwent Register Number :
i Related SER :
SSER :
SER/SSER Impact
- No Figure 3.6B-141 2
Add stress problem 2-79H to drawing showing the boundaries of this problem.
Clarification :
Shows which pipe sections were governed by the.
applicable problem number.
Change Request Number
- .SA-93-3.3 Commitment Register Number :
Related SER :
SSER :
SER/SSER Impact
- No Figure 3.6B-142 2
Adds note to drawing indicating that intermediate breaks.for stress problem 2-79G may be eliminated by seismic stress analysis.
Clarification
~ _.
Attachment to TXX-93149
[
April 16, 1993 Page 4 of 45 i
Prefix Page (as amended)
Group Description See justification for change to Figure 3.6B-141 j
(Change Request No. SA-93-3.1).
Change Request Number
- SA-93-3.2 Commitment Register Number :
Related SER :
SSER :
i SER/SSER Impact
- No i
Figure 3.6B-142 2
Adds stress problem 2-79G to drawing showing the l
boundaries of the problem.
i Clarification :
Shows which pipe sections were governed by the applicable problem numbers.
Change Request Number
- SA-93-3.4 l
l Commitment Register Number :
i Related SER :
SSER :
i SER/SSER Impact
- No
}
s Figure 3.6B-184 2
Delete break 006T-C from downstream side of valve 2LCV-459.
i Correction l
A terminal break, break no. 006T was previously.
l
. postulated at the boundary of stress problems 2-41A l
and 2-41L on Figure 3.6B-184.
The effects of this break were determined to be undesirable due to potential damage to two CVCS isolation valves.
A piping analysis has been performed combining these
[
two stress problems, thereby eliminating the need of j
postulating a terminal break at the boundary.
Change Request Number
- SA-93-3.5 i
Commitment Register Number :
Related SER :
SSER :
i SER/SSER Impact
- No i
3.7B-42 1
Revises discussion of Interaction of Non-Category I f
Structures with Sei:mic Categor/ I Sturetures.
Revision 1
Adds the specific exception concerning the Unit 2 Heater Drain line piping in the Turbine Building.
The Heater Drain piping has been reclassified as Class 5 and redesignated as Seismic Category II to allow the placement of a seismic /non-seismic boundary anchor of a seismically qualified high energy Heater Drains pipe line thirteen inches inside the Turbine Building.. Analyses have been performed that demonstrate that the non-Category I structures and components within the Turbine Building will not unacceptably interact with Heater Drain piping during and after a seismic event.
Change Request Number
.: SA-93-4.3 Commitment Register Number :
Related SER : 3.7 SSER :
SER/SSER Impact
- No
t 1
t j
Attachment to TXX-93149 1
April 16, 1993 i
Page 5 of 45 l
Prefix Page (ai amended)
Group Etscription.
j
)
6.2-113 4
Inserts the last paragraph from the response to i
0022.9 into FSAR Section 6.2.5.3.1.
i 0&R Incorporation :
j This is an editorial change to ready the Q&R Section for deletion when the updated FSAR is prepared.
a Refer to the justification for Page Q&R 022-34 Change Request No. SA-93-46.1.
Change Request Number
- SA-92-46.3 l
Commitment Register Number :
i Related SER : 6.2.4 SSER :24 6.2.4
}
SER/SSER Impact
- No
]
1 6.2-142 3
See Sheet No(s) :143 The acceptance criteria to perform Containment Reduced Pressure Test during preoperational, periodic and supplemental tests has been removed from FSAR Section 6.2.6.1. Sub-paragraphs 1 through 3.
Revision The acceptance criteria was removed from the CPSES Combined Unit Technical Specifications Amendment 14.
i This change is made to FSAR Section 6.2.6.1 to make
_3 1
the FSAR text consistent with the approved Technical Specifications.
10CFR50, Appendix J. Section i
III.A.4.a allows a Type A Containment Integrated Leakage Rate Test (ILRT) to be performed at a reduced pressure Pt. not less than 0.50 Pa, if a i
correlation between the reduced pressure ILRT test and the Peak Pressure ILRT can be made to ensure
{
that the total Containment leakage volume will not exceed the value assumed in the Safety Analyses at the Peak accident pressure. This reduced pressure l
test is initially performed during preoperational Startup tests in order to apply this correlation for j
future periodic ILRTs. The data collected by the American Nuclear Insurers ( ANI) for 50 pairs of preoperational ILRTs conducted at both peak and reduce pressure does not support a clear correlation between reduced pressure and peak leak rates.
Any relationship between leakage rates determined during preoperational testing cannot be reasonably presumed to exist for extended periods of time. During years of operation, the dominant leakage paths at any plant will tend to change due to operational events, modifications and maintenance. Testing and failure experience has shown that some leakage testing failures were due to the inception of leaks brought on by increasing pressure.
Using the Unit 1 Containment reduced pressure test results, a correlation could not be made. The proposed revision to 10CFR50 Appendix J does not allow reduced pressure tests to be used for periodic ILRT because it has not been demonstrated that one can
. _~.- _
I Attachment to TXX-93149 1
April 16, 1993 l
Page 6 of 45 l
Prefix Page -
l
(_a_s amended)
Group Description j
extrapolate a leakage rate from a reduced pressure test to a leakage rate under full pressure.
Refer l
t to the description provided for pages 3.8-72 and i
6.2-139 (ref. LDCR SA-92-733) in Amendment 86.
Change Request Number
- SA-92-764.1 l
Commitment Register Number :
l l
Related SER : 6.2.5 SSER :
[
SER/SSER Impact
- No l
6.5-26 3
In Section 6.5.2.4, Tests and Inspections, f
Paragraph 1. Preoperational Tests, where it states "Preoperational testing is conducted using refueling water as a test fluid.", deletes'the word
" refueling" and then adds the following sentence p
"The chemical additive tank (CAT) is aligned to the eductors and acceptable flow is demonstrated for each eductor over the range of CAT levels".
e Clarification I
Preoperational testing was performed utilizing water in the CATS.
Change Request Number
- SA-93-23.2 Commitment Register Number :
-[
Related SER : 6.5.2 SSER :23 6.5.2 SER/SSER Impact
- No 6.5-26 3
In Section 6.5.2.4, Tests and Inspections, Paragraph 1. Preoperational Tests, modifies the
{
sentence discussing evaluation of test data to read l
"For evaluation of test data, equivalent chemical i
solution and water flows are calculated accounting for physical differences (e.g. density and viscosity)".
l Correction l
The correlation factor discussed in the previous l
text applied to preoperational testing utilizing i
borated water. As discussed in Change SA-93-23.2, l
preoperational testing was actually performed utilizing just water in the CAT.
Refer to the Description for Page 6.5-26. Change Request No.
SA-93-23.2 Change Request Number
- SA-93-23.3 Commitment Register Number :
Related SER : 6.5.2 SSER :23 6.5.2
.SER/SSER Impact
- No 6.5-26 4
See Sheet No(s) :27 t
In Section 6.5.2.4 Tests and Inspections, Paragraph 1 Preoperational Tests, takes the portions of the text that deal with inservice testing and moves them to Section 6.5.2.4, Paragraph 2. Inservice Surveillance, as shown.
j Editori al Portions;of this section (6.5.2.4.1.)
-. -.. _... ~.,
l.
I Attachment to TXX-93149 j
i April 16. 1993 Page 7 of 45 Prefix Page (n amended)
Group Description inappropriately describe inservice surveillance testing which was reserved for section 6.5.2.4.2.
This includes the text that refers directly to inservice surveillance, discusses testing utilizing the refueling water storage tank.(RWST) and discusses periodic operation of the chemical j
additive tank isolation valves.
Change Request Number
- SA-93-23.1 Commitment Register Number :
}
Related SER : 6.5.2 SSER :23 6.5.2 i
SER/SSER Impact
- No 6.5-26 4
See Sheet No(s) :27 In Section 6.5.2.4. Tests and Inspections.
Paragraph 1. Preoperational Tests, in the sentence beginning with "A pressure gauge located... ".
changes the discussion of testing utilizing the RWST-test line to recognize throttling of flow in the j
test line rather than the use of an orifice.
(Note
}
that this sentence has been moved to Section j
6.5.2.4. Tests and Inspections. Paragraph 2, Inservice Surveillance, as described in Change i
Request No.93-023.1).
Clarification :
This change clarifies the use of flow throttling i
rather than the use of an orifice during testing.
l Change Request Number.
- SA-93-23.4 L
Commitment Register Number :
}
Related S R : 6.5.2-SSER :23 6.5.2 i
SER/SSER 1mpact
- Yes SER section 6.5.2. page 6-22 discusses Technical Specification surveillance testing. This testing is
(
described by the SER as utilizing floor drain connections to perform this. testing rather than a RWST test line.
(Note that this minor difference I
was not created by this FSAR change but was noted during review).
6.5-27 4
See Sheet No(s) :28 In Section 6.5.2.5. Instrumentation Requirements.
}
Paragraph 2. Chemical Additive Flow and Pressure.
I adds to the end of the second sentence "(; scribed in 6.5.2.4 above" and deletes the third sentence.
Clarification :
The addition to the second sentence was to clarify f
the testing being referred to.
The third sentence f
was deleted because it is out of place and testing i
is adequately described in the previous section.
Change Request Number
- SA-93-23.5
{
Commitment Register Number :
}
Related SER : 6.5.2 SSER :23 6.5.2 SER/SSER Impact
- No I
l Attachment to TXX-93149 April 16, 1993 Page 8 of 45 Prefix Page 1
(as _ amended)
Group Description 7.2-6 4
Adds description from 0222.5 response to the FSAR text.
Editorial Q&R response is revised to reference the FSAR text.
Change Request Number
- SA-92-222.1 Commitment Register Number :
Related SER : 7.2.1 SSER :22 7.2.1 SER/SSER Impact
- No 8.3-13 4
Adds description from 0423.34 response to the appropriate FSAR text section.
Editorial Q&R response is revised to reference the FSAR text.
Change Request Number
- SA-92-551.2 Commitment Register Number :
Related SER :
SSER :22 8.2.1 SER/SSER Impact
- No 8.3-65 2
Removes transformers T2C5-1 and T2C6-1 from the FSAR text.
Update Unit 2 Non-1E transformers in cable spreading room have been removed as they are no longer required.
I Change Request Number
- SA-93-18.1 Commitment Register Number :
Related SER : 8.4.4 SSER :26 8.4.6 SER/SSER Impact
- No Table 8.3-1A 2
See Sheet No(s) :02 and 07 Changes the Diesel Generator loading Table 8.3-1A to account for the added 0.2KW load due to the addition of new battery packs to emergency lighting panels.
Correction The added load ultimately increases the load on the Diesel Generator. The revised loading on the Diesel Generator is less than the rated capacity as well as the Technical Specification limits.
Change Request Number
- SA-92-837.1 Commitment Register Number :
Related SER : 8.3.1 SSER :22 8.3 i
SER/SSER Impact
- No Table 8.3-1B 4
See Sheet No(s) :01 through 07 Changes the table to read as " RECIRCULATION PHASE" and deletes " INJECTION PHASE" from the title.
Editorial This change is made to correct the typographical error in the table title.
l Change Request Number
- SA-92-837.4 Commitment Register Number :
l Related SER : 8.3.1 SSER :22 8.3 SER/SSER Impact
- No
i Attachment to TXX-93149 April 16. 1993 Page 9 of 45 i
l Prefix Page l
(n amended)
Group Description j
l Table 8.3-1B 2
See Sheet No(s) :02 and 07
. Changes the Diesel Generator loading Table 8.3-1B to account for the added 0.2KW load due to the addition of new battery packs to emergency lighting panels.
Correction l
The added load ultimately increases the load on the l
Diesel Generator. The revised. loading on the Diesel i
Generator is less than the rated capacity as well as the Technical-Specification limits.
r Change Request Number
- SA-92-837.2 Commitment Register Number :
i Related SER : 8.3.1 SSER :22 8.3 SER/SSER Impact
- No i
Table 8.3-1B 4
See Sheet No(s) :05 Deletes duplicate loading information on the Control-Room Makeup Supply Fan from the Table.
Editorial The loading information was inadvertently l
duplicated in the Table during roll-over process-for Amendment 87 of the FSAR (sheets 5 and 6 of Table 8.3-1B. Amendment 87).
Change Request Number
- SA-92-837.5 l
Commitment Register Number :
Related SER : 8.3.1
.SSER :22 8.3 SER/SSER Impact
- No Table 8.3-2 2
See Sheet No(s) :02 and 09 l
Changes the Diesel Generator loading Table 8.3-2 to account for the added 0.2KW load due to the addition e
of new battery packs to emergency lighting panels.
Correction The added load ultimately increases the load on the Diesel Generator. The revised loading on the Diesel-i Generator is less than the rated capacity as well as
)
the Technical Specification limits.
l Change Request Number
- SA-92-837.3 Commitment Register Number :
Related SER : 8.3.1 SSER :22 8.3 SER/SSER Impact
- No Figure 8.3-9 2
See Sheet No(s) :02 Changes the motor HP for the motor operated. valve 1-HV-2484 to 0.33HP and shows the splicing of the power cable E0100550A with E0100550 in the splice box per specification 2323-ES-100.
Revision This change is to provide adequate design margin for MOV testine "nder GL 89-10 by replacing the existing conf % ition with larger motor and splicing the vw
- and control cables-due to repositioning of the.new motors.
Attachment to TXX-93149 April 16, 1993 Page 10 of 45 Prefix Page (as amended)
Group DescriDtion Change Request Number
- SA-92-842.1 Commitment Register Number :
" elated SER : 8.3 SSER :22 8.3 SER/SSER Impact
- No Figure 8.3-9 2
See Sheet No(s) :04 Changes the motor HP for the motor operated valve 1-HV-2485 to 0.33HP and shows the splicing of the power cable EG100613A with EG100613 in splice boxes per specification 2323-ES-100.
Revision This change is to provide adequate design margin for H0V testing under GL 89-10 by replacing the existing configuration with large motor and splicing the power and control cables due to repositioning of the new motors.
Change Request Number
- SA-92-842.2 Commitment Register Number :
Related SER : 8.3 SSER :22 8.3 SER/SSER Impact
- No Figure 8.3-14A 2
See Sheet No(s) :01 Revises the ground fault detection circuit for DC switchboard ID2 to lower the value of the resistor from 50K-Ohm to SK-Ohm.
Correction The current resistor value in the circuit is too high to allow for the proper operation of the ground fault detection lights on panels. The new lower resistor value would allow proper operation of the lights when the ground detector switch is operated.
Change Request Number
- SA-92-843.1 Commitment Register Number :
Related SER : 8.3 SSER :22 8.3 SER/SSER Impact
- No Figure 8.3-14A 2
See Sheet No(s) :02 Revises the ground fault detection circuit for DC switchboard IDI to lower the value of the resistor from 20K-Ohm to 33-Ohm.
Correction The current resistor value in the circuit is too high to allow for the proper operation of the ground fault detection lights on panels.
The new lower l
resistor value would allow proper operation of the lights when the ground detector switch is operated.
Change Request Number
- SA-92-843.2 Commitment Register Number :
Related SER : 8.3 SSER :22 8.3 SER/SSER Impact
- No 9.2-40 4
Adds word " permanent" to Item 1 of Section 9.2.4.1.
Clarification :
i, l
Attachment to TXX-93149 3
April 16, 1993 Page 11 of 45 4
I i
Prefix Page I
(as amended)
Group DgscriDtion Potable water system supplies only permanent locations.
l i
Temporary locations may use bottled water.
l Change Request Number
- SA-92-592.1 Commitment Register Number :
i Related SER : 9.2.4 SSER :
l SER/SSER Impact
- No 4
y l
9.2-40 3
Deletes reference to use of potable / sanitary water i
for treatment plant. gas chlorination (formerly Item 2 to Section 9.2.4.1.
I Update 4
Gaseous chlorination is no longer used.
The system l
1 was replaced with solid chlorination using treated l
sewage flow.
j Change Request Number
- SA-92-592.2 l
5 Commitment Register Number :
i Related SER.: 9.2.4 SSER :-
SER/SSER Impact
j
,j 9.2-40 3
Adds emergency eyewash and deletes. specific
{
locations of these emergency facilities (formerly l
1 Item 3' renumbered as Item 2 to Section 9.2.4.1).
i j
Update f
The emergency showers also contain eyewashes.
i The locations of the emergeacy facilities change l
from time-to-time and is considered to be 2
unnecessary detail.
l Change Request Number
- SA-92-592.3 l
Commitment Register Number :
Related SER : 9.2.4 SSER :
l 1
SER/SSER Impact
- No i
9.2-40 3
Expands Item 5 (renumbered to be Item 3) in 'Section j
9.2.4.1 to indicate potable water is used in various
[
on-site buildings to supply fire protection hoses.
1 Update 1
Clarifies the fire protection usage-of potable water.
Change Request Number
- SA-92-592.5 l
f Commitment Register Number :
3 Related SER : 9.2.4 SSER :
1 SER/SSER Impact
- No t
9.2-40 4
Changes the name " fire water storage tanks" in l
It'm 4 (formerly Item 6) to Section 9.2.4.1 to read as ~' Fire Protection Storage Tank".
Editorial l
Updates name of the Fire Protection Storage Tank.
I Change Request Number
- SA-92-592.6 Commitment Register Number :
i Related SER : 9.2.4 SSER :
l SER/SSER Impact
- No
Attachment to TXX-93149 April 16, 1993 Page 12 of 45 i
Prefix Page fa_s amended)
Group Description 9.2-41 3
Deletes Item 4 concerning removal of wastes produced by potable / sanitary water from Section 9.2.4.1 and renumbers Items 5 and 6 as Items 3 and 4.
Update The transport of potable and sanitary wastes is discussed in 9.2.4.2.
i Change Request Number
- SA-92-592.4 Commitment Register Number :
Related SER : 9.2.4 SSER :
SER/SSER Impact
- No 9.2-41 3
Deletes Items 7 and 8 concerning potable / sanitary water usage from Section 9.2.4.1.
Update These items were unclear and contained excessive detail.
Change Request Number
- SA-92-592.7 Commitment Register Number :
Related SER : 9.2.4 SSER :
SER/SSER Impact
- No 9.2-41 4
Provides an updated description of potable water system to Section 9.2.4.2 (first paragraph).
Update The water treatment system is presently isolated from the potable water system.
Change Request Number
- SA-92-592.8 Commitment Register Number :
Related SER : 9.2.4 SSER :
SER/SSER Impact
- Yes The SER indicates the surface water pre-treatment faclity may supply potable water.
9.2-41 4
Changes the second paragraph of Section 9.2.4.2 to indicate the chlorination by the additon of sodium hypochlorite and renames the Texas Board of Health to read as the Texas Department of Health.
Clarification Clarifies the method of potable water chlorination and updates the name of the Texas Department of Health.
Change Request Number
- SA-92-592.9 Commitment Register Number :
Related SER : 9.2.4 SSER :
SER/SSER Impact
- No 9.2-41 4
Adds reference to regulatory permits in Section 9.2.4.2.
l Clarification :
This is consistent with past and present practices but is now added for clarity.
Change Request Number
- SA-92-592.10
Attachment to TXX-93149 April 16, 1993 Page 13 of 45 Prefix Page
(_al amended)
Srpup Description u
Commitment Register Number :
Related SER : 9.2.4 SSER :
SER/SSER Impact
- No 9.2-42 3
Deletes the last paragraph of Section 9.2.4.2 describing on-site wells.
Update This description is unnecessary detail which changes from time-to-time.
Change Request Number
- SA-92-592.11 Commitment Register Number :
Related SER : 9.2.4 SSER :
SER/SSER Impact
- No 9.2-42 4
Changes the discussion of the alternate supply of water in the event that a power failure occurs with all well pumps.
Clarification Clarifies the discussion of " trucked in" potable water in the event of well pump failure.
Change Request Number
- SA-92-592.12 Commitment Register Number :
Related SER : 9.2.4 SSER :
SER/SSER Impact
- No 9.2-43 4
Changes the discussion in Item 2 to Section 9.2.4.4.
Clarification Clarifies discussion of potable water testing.
Change Request Number
- SA-92-592.13 Commitment Register Number :
Related SER : 9.2.4 SSER :
l SER/SSER Impact
- No 9.2-44 3
Delete Reg. Guide 1.26 from discussion regarding regulatory guidance for design of the ultimate heat sink.
Clarification Reg. Guide 1.26 can be deleted from the text because it does not apply to the Safe Shutdown Impoundment.
Reg. Guide 1.26 applies to components of fluid systems within the scope of the ASME B&PV Code.
Change Request Number
- SA-93-13.1 Commitment Register Number :
Related SER : 9.2.5 SSER :
SER/SSER Impact
- No 9.2-49 3
Correct description of peak Component Cooling Water temperature by deleting "during the first 400 seconds after the DBA" and adding "upon initiation of containment spray recirculation."
Clarification :
The deleted information was the approximate time to reach maximum sump temperature, not the CCW
Attachment to TXX-93149 April 16, 1993 Page 14 of 45 Prefix Page i
(as amended)
Group Description l
maximum temperature. This information was inadvertently added in Amendment 77.
The initial switchover to ECCS recirculation cannot occur prior to 10 minutes. The peak CCW temperature occurs after the empty setpoint alarm (approximately 17 minutes post-LOCA) when containment spray switchover begins. The added information clarifies when the CCW water reaches maximum temperature.
Change Request Number
- SA-93-13.2 Commitment Register Number :
Related SER : 9.2.5 SSER :
SER/SSER Impact
- No 9.2-49 3
In the sentence that discusses when the maximum CCW temperature occurs, change "four" to "several."
Clarification Since the peak CCW temperatures do not occur at specific times, the specific time interval of "four hours" is inappropriate. The peak CCW temperatures occur at specific plant evolutions.
This change clarifies the evolutions associated with the maxima of 135 degrees F and 122 degrees F.
Change Request Number
- SA-93-13.3 Commitment Register Number :
Related SER : 9.2.5 SSER :
SER/SSER Impact
- No 9.2-53 3
See Sheet No(s) :54 Revises the description in Section 9.2.7.1 of the Surface Water Pre-Treatment System and what it supplies.
Update Due to pending EPA legislation the potable water system is isolated from the Pre-Treatment System. The Surface Water Pre-Treatment supplies all water for plant make-up but not potable water.
Change Request Number
- SA-92-592.14 Commitment Register Number :
Related SER : 9.2.4 SSER :
SER/SSER Impact
- Yes The SER indicates the Surface Water Pre-Treatment System may supply potable water.
9.2-53 4
See Sheet No(s) :54 Clarifies the description in Section 9.2.7.2 of the pre-treatment facility.
Clarification :
Replaces " pre-treatment facility" with clarifier to better describe the portion of the pre-treament facility involved.
Change Request Number
- SA-92-592.15 Commitment Register Number :
Related SER : 9.2.4 SSER :
I A* tachment to TXX-93149 April 16, 1993 Page 15 of 45 Prefix Page 1
(as amended)
Group Description SER/SSER Impact
- No j
i 9.2-54 4
Deletes "to the low volume waste pond" from the first paragraph of Section 9.2.7.3.
Clarification :
This is deleted for clarity since the low volume waste pond is part of the Waste Management System.
j Change Request Number-
- SA-92-592.16 Commitment Register Number :
Related SER : 9.2.4 SSER :
SER/SSER Impact
- No l
J 9.2-55 4
Deletes the last sentence of Section 9.2.7.3 which 3
discussed sources of water in the event of power failure.
l Clarification Removes redundant detail. These sources of water are already covered in 9.2.7.2.
Change Request Number
- SA-92-592.17 Commitment Register Number :
s I
Related SER : 9.2.4 SSER :
l SER/SSER Impact
- No i
9.2-55 4
Deletes the discussion of instrumentation used in j
q the surface pre-treatment system from Section j
9.2.7.5.
t Clarification l
The instrumentation listed has been disabled or disconnected due to unreliable performance or excessive maintenance. The system parameters are read locally and system parameters adjusted as necessary.
Change Request Number
- SA-92-592.18 Commitment Register Number :
1, Related SER : 9.2.4 SSER :
SER/SSER Impact
- No 3
4 Figure 9.2-3 3
See Sheet No(s) :02, 03, 04, 06 and 09 l
Change the CCW unit isolation valves on the common components to normally closed.
Correction The common cooling loads on the CCW systems may be fed from either unit without giving a preference to a specific unit.
The figures at present depict the-valve alignment to one particular unit.
In order to indicate that unit separation is maintained, the position of the component valves is locked closed.
These changes are consistent with FSAR Section 9.2.2 and meet the separation requirements in accordance with 10CFR50, Appendix A, GDC 5.
Change Request Number
- SA-93-14.
Commitment Register Number.:
s y
Related SER : 9.2.2 SSER :25 9.2.2
l i
Attachment to TXX-93149 April 16, 1993
.l Page 16 of 45 Prefix Page (n amended)
Group Description
{
l SER/SSER Impact-
- No Figure 9.2-4A 4
See Sheet No(s) :04 f
Revised figure to show the 2 1/2" line coming from l
the auxiliary boiler sump pump running to the waste l
sump and pumps.
i Correction Drawing change required to reflect as-built condition of piping.
This is a trivial change to non-safety related piping for the Surface Water Pre-treatment System.
l Change Request Number
- SA-93-27.1 Commitment Register Number :
Related SER : 9.2 SSER :22 9.2 SER/SSER Impact
- No i
Figure 9.2-5 3
See Sheet No(s) :01 l
Adds eye wash and local shower station to non-nuclear safety related structure / system.
l Addition l
These changes are non-nuclear safety related in a non-nuclear safety related structure (Turbine i
Building). The changes made to the non-nuclear safety related demineralized water system add a local eye wash / shower station & associated valves, j
l These changes do not affect any plant operation or events which are described in the FSAR, SER, or i
other LBDs. This change was inadvertently included l
in Amendment 87 and thus is not included in this Amendment.
l Change Request Number
- SA-92-695.
Commitment Register Number :
l Related SER : 9.3.3 SSER :6 9.3.3 i
SER/SSER Impact
- No 7
Figure 9.2-6 4
Drain valve added to Figure 9.2-6 and heat trace i
requirement removed from potable water line.
I Correction The drain valve wasadded for operational reasons.
The heat tracing is not required since the piping is underground or in the auxiliary boiler building.
This change _has no impact on safety related systems, structures or components.
Change Request Number
- SA-93-37.
Commitment Register Number :
Related SER : 9.2.4 SSER :22 9.2.4 SER/SSER Impact
- No Figure 9.3-1 3
See Sheet No(s) :01, 08 and 14
- 1) Change position of the following valves in the Instrument Air System to normally. pen status:
a) 2HV-3476 as shown on Fig. 9.3-1, Sheet 1 (Location E-6).
. - ~
l i
Attachment to TXX-93149 l
April 16, 1993 l
Page 17 of 45 Prefix Page (as amended)
GrouD DescriDtion i
l b) Valve in the line from Unit 2 instrument air i
dryer on Fig. 9.3-1. Sheet 8 (Location B-4).
c) 2-PV-4252 and 4253 in Service Water Pump House as shown on Fig. 9.3-1 Sheet 14 (Location F-2 F-5).
- 2) Change position of valve in Instrument Air System i
from Unit 2 instrument air dryer to normally closed as shown on Fig. 9.3-1, Sheet 8 (Location C-5).
Update All of the valves affected by this change, except 101-0684 were designated as LC-2 valves. The LC-2 designation was used to identify valves that were to be locked closed during Unit 2 construction / Unit 1 operation to serve as the Unit 1/ Unit 2 cross tie isolation points. This isolation provided protection for major equipment during Unit 2 construction and was in addition to any locking requirements necessary to meet GDC-5, " Sharing l
Structures, Systems, and Components." Valve ICI-i l
0684 is required to be normally open per request by i
I operations. This valve is not safety related and is not associated with GDC-5.
This change does not alter the original design intent and will allow for i
l normal operation of the plant.
l Change Request Number
- SA-93-7.
l Commitment Register Number :
j Related SER : 9.3.1 SSER :23 l
SER/SSER Impact
- No Figure 9.3-4 3
See Sheet No(s) :01 This change replaces 3/4" globe uni-valves in the Process Sampling System with 3/4" hermetically-sealed globe valves.
Update 1
The modification of changing globe valves to hermetically-sealed valves is an upgrade to the Process Sampling System.
This modification will improve ALARA considerations for these valves and will improve the capability of the valves to act as a boundary valve for isolation valve testing.
ALARA is improved by isolating the valve stem and packing from the reactor coolant water, thus preventing stem leakage. The design, function or operation of the valves and Process Sampling System is not affected by this modification.
Change Request Number
- SA-92-690.
Commitment Register Number :
i Related SER : 9.3.2 SSER :22 9.3.2 SER/SSER Impact
- No i
Figure 9.3-4 3
See Sheet No(s).:01, 02, 03 and 03A I
l Add " NOTE
- CHANGES APPLY T0 UNIT 2 ONLY" for RC Pass
Attachment to TXX-93149 April 16, 1993 Page 18 of 45 i
Prefix Page (as amended)
GrouD DescriDtion Sample Cooler, Component Cooling Water non-safeguard loop, and Steam Generator Blowdown sample panel drains in the Process Sampling' System.
}
Delete piping changes for the RC Process Sample Cooler j
l and Component Cooling Water non-safeguard drains for Unit 2 Process Sampling System.
Update The above changes are made to reflect the as-built routing of the Process Sampling System piping and i
tubing. The changes do not affect the Process.
Sampling System function or operation as previously shown in Figure 9.3-4.
l
. Change Request Number
- SA-92-651.
l Commitment Register Number :
Related SER : 9.3.2 SSER :22 9.3.2 SER/SSER Impact
- No
- i Figure 9.3-4 3
See Sheet No(s) :02, 03A Add vent line to Process Sampling System drain line.
Addition The added vent line will provide a direct exhaust to reduce the amount of airborne contamination in the sample room. The added information to other FSAR figures will maintain consistency between the flow diagrams and the FSAR.
This change is only applicable to Unit-1.
Change Request Number
- SA-92-732.1 Commitment Register Number :
Related SER : 9.3.4 SSER-:
SER/SSER Impact
- No Figure 9.3-9 4
See Sheet No(s) :01 Valve XVD-0579 added to the discharge of the Sump 1 pumps in the Turbine and Fuel Handling Building Vents and Drains System.
Correction Reflects the current as-built configuration of the.
system. Valve XVD-0579 was-inadvertently removed from a previous revision'of the flow diagram.
Change Request Number'
- SA-93-28.
Commitment Register Number :
Related SER : 9.3.3 SSER :6 9.3.3 SER/SSER Impact
- No Figure 9.3-9 4
See Sheet No(s) :02 Delete pipe caps at B10 and B12 tie-ins on drain header B upstream of.the 3 inch isolation valves.
Correction The cap connections upstream of the 3-inch isolation valves were a drafting error.
Change Request Number
- SA-93-29.
Commitment Register Number :
Related SER : 9.3.3 SSER :6 9.3.3
Attachment to TXX-93149 April 16, 1993 Page 19 of 45 Prefix Page
(_a_s amended)
Group Description i
i SER/SSER Impact
- No Figure 9.3-10 3
See Sheet No(s) :08 This change corrects Boric Acid Transfer Pumps valves to indicate that valves 2CS-8457A, B. C and D are open and locked in position. This change also removes the LC-2: designation from the figure.
Update This change corrects the typographical errors (LO to LIP) for valves 2CS-8475A and B.
Valves 2CS-8457C and D were previousley LC-2 valves.
Correcting these valves to." LIP" makes them consistent with the i
as-built configuration. This change restores the l
valves to their design position in order to provide adequate Boric Acid Transfer Pump Protection (miniflow) while operating'in a two pump, common recirculation line configuration.
Change Request Number _
- SA-93-15.
Commitment Register Number :
Related SER : 9.3.4 SSER :
SER/SSER Impact
- No
^
Figure 9.4-1 3
Sae Sheet No(s) :01 For all dampers annotated "LO SEE NOTE 16" delete l
the "LO" from the drawing and change Note 16 from I
"Due to flow balancing, dampers are locked in the open position.", to " Damper Manually Positioned For Flow Balancing Purposes."-
Add new Note 17 (applicable to damper CPX-VADP00-25) as follows: " Damper fails to_a preset position determined by flow balancing."
Revision The ventilation dampers do not fall in any criterion-i of the locking program described in ER-ME-15.
These 8
dampers are utilized for flow balancing purposes
.i only.
l Note 17 was:added for clarification.
l Change Request Number
- SA-93-30.1 i
Commitment Register Number :
Related SER : 9.4 SSER :22 9.4.4-SER/SSER Impact
- No i
Figure 9.4-2 3
See Sheet No(s) :01, 02, 03, 04, and 05 For all dampers annotated "LO SEE NOTE 12" delete I
the "LO" from the drawing and change Note-12 from "These dampers are locked open. All air connections and electrical connections are' disconnected. Hand wheels are locked to prevent local operations. All instrumentation and operators have been removed.",
to "These dampers are abandoned in-place (in open position). All air connections and electrical connections are disconnected. - All instrumentation and operators have been removed.".
I
4 Attachment to TXX-93149 April 16, 1993 Page 20 of 45 l
Prefix Page (as amended)
Group Description Revi si on These dampers have been rendered inoperable and are abandoned in place. The ventilation dampers do not fall in any criterion of the locking program described in ER-ME-15.
Change Request Number
- SA-93-30.2 Commitment Register Number :
Related SER : 9.4 SSER :22 9.4.4 SER/SSER Impact
- No Figure 9.4-4 3
See Sheet No(s) :02 and 04 For all dampers annotated "L0 SEE NOTE 4" delete the "LO" from the drawing and change Note 4 from
" Dampers are locked open in Unit 1.
They are not installed in Unit 2.", to " Dampers are abandoned in-place (in open position) in Unit 1.
They are not installed in Unit 2.".
Revision These dampers have been rendered inoperable and are abandoned in place. The ventilation dampers do not fall in any criterion of the locking program described in ER-ME-15.
Change Request Number
- SA-93-30.3 j
Commitment Register Number :
l Related SER : 9.4 SSER :22 9.4.4 l
SER/SSER Impact
- No Figure 9.4-4 3
See Sheet No(s) :04 Add vent line to Process Sampling System drain line.
Addition The added vent line will provide a direct exhaust to reduce the amount of airborne contamination in the sample room.
The added information to other FSAR i
figures will maintain consistency between the flow diagrams and the FSAR.
This change is only j
applicable to Unit 1.
Change Request Number
- SA-92-732.2 Commitment Register Number :
Related SER : 9.4.4 SSER :25 9.4.4 i
SER/SSER Impact
- No l
Figure 9.4-9 4
See Sheet No(s) :01 Remove the air equalizer f rom the flow element assembly X-FE-6175D from the Primary Plant Ventilation System intake duct.
Update l
The air equalizer X-FE-6175D is damaged and has been removed.
Removal of the air equalizer from the flow element assembly has no potential safety impact to the system.
In the event that flow element is located too close to the source of turbulent flow, the air equalizer is required to improve the air flow measurement. There is sufficient distance
Attachment to TXX-93149 l
April 16, 1993 l
Page 21 of 45 i
i Prefix Page j
(_a_s amended)
Group Description between X-FE-6175D and the source of the turbulent flow.
In addition, sufficient numbers of air flow measurement sensors are available to provide an accurate air flow reading.
In the event that it is necessary to obtain a confirmation of the air flow reading, additional traverse locations are available for air flow comparisons.
Change Request Number
- SA-93-8.
Commitment Register Number :
Related SER : 9.4.4 SSER :25 9.4.4
(
SER/SSER Impact
- No l
l Figure 9.4-9 3
See Sheet No(s) :01 and 03 Delete the word " locking" from Note 6.
l Add a new note 10 that states " Damper abandoned in-place (in open position). All air and electrical connections are disconnected ", and add this note to damper CP2-VADPOC-03.
Revision The ventilation dampers (associated with Note 6) do not fall in any criterion of the locking program described in ER-ME-15.
This damper (CP2-VADPOC-03) has been rendered inoperable in the open position and is abandoned in place. This ventilation damper does not fall in any criterion of the locking program described in ER-ME-15.
Change Request Number
- SA-93-30.4 i
Commitment Register Number :
Related SER : 9.4 SSER :22 9.4.4 SER/SSER Impact
- No Figure 9.4-11 3
See Sheet No(s) :01 Change the proper valve positions and flow arrows for the Non-Safety Ventilation Chilled Water System.
Update This change represents the as-built design and is also consistent with the description in FSAR Section 9.4E.
It also accurately reflects operation of the Chilled Water System with both Ventilation Chilled Water subsystems.
Change Request Number
- SA-92-845.
Commitment Register Number :
Related SER : 9.4.6 SSER :22 9.4.6 SER/SSER Impact
- No Figure 9.4-12 3
See Sheet No(s) :01, 02 & 03 Adds a new symbol for disc-less check valves.
Clarification This is an editorial change to provide a user friendly symbol and clarify the as-built condition.
The not:s for each affected valve are unchanged in meaning.
Change Request Number
- SA-92-854.2
~..
i j
Attachment to TXX-93149 l
April 16. 1993 j
l Page 22 of 45 Prefix Page (n amended)
Group Description Commitment Register Number :
Related SER : 3.2
_ SSER :
j SER/SSER Impact
- No l
l 9.5-113 2
Changes carpet class'from "II or higher" to "I" of i
NFPA 101, 1991 ED. for carpet in the control room envelope.
Revision This change makes this information consistent with as-built conditions and Safety Evaluation SE-91-067 Rev. O.
Change Request Number
- SA-92-856.1 i
Commitment Register Number :
l Related SER : 9.5 SSER :23 9.5 SER/SSER Impact
- No i
10.4-30 4
Inserts the last two paragraphs of the response to-j O&R 040.105 into FSAR Section 10.4.4.3.
l Q&R Incorporation :
This an editorial change to ready the 0&R Section l
for deletion when the updated FSAR is prepared.
i Refer to the justification for Page 0&R 040-140, j
Change Request Number SA-92-174.1.
Change Request Number
- SA-92-174.2 Commitment Register Number :
i Related SER : 15.2.1 SSER :23 15.2.1 SER/SSER Impact-
- No i
10.4-38 3
See Sheet No(s) :40, 42, 43, 44, 47 Revises the Condensate Cleanup system's backwash l
reclamation function in Section 10.4.6 to indicate that reclamation or discharge are both options.
l Clarification :
l Backwash water is normally discharged and not reclaimed.
Reclamation of backwash water is normally l
only performed in the event of extreme water shortage.
i Change Request Number
- SA-92-592.19 i
Commitment Register Number :
i Related SER : 11.2.1.2SSER :
l SER/SSER Impact __
- Yes SER 11.2.1.2 discusses the reclamation of backwash water.
10.4-39 3
See Sheet No(s) :45 Updates Condensate Cleanup System effluent quality criteria in Section 10.4.6 to remove reference to specific revisions of EPRI and NSSS vendor guideline documents (these documents are often revised) and removes the specific impurity concentration levels.
Update Vendor and EPRI guidlines are general, sometimes conflict, and are not always applicable to CPSES.
i Attachment to TXX-93149 April 16. 1993 1
Page 23 of 45 Prefix Page (as amended)
GrouD DescriDtion CPSES technical evaluations are performed if exceptions to secondary feedwater chemistry guidelines are taken.
Change Request Number
- SA-92-592.20 l
Commitment Register Number :
l Related SER : 10.4.6 SSER :
SER/SSER Impact
- No 10.4-40 3
Adds the word "normally" as related to use of powdered ion exchange resin in Section 10.4.6.2 Subsection 1.
Update Other precoat media such as "Ecodex" may be used in special circumstances.
Change Request Number
- SA-92-592.21 Commitment Register Number :
Related SER : 10.4.6 SSER :
SER/SSER Impact
- No i
10.4-40 3
Adds the spent resin tank and pump skid to the listing of main components of the Condensate Cleanup System in Section 10.4.6.2. Subsection 1.
Addition These components were inadvertantly omitted from the l
previous description.
Change Request Number
- SA-92-592.22 Commitment Register Number :
Related SER : 10.4.6 SSER :
l SER/SSER Impact
- No 10.4-41 3
Deletes discussion of a specific demineralizer vessel line-up from Section 10.4.6.2, Subsection 2.
Update The existing line-up was unecessarily restrictive.
I Removal provides the flexibility to use any appropriate configuration.
Change Request Number
- SA-92-592.23 Commitment Register Number :
Related SER : 10.4.6 SSER :
SER/SSER Impact
- No 10.4-41 3
Revises discussion of operator action on high differential pressure to remove the reference to the standby vessel in Section 10.4.6.2. Subsection 2.
Update Depending on the line-up there may not be a standby vessel.
Change Request Number
- SA-92-592.24 Commitment Register Number :
Related SER : 10.4.6 SSER :
SER/SSER Impact
- No 10.4-41 3
Expands the discussion in Section 10.4.6.2 Subsections 2 and 4 of when a demineralizer is to be
i Attachment to TXX-93149 April 16, 1993 Page 24 of 45 Prefix Page (as amended)
Group Descriotion serviced.
Update Other parameters are monitored besides conductivity to determine when servicing the demineralizers is required.
Change Request Number
- SA-92-592.25 Commitment Register Number :
l Related SER : 10.4.6 SSER :
l SER/SSER Impact
- No 10.4-41 3
Deletes reference to 75 gpm holding pump flow from Section 10.4.6.2, Subsection 2.
Revision System design does not allow flow measurement.
The resin " holding" capacity is based on the rating of the pump.
Change Request Number
- SA-92-592.26 Commitment Register Number :
Related SER : 10.4.6 SSER :
SER/SSER Impact
- No 10.4-42 4
Updates the description of the demineralizer backwash and precoating in Section 10.4.6.2, Subsection 3.
Clarification Clarifies that the vessel is filled prior to precoating and can be put directly into service (rather than just standby), and that the backwash pump discharges to the backwash drain line.
Change Request Number
- SA-92-592.27 Commitment Register Number :
Related SER : 10.4.6 SSER :
SER/SSER Impact
- No 10.4-42 4
Deletes reference to the resin slurry concentration from Section 10.4.6.2, subsection 3.
Clarification This is unnecessary detail which may change.
Change Request Number
- SA-92-592.28 Commitment Register Number :
Related SER : 10.4.6 SSER :
SER/SSER Impact
- No 10.4-44 3
Deletes the description of recovery of Tank A decant water from Section 10.4.6.2, Subsection 5.
Revision The tank water contains more than acceptable concentration of organics and colloidal material for reclamation.
Change Request Number
- SA-92-592.37 Commitment Register Number :
Related SER : 11.2.1.2SSER :
SER/SSER Impact
- Yes
l Attachment to TXX-93149 April 16, 1993 i
Page 25 of 45 l
l Prefix Page
)
(n amended)
Group Description i
SER 11.2.1.2 discusses decant recovery.
l 10.4-44 4
Changes Section 10.4.6.2. Subsection 5 discussion of requirements and limits on resins.
{
Clarification Clarifies that the limit is on the inventory of l
radioactive material not on the quantity of powdex resins.
Change Request Number
- SA-92-592.29 r
Commitment Register Number :
i Related SER : 10.4.6 SSER :
l SER/SSER Impact
- No 10.4-44 3
Deletes discussion of the hot phase separator tank l
l and adds reference to the transfer of radioactive resin wastes in Section 10.4.6.2, Subsection 5.
l Revision The transfer system to the hot phase separator tank l
has ben demonstrated to be ineffective and is no i
l longer used.
Radioactive _ resin wastes are transferred
[
directly to a disposal container.
i Change Request Number
- SA-92-592.30 i
l Commitment Register Number :
j Related SER : 11.2.1.2SSER :
SEP,/SSER Impact
- Yes SER 11.2.1.2 discusses the use of the phase separator.
{
10.4-44 4
Clarifies the conditions for bypassing the l
l Condensate Cleanup System (CCS) in the first l
l paragraph of Section 10.4.6.4.
l Editorial The Condensate Cleanup System can only reduce l
contaminants and minimize impact on plant chemistry.
1 It cannot prevent limits from being exceeded in the l
event of a condenser tube leak.
Change Request Number
- SA-92-592.31 Commitment Register Number :
Related SER : 10.4.6 SSER :
SER/SSER Impact
- No 10.4-46 4
Changes the pressure differential range from "25 to 40 psi" to read as "40 psi" in Section 10.4.6.5, subsection 2.
Editorial There is no minimum for differential pressure.
Change Request Number
- SA-92-592.32 Commitment Register Number :
Related SER : 10.4.6 SSER :
SER/SSER Impact
- No 10.4-46 4
Changes the second paragraph of Section 10.4.6.5, Subsection 3.
l Editorial i
l
~
I Attachment to TXX-93149 April 16. 1993 Page 26 of 45 i
Prefix Page (as amended)
Group Dg_scription Deletes a redundant reference to cation conductivity.
Change Request Number
- SA-92-592.33 Commitment Register Number :
Related SER : 10.4.6 SSER :
SER/SSER Impact
- No 10.4-46 3
Deletes reference to the carbon dioxide analyzer i
from Section 10.4.6.5, Subsection 3.
Revision The carbon dioxide has been ineffective and its use has been discontinued.
Change Request Number
- SA-92-592.34 Commitment Register Number :
Related SER : 10.4.6 SSER :
SER/SSER Impact
- No 10.4-47 4
Changes the discussion of the expected life of the filter element in Section 10.4.6.6 Editorial Deletes reference to a " minimum" lifetime of filter elements since this is really an " expected" lifetime.
Change Request Number
- SA-92-592.35 Cormitment Register Number :
Related SER : 10.4.6 SSER :
SER/SSER Impact
- No 10.4-48 3
Deletes reference to the Condensate Cleanup System interface to Radwaste System from the last paragraph to Section 10.4.6.7.
Revision This previously referred to the hot phase separator transfer which is no longer used. See description provided for page 10.4-44.
Change Request Number
- SA-92-592.36 l
Commitment Register Number :
Related SER : 10.4.6 SSER :
SER/SSER Impact
- No i
Figure 10.4-5 3
See Sheet No(s) :01 and 04 Show valve XCW-0008 as closed on Sh. 1 (location F-6) and valve XCW-0035 as open on Sh. 4 (location A-3).
Revision Valve XCW-0008 was shown in Sh. I as a locked closed (LC-2) designated valve prior to Amendment 87. which removed the LC-2 designation on the valve from this l
drawing. The LC-2 designation was used to identify valves that were to be locked closed during Unit 2 construction with Unit 1 in operation. These valves served as the Unit 1/ Unit 2 cross tie isolation points. This isolation was to provide for major equipment protection during Unit 2 construction and was in addition to any locking requirements
Attachment to TXX-93149 April 16,1993 Page 27 of 45 Prefix Page (as amended)
Group Description i
necessary to meet GDC-5, " Sharing Structures, i
Systems, and Components".
Valve XCW-0035 is required to be opened per Operations request.
Operations request to keep valve XCW-0008 closed and to open valve XCW-0035 does not alter the established. design intent and will allow for normal operation of the plant.
Change Request Number
- SA-93-6.1 j
Commitment Register Number :
Related SER : 10.4.5 SSER :4 10.4.5 SER/SSER Impact
- No Figure 10.4-10 4
See Sheet No(s) :02
{
Change drawing in four places to show a olind flange _
l at each of the resin fill connections for the steam generator blowdown system demineralizers.
Correction j
These blind flanges were inadvertently omitted from I
the figure. This change brings the FSAR figure into agreement with the as-built condition of the plant.
Change Request Number
- SA-93-17.1 Commitment Register Number :
[
Related SER : 10.4.8 SSER :22 10.4.8 SER/SSER Impact
- No Figure 10.4-14 4
See Sheet No(s) :02 Adds four 1 inch globe valves (2 each to 2-LS-2612A i
and 2-LS-2611A respectively) to bridle piping on i
heaters 2-6A and 2-6B.
Includes " Note 7: These valves pertain to Unit 2 only".
Correction l
This change adds Unit 2 instrumentation isolation valves to FSAR Figure 10.4-14. Sheet 2 to reflect I
the change made to the Heater Drains System by an approved design modification during construction, i
This correction will also be reflected in the l
respective plant flow diagram. These valves are Non-
[
Safety Related and this change will not affect any Safety Related systems. Design and function of the Heater Drains system is not impacted by this FSAR figure change.
Change Request Number
- SA-93-20.1 l
Commitment Register Number :
Related SER :
SSER :
SER/SSER Impact
- No 1
Figure 10.4-16 3
See Sheet No(s) :04 and 05 Adds a silencer on Auxiliary Boiler steam supply vent I
and replaces steam traps and steam trap bypass valves.
Revision The silencer reduces excessive noise while venting.
The steam traps and bypass valves have experienced excessive failures and are being replaced with more I
4 l
Attachment to TXX-93149 I
April 16, 1993
(
Page 28 of 45 l
Prefix Page i
(n amended)
Group Descriotion l
I reliable components.
Change Request Number
- SA-92-706.
i Commitment Register Number :
Related SER : 10.3 SSER :
l SER/SSER 1mpact
- _No Figure 10.4-16 4
See Sheet No(s) :05 Revised figure to show cap on temporary piping to backwash sump and to add the 2 1/2" line running to the water treatment waste sump.
Correction Drawing change is required to reflect as-built j
condition of the piping. This is a trivial change j
to non-safety related piping for the Auxilliary' Steam System.
Change Request Number
- SA-93-27.2 Commitment Register Number :
i Related SER : 10.4.6 SSER :22 10.4.6 l
l SER/SSER Impact
- No l
Figure 10.4-18 3
See Sheet No(s) :02 l
Change the position shown for valve XNG-0030 from i
normally " closed" to "open".
j Revision i
The nitrogen supply system at CPSES is shared i
between Units 1 and 2.
This cross connect valve, I
was maintained in a locked closed (LC-2) configuration during the completion of construction in Unit 2.
The valve's LC-2 designation was removed from this drawing by Amendment 87, leaving the valve j
shown as normally closed.
However, normal Unit 2 j
plant operations requires this valve to be open.
necessitating a revision to this Figure. This change does not alter the design intent of this j
system.
Change Request Number
- SA-92-857.1 Commitment Register Number :
Related SER :
SSER :26 APPEND.R SER/SSER Impact
- No Figure 10.4-19 3
Change the position shown for valve XHG-0025 from normally " closed" to "open".
Revision The hydrogen supply system at CPSES is shared between Units 1 and 2.
This cross connect valve.
was maintained in a locked closed (LC-2) configuration during the completion of construction in Unit 2.
The valve's LC-2 designation was removed from this drawing by Amendment 87, leaving the valve shown as normally closed. However, normal Unit 2 plant operations requires this valve to be open, necessitating a revision to this Figure. This change does not alter the design intent of this
~.
~ _ _. -
I-Attachment to TXX-93149 l
April 16, 1993 Page 29 of 45 t
i Prefix Page (as amended)
Group Description system.
I Change Request Number
- SA-92-857.2 Commitment Register Number :
Related SER :
SSER :
SER/SSER Impact
- No Table 11.2-8 3
See Sheet No(s) :2 & 3 1
Corrects certain nuclide values re: Liquid Waste Processing System (LWPS) co~ponent design m
inventories for the Recycle Holdup and Waste Monitor Tanks.
j Correction Values are corrected to be consistent with Design Calculation ME-CA-0000-3211. Rev. O.
Change Request Number
- SA-93-2.1 Commitment Register Number :
Related SER : 11.2.1 SSER :22 11.2.1 SER/SSER Impact
- No Table 11.2-10 3
See Sheet No(s) :1 Corrects certain isotopic values re: design release l
concentration with one percent failed fuel.
Correction Values are corrected to be consistent with Design Calculation ME-CA-0000-3211, Rev. O.
Change Request Number
- SA-93-2.2 Commitment Register Number :
Related SER : 11.2.1 SSER :22 11.2.1 SER/SSER Impact
- No Figure 11.2-2 3
Change address arrtw on figure to correctly refer to VENT HEADER: FIG 11.3-1 SH1; LOC A-3.
Correction Subject address arrow on Figure 11.2-2 was incorrect.
Change Request Number
- SA-92-707.1 i
Commitment Register Number :
Related SER :
SSER :
11.2 SER/SSER Impact
- No Figure 11.2-4 3
See Sheet No(s) :01 Change the position shown for valve XWP-0160 from normally " closed" to "open".
Revision The liquid waste processing system at CPSES is shared between Units 1 and 2.
This cross-connect valve, was maintained in a locked closed (LC-2) configuration during the completion of construction in Unit 2.
The valve's LC-2 designation was removed from this drawing by Amendment 87 leaving the valve shown as normally closed. ' However, normal Unit 2 plant operations requires this valve to be open, necessitating a revision to this Figure. This
i Attachment to TXX-93149 l
April 16,1993 Page 30 of 45 l
f t
Prefix Page (n amended)
Sroup Description l
change does not alter the design intent of this f
system.
)
Change Request Number
- SA-92-857.3 Commitment Register Number :
l Related SER : 11.2.1 SSER :22 11.2.1 l
SER/SSER Impact
- No I
Figure 11.3-1 3
See Sheet No(s) :01 Revise Figure to show valve IGH-7809 as a normally closed valve.
Revision l
The indicated valve is a manually operated valve that will isolate the Reactor Coolant Drain Tank l
(RCDT) from the Gaseous Waste Processing System (GH). By indicating this valve to be normally
^
1 closed and procedurally opening the valve when the j
i RCDT is vented, maintaining the hydrogen y
concentration in the GH system to within Tech Spec limits will be assured.
Change Request Number
- SA-92-707.2 Commitment Register Number :
Related SER :
SSER :
11.2 SER/SSER Impact
- No f
Figure 11.3-1 3
See Sheet No(s) :01 Revise figure.to show valve position XGH-0023 to normally open.
Revision This valve serves as the header isolation for Unit 2 i
feed from Process Sampling, Reactor Coolant Drain Tank, and Volume Control Tank to the Waste Gas l
4 Compressors. These feeds have individual block and control valves which. prevent uncontrolled releases j
to the Gaseous Waste Processing System. This change does not change the intended design, function or performance of the Gaseous Waste Processing System.
Change Request Number
- SA-93-12.1 l
Commitment Register Number :
Related SER :
SSER :
11.2 SER/SSER Impact
- No 13.1-1 4
Updates the descriptions of the TU Electric corporate and CPSES site organizational structures.
Update Section 13.1 has been updated to reflect the current TV Electric corporate organizational structure which now includes the following divisions: Operations:
Production: Bulk Power and Technical Support:
Finance and Corporate Support.
The title of the nuclear group within the Production Division, has been has been changed from " Nuclear Engineering and Operations (NEO)" to " Nuclear Production". The CPSES site organizational structure (Nuclear
I Attachment to'TXX-93149 l
April 16, 1993
)
Page 31 of 45 j
Prefix Page (a_s 3 mended)
Sroup Description Production Group) has been updated to indicate the j
following organizations:
Nuclear Engineering and Support: Nuclear Operations: Regulatory Affairs; and l
Nuclear Overview.
I Change Request Number-
- SA-92-839.1 Commitment Register Number :
Related SER : 13.1 SSER :25 13.1 SER/SSER Impact
- Yes Section 13.1. should be-updated to reflect the j
current organizational structure.
(
13.1-2 4
See Sheet No(s) :03 i
Updates the Nuclear Production Group's management l
and technical support organization descriptior.s.
i Update l
l Section 13.1.1.1.1 and'13.1.1.1.3 have been updated j
to indicate that the " Engineering and Construction" l
l organization no longer exits in the current.
l l
organizational structure. These responsibilities
_j have been assumed by the " Nuclear Engineering and t
Support" organization.
i Section 13.1.1.1.2 has been revised to more accurately reflect to the division of j
responsiblities for the Initial Test Program. The-l Nuclear Operations organization (i.e. Manager, I
Startup) was responsible for the preoperational test program. The Nuclear Engineering and Support i
organization (i.e., Manager, Maintenance Engineering) is responsible for the initial startup test program.
l Change Request Number
- SA-92-839.2 i
Commitment Register Number :
Related SER : 13.1 SSER :25 13.1 l
SER/SSER Impact
- No l
13.1-3 4
See Sheet No(s) :04 thru 12 Updates the Nuclear Production Group's management f
and technical support organization descriptions to reflect the new organization structure.
All previously assigned responsibilities and duties have been reassigned to appropriate positions within the new organization structure in a manner that assures that the individual in each position has the authority and experience needed to properly perform the assigned functions. Those positions associated with construction activities have been deleted as part of the destaffing and transition to dual operating units.
Update Section 13.1.1.2 has been updated to reflect the position title change from " Group Vice President, j
Nuclear Engineering and Operations" to
" Group Vice President, Nuclear Production."
t
Attachment to TXX-93149 April 16, 1993 Page 32 of 45 Prefix Page (as amended)
GrouD Description Section 13.1.1.2.1 has been updated to reflect the following changes:
The position title "Vice President Nuclear Operations" has been changed to "Vice President of Nuclear Operations" who has assumed the responsibilities of the Plant Manager.
The positions of Plant Manager: Manager, Startup; and Manager, Plans and Projects have been deleted.
The Manager, Nuclear Training now reports to the Director of Nuclear Overview.
The Manager, Operations: Manager, Maintenance; Radiation Protection Manager; Manager, Work Control; and the Manager, Plant Support now report directly to the Vice President of Nuclear Operations.
Section 13.1.1.2.2 has been updated to reflect the following changes:
The organization title " Engineering and Construction" has been renamed " Nuclear Engineering and Support."
The position of "Vice President of Nuclear Engineering and Support" has been added which assumes the responsibilities of the Chief Engineer -
Department of Engineering and the Vice President, Support Services.
The positions of Senior Vice President: Unit 2 Project Manager: Manager, Material Management: Chief Engineer: Mar ager, Unit 2 Engineering: Manager, Plant Engineering: and Vice President, Support Services no longer exist in the new organizational structure and have been deleted.
The position title " Manager of Design Engineering" has been changed to " Manager of Tecnical Support and Design Engineering" who reports directly to the Vice President of Nuclear Engineering and Support.
i The Manager of Tecnical Support and Design Engineering has assumed additional responsibilities Site Facility, Environmental, Project, Maintenance, Procurement and System Engineering.
The position title of " Director of Reactor Engineering" has been changed to " Manager of Reactor Engineering" who reports directly to the Vice President of Nuclear Engineering and Support.
l The description of responsibilities for the Manager, l
Administrative Services has been removed from l
Section 13.1.1.2.2 because this position does not perform a safety function and does not need to be in the FSAR.
The description for the Nuclear Engineering organization (old Section 13.1.1.2.3) has been deleted. These responsibilities have been reassigned to the Manager of Regulatory Affairs, the Director of Nuclear Overview and the Manager of
(
Reactor Engineering.
Attachment to TXX-93149 April 16, 1993 Page 33 of 45 Prefix Page (as amended)
Group Description Section 13.1.1.2.3 has been reassigned to the Regulatory Aff airs organization. The Manager of Regulatory Affairs now reports directly to the Group Vice President, Nuclear Production.
Section 13.1.1.2.4 has been reassigned to the Nuclear Overview organization with the following changes:
The Director of Nuclear Overview now reports directly to the Group Vice President, Nuclear Production.
The responsibility of the Director of Nuclear Overview to provide " Corporate Health Physics support" has been revised to " Health Physics review" since the Corporate Health Physics group has been dissolved.
The Manager, Nuclear Training now reports to the Director of Nuclear Overview.
The Manager, ISEG reviews plant activities and makes recommendations to the Director of Nuclear Overview.
The position of Manager, Construction Quality Control no longer exists in the new organizational structure and has been deleted.
The position title of " Plant Analysis Manager" has been changed to " Manager, Plant Analysis."
The Support organization no longer exists in the new organizational structure. The responsibilities described for the Vice President, Support (old Section 13.1.1.2.4) have been assumed by the Vice President of Nuclear Engineering and Support.
Change Request Number
- SA-92-839.3 Commitment Register Number :
Related SER : 13.1 SSER :25 13.1 SER/SSER Impact
- Yes Section 13.1 should be updated to reflect the current organizational structure.
13.1-12 4
See Sheet No(s) :13, 15 thru 18 Updates Nuclear Production's operating organization description.
Update Section 13.1.2 has been updated to reflect the current management and additional support organizations as described in revised Section 13.1.1.2.1.
Sections 13.1.2.1.2 and 13.1.2.1.5 have been updated to reflect that the Shift Operations Managers and the Chemistry Manager now reports to the Manager, Operations. The position title " Chemistry and Environmental Manager" has been changed to
" Chemistry Manager." Environmental responsibilities have been reassigned to the Civil / Site Facility / Environmental Engineering staff which reports to the Manager of Technical Support and b
Attachment to TXX-93149 April 16. 1993 Page 34 of 45 Prefix Page (as amended)
Group Description Design Engineering.
Section 13.1.2.1.3 has been updated to indicate the position title change from "Intrumentation and Control Manager" to "I&C Maintenance Manager" and j
provide a description ~for the new Construction / Operations Maintenance Support Group l
(C0SG).
Section 13.1.2.1.4 has been revised to add the words
" post processing" to clarify the Radiation Protection Department responsibilities with respect to handling, packaging, and storage of radioactive waste. This change makes the FSAR consistent with i
Revision 2 of the Process Control Program.
Change Request Number
- SA-92-839.4 Commitment Register Number :
Related SER : 13.1 SSER :25 13.1 SER/SSER Impact
- Yes i
Section 13.1 should be updated to reflect the.
current organizational structure.
Table 13.1-1 4
See Sheet No(s) :01 and 02 Update Table to reflect the new position titles in the current CPSEF organizational-structure.
Update The position titles indicated in the Table have been updated as +0llows to reflect the CPSES organization structure ce ;cribed in Section 13.1.
The position title " Plant Manager" has been changed to "Vice President of Nuclear Operation." The Plant Manager position has been deleted and its responsibilities have been assumed by the Vice i
President of Nuclear Operations.-
l The position title "Intrumentation & Controls Manager" has been changed to "I&C Maintenance Manager."
l The position title " Manager, Plant Engineering" has l
l been changed to " Manager of Technical Support and Design Engineering." The position of Manager, Plant Engineering has been deleted and its j
responsibilities assumed by the Manager of Technical l
Support and Design Engineering.
The position titles " Chemistry and Environmental Manager." " Chemistry and Environmental Supervisor."
l and " Chemistry and Environmental Technician" have been changed to " Chemistry Manager." " Chemistry Supervisor," and " Chemistry Technician,"
respectively. The Environmental responsibilities i
have been assumed by the Manager of Technical Support and Design Engineering.
The position of " Manager, Startup" has been deleted as part of the destaffing and transition to dual i
operating units. The activites associated with l-power ascension testina are being performed under l
Attachment to TXX-93149 April 16, 1993 Page 35 of 45 l
l l
i Prefix Page (n amended)
Group Description j
i the Manager. Maintenance Engineering who reports to the Manager of Technical Support and Design j
Engineering.
l Change Request Number
- SA-92-839.13
{
~
Cominitment Register Number :
Related SER : 13.1 SSER :25 13.1 SER/SSER Impact
- No Figure 13.1-1 4
Updates description of the TU Electric corporate l
organizational structure.
f Update' See Description for p. 13.1-1.
t Change Request Number
- SA-92-839.5 l
Commitment Register Number :
Related SER : 13.1 SSER :25 13.1
[
SER/SSER Impact
- Yes l
Section 13.1 should be updated to reflect the l
l current organizational structure, j
Figure 13.1-2 4
Updates the Nuclear Production Group organizational description.
i I
Update See Descriptions for pp. 3 thru 21.
Change Request Number
- SA-92-839.6 Commitment Register Number :
Related SER : 13.1 SSER :25 13.1
[
SER/SSER Impact
- No I
Figure 13.1-3 4
Updates description.of the Station Organization.
?
Update See Description for pp. 13.1-15 thru 21.
Change Request Number
- SA-92-839.7 l
Commitment Register Number :
Related SER : 13.1 SSER :25 13.1 l
SER/SSER 1mpact
- No l
13.1A-1 4
See Sheet No(s) :02 thru o9 Section 13.1A has been updated to reflect the personnel changes in the Nuclear Production Group as a result of the reorganization desribed in Section 13.1.
I Change Request Number
- SA-92-839.8 i
Commitment Register Number :
}
Related SER : 13.1 SSER :25 13.1 SER/SSER Impact-
- No i
13.2-11 4
See Sheet No(s) :-12, -13 & -14 Revises training program description for "non-licensed operators" to differentiate between J
auxiliary and radwaste operators.
Clarification :
)
Changes to the description of the auxiliary and radwaste training program are made in response'to 0A-l
l Attachment to TXX-93149 l
April 16, 1993 Page 36 of 45 Prefix Page (a1 amended)
Group Description audit 0AA-92-125. Change enhances description of auxiliary and radwaste operator training program by distinguishing between the two functional positions.
Change Request Number
- SA-92-835.1 Commitment Register Number':
Related SER : 13.2 SSER :22 13.2.1 SER/SSER Impact
- No 13.2-13 3
Deletes system observation training in the non-licensed operator training program.
I Revision The system observation training program is being replaced with enhanced on-the-job training program descriptiens designed for auxiliary operators' and i
radwaste operators' specific tasks.- Deletion ~of
{
system observation training is consistent with
" Guidelines for Training and Qualification of l
Nonlicensed Operators," National Academy for Nuclear l
Training.
Change Request Number
- SA-92-835.3
{
Commitment Register Number :
i Related SER : 13.2 SSER :22 13.2.1 SER/SSER Impact
- No l
.i 13.2-13 3
Deletes on-the-job training in the radwaste systems area for auxiliary operators.
Revision Radwaste operators will receive on-the-job training in the radwaste systems area instead of auxiliary operators. This enhances the non-licensed operator program since the training program designates a i
non-licensed operator specifically for radwaste tasks.
Change Request Number
- SA-92-835.4 Commitment Register Number :
i Related SER : 13.2 SSER :22 13.2.1 SER/SSER Impact
- No i
t 13.2-13 3
Adds description of radwaste operators' on-the-job training program which includes training in radwaste areas Addi tion Addresses the self-paced and classroom training portion of the radwaste operator' training program, which is consistent with guidance in NUREG-0800.
Change Request Number
- SA-92-835.5 Commitment Register Number :
Related SER : 13.2 SSER :22 13.2.1 SER/SSER Impact
- No 13.2-15 4
Deletes "three-week" before " General Plant Information Course".
Correction
l f
Attachment to TXX-93149 April 16, 1993 Page 37 of 45 i
i Prefix Page (n amended)
Group Descriotion l
Though the General Plant Information Course is still i
I given, it does not last exactly three weeks.
Change Request Number _
- SA-92-835.6
'l Commitment Register Number :
Related SER : 13.2 SSER :22 13.2.1 SER/SSER Impact
- No l
l r
13.2-23 4
See Sheet No(s) :24 i
i Revises training program description for "non-licensed operators" to differentiate between i
l auxiliary and radwaste operators.
Clarification Changes to the description of the auxiliary and l
radwaste training program are made in response to OA t
l audit 0AA-92-125.
Change enhances desciiption of l
auxiliary and radwaste operator training program by distinguishing between the two functional positions.
i Change Request Number
- SA-92-835.2 Commitment Register Number : TR-0024 l
Related SER : 13.2 SSER :22 13.2.1 I
SER/SSER Impact
- No Figure 14.2-3 4
See Sheet No(s) :1 References 0423.10 at the applicable portions of the i
figure identifying the response to NRC question.
Editorial 0&R response is revised to reference the figure.
Change Request Number
- SA-92-535.2 T
Commitment Register Number :
Related SER :
SSER :22 14 SER/SSER Impact
- No Figure 14.2-4A 4
References 0423.10 at the applicable portions of the figure identifying the response to NRC question.
Editorial Q&R response is revised to refer to the figure.
Change Request Number
- SA-92-535.3 l
Commitment Register Number :
i Related SER :
SSER :22 14 SER/SSER Impact
- No Figure 14.2-4B 4
References 0423.10 at the applicable portions of the figure identifying the response to NRC question.
Editorial 0&R response is revised to refer to the figure.
Change Request Number
- SA-92-535.4 Commitment Register Number :
Related SER :
SSER :22 14 SER/SSER Impact
- No 15.0-14 4
See Sheet No(s) :28 Adds description from 0232.3 response to the FSAR text and adds reference from 0232.3 response to FSAR
Attachment to TXX-93149 April 16. 1993 Page 38 of 45 Prefix Page (as amended)
Group Description Section 15.0 References.
Editorial These changes appropriately incorporate the response to 0222.5 into the pertinent FSAR text.
Change Request Number
- SA-92-241.1 Commitment Register Number :
Related SER : 15.1.1 SSER :22 15.1.1 SER/SSER Impact
- No 15.1-21 4
See Sheet No(s) :26, 32 Adds description from 0222.5 response to the FSAR l
text.
t Editorial l
Q&R response is revised to reference the FSAR l
text.
Change Request Number
- SA-92-222.2 Commitment Register Number :
Related SER : 15.3.5 SSER :24 15.3.5 SER/SSER Impact
- No 15.1-32 4
Changes the description for reference 5 to clearly identify the documents.
Editorial
.The revised Reference 5 provides the correct title of the report.
Change Request Number
- SA-92-222.3 Commitment Register-Number :
Related SER : 15.3.5 SSER :24 15.3.5 SER/SSER Impact
- No 17.1-2 2
Section 17.1. Quality Assurance During Design and Construction. has been deleted in its entirety.
Revision FSAR Section 17.1. Quality Assurance During Design and Construction, has been deleted in its entirety to reflect the transition from construction to operations phase for CPSES Unit 2.
All descriptions of the current TV Electric corporate and site organizations and personnel responsibilities and duties have been updated and are discussed in Sections 13.1 and 17.2 (e.g.
Figure 17.1-1 has been replaced by current Figure 13.1-1).
Change Request Number
- SA-92-839.9 Commitment Register Number :
Related SER : 17.1 SSER :22 17.1 SER/SSER Impact
- Yes Section 17 should be updated to reflect the current organizational structure.
17.2-1 4
See Sheet No(s) :02 - 06. 08. 11 - 14, 25, 35, 37, 38 Updated description of the CPSES organizational structure to provide consistency with the Section 13~.1 organizational updates.
j i
r l
Attachment to TXX-93149 April 16, 1993 i
Page 39 of 45 i
l Prefix Page (n amended)'
Srggg Description Update Section 17.2 has been updated to provide consistency i
with the organizational changes described in FSAR l
Section 13.1.
Section 17.2.1 has been updated as follows:
{
"NE0" has been changed to " Nuclear Productions Group."
i The position title " Group Vice President, Nuclear Engineering and Operations" has been changed to
" Group Vice President, Nuclear Production."
l The position of " Senior Vice President" has been deleted.
The new position of "Vice President of Nuclear Engineering and Support" has been added with overall responsibility for implementation of the QA program for the " Nuclear Engineering and Support" function at CPSES.
[
The position title "Vice President, Nuclear Operations" has been changed to "Vice President of Nuclear Operations" with his updated duties and reponsibilities as described in Section 13.1.
The position of " Plant Manager" has been deleted with its responsibilities assumed by the Vice President of Nuclear Operations.
The duties and responsibilities of the Director of Nuclear Overview has been updated to include Nuclear Training.
The Nuclear Overview Department now provides the j
function of " Health Physics review" since the Corporate Health Physics group has been dissolved.
The position title of " Plant Analysis Manager" has been changed to " Manager, Plant Analysis."
-t Section 17.2.3 has been updated as follows:
The Vice President of Nuclear Operations shall have the responsibility for approving and controlling the
[
implementation of station design modifications.
t The Vice Presidient of Nuclear Engineering and Support shall have the overall responsibility for l
developing procedures to maintain and control the design control process; he has absorbed the responsibilities of fuel-related design control process.
The position of " Chief Engineer" has been deleted and those responsibilities assumed by the Vice President of Nuclear Engineering and Support.
Section 17.2.18 has been updated to reflect the current organizational structure.
Change Request Number
- SA-92-839.10 Commitment Register Number :
Related SER : 17.2 SSER :22 17.2 t
SER/SSER Impact
- Yes Section 17 should be updated to reflect the current organizational structure.
Attachment to TXX-93149 April 16, 1993 i
Page 40 of 45 I
Prefix Page (Al Amended)
Group Description f
i Figure 17.2-1 4
Provides Figure to reflect current organizational i
structure.
Update Figure 17.2-1 was deleted in a previous amendment i
and a reference added to see Figure 17.1-6 for the organizational structure information. However.
since Section 17.1 has been deleted in its entirety.
Figure 17.1-6 has been renumbered to Figure 17.2-1 l
and updated to reflect the current organizational structure as described in Section 13.1.
Change Request Number
- SA-92-839.11 Commitment Register Number :
Related SER : 17.2 SSER :22 17.2
{
l SER/SSER Impact
- No j
l Figure 17.2-2 4
Updates Figure to reflect current organizational l
structuure.
Update i
Figure 17.2-2 has been updated to reflect the
. current organizational structure as described.in l
Section 13.1.
i Change Request Number
- SA-92-839.12 Commitment Register Number :
Related SER : 17.2 SSER :22 17.2 SER/SSER Impact
- No Table 17A-1 1
See Sheet No(s) :50 j
Add Note 81 to List of Quality Assured Structures.
I Revision The specific exception concerning the Heater Drain piping in the Turbine Building has been added to j
Table 17A-1 via Note 81.
The. quality assurance requirements for this piping will be the same as for any Class 5, Seismic Category'II piping except that.
i the piping is not located in a Seismic Category I structure.
Change Request Number
- SA-93-4.4 Commitment Register Number :
Related SER :
SSER :
j SER/SSER Impact
- No i
Table 17A-1 1
See Sheet No(s) :60 Revises Note 81 to List of Quality Assured Structures, Systems and Components.
Revision Revises note 81 to indicate that there is more than one piping segment located in the Turbine Building which is designated class 5 piping and classified as Seismic Category II even' though located in a non-seismic building. The applicable piping segments are listed in Section 3.7B.2.8.
Change Request Number
- SA-93-4.5
~
Attachment to TXX-93149
-April 16, 1993 i
Page 41 of 45 f
Prefix Page (11 amended)
Group DescriDtion i
Commitment Register Number :
Related SER :
SSER :
I SER/SSER Impact
- No i
III.A-3 3
In the CPSES response to the NRC Action Plan (on l
NUREG-0654) delete reference to a consultant'and t
reflect Emergency Planning assistance to Federal,
[
State and local officials being provided by TU i
Electric.
}
Revision A full time TV Electric employee has been hired to provide planning assistance to Federal, State and local officials on the CPSES Emergency Plan.
Change Request Number
- No l
0&R 022-34 4
O&R 022.9: Statement specifying the uncertainty accounted for in the difference in zinc paint and galvanized steel corrosion rates is moved to Section 6.2.5.3.1.
Statement summarizing the approximate surface area in Containment that is zine related and-paragraph discussing corrosion data (and the associated reference) are deleted.
A reference to Section 6.2.5.3.1 and Table 6.2.5A-3 is added.
4 Q&R Incorporation :
l This is an editorial change to ready the Q&R Section '
l for deletion when the updated FSAR is' prepared.
Section 6.2.5.3.1, which covers corrosion in l
Containment, is the appropriate place to relocate the statement on corrosion rate uncertainty. The statement summarizing the approximate surface area in Containment that is zine related is unnecessary l
as revised Table 6.2.5A. has specf fic information j
on the source, weight and surface area of zinc and 4
aluminum related structures and equipment in i
Containment. The paragraph discussing corrosion rate data (and reference) is deleted since this topic (and reference) is'more thoroughly addressed in Section 6.2.5A.
Change Request Number
- SA-92-46.1 Commitment Register Number :
Related SER : 6.2.4 SSER :24 6.2.4 SER/SSER Impact
- No Q&R 040-140 4
0&R 040.105: Discussion on the effects of Turbine Bypass system malfunctions on Turbine-Generator and Reactor is moved to Section 10.4.4.3.
Discussions on transient response due to postulated failed open single and multiple steam dump valves are deleted.
A reference to Sections 10.4.4.3, 15.1.4 and 15.1.5 is added.
I
-~
e-e Attachment to TXX-93149 l
April 16. 1993
)
Page 42 of 45 l
l Prefix Page (As amended)
Argus p_essription 0&R Incorporation :
i This is an editorial change.to ready the O&R Section i
for deletion when the updated FSAR is prepared.
l Section 10.4.4.3 contains Safety Evaluation information relating to the Steam Dump system and is the appropriate place to relocate the discussion on l
the effects of Turbine Bypass system malfunctions on l
the Reactor and Turbine-Generator.
Discussion on j
transient response due to one failed open steam dump f
is covered in recently revised Section 15.1.4.
The transient response due to multiple failed open steam j
dumps is bounded by the Steam system piping failure analysis (because the steam dump valves are downstream of the Steam Generator outlet nozzle flow restrictors which would limit the steam dump flow to l
1ess than or equal to that in a Steam Line Break Event) which is provided in Section 15.1.5.
Thus i
the information on steam dump failure transient response in the Q&R can be deleted.
Change Request Number
- SA-92-174.1
}
Commitment Register Number :
i Related SER : 15.2.1 SSER :23 15.2.1 SER/SSER Impact
- No I
0&R 212-71 4
See Sheet No(s) :72
{
Deletes the information contained in the response to Q&R 212.39 and adds references to the related FSAR Section 6.3.2.8 and Table 6.3-7.
}
Q&R Incorporation :
This is an editorial change to ready the 0&R Section i
for deletion when the updated FSAR is prepared.
In this case, information on operator actions.
applicable alarms and associated time for operator i
actions relative to ECCS actuation / operation is l
adequately discussed in section 6.3.2.8 and Table 6.3-7.
The information in this response is thus repetitive and can be deleted, i
Change Request Number
- SA-92-390.1 Commitment Register Number :
Related SER : 6.3.3 SSER :1 6.3.3 SER/SSER Impact
' No 0&R 222-6 4
Replaces O&R response to 0222.5 by referencing the pertinent FSAR text.
Editorial This change prepares the O&R section for deletion when the USAR is submitted.
Change Request Number
- SA-92-222.4 Commitment Register Number :
Related SER : 7.2.1 SSER :22 7.2.1 SER/SSER Impact
- -No O&R 232-3 4
Replaces the response to 0232.3 by referencing the-
Attachment to TXX-93149 April 16, 1993 Page 43 of 45 l
Prefix Page (n amended) gr_ou3 DescriDtion FSAR text. where the information is discussed.
Editorial I
This change relocates the information into the FSAR l
-text in preparation for the Updated Safety Analysis j
Report (USAR).
Change Request Number
- SA-92-241.2-Commitment Register Number :
Related SER : 15.1.1 SSER :22-15.1.1 i
SER/SSER Impact
- No i
Q&R 312-20 4
Replaces response to 0312.18 by referencing the l
pertinent sections of the FSAR text.
Editorial This change prepares the Q&R section for deletion when the USAR is submitted.
Change Request Number
- SA-92-273.1-Commitment Register Number :
i Related SER : 15.4.1 SSER :22 15.4.1 SER/SSER Impact
- No j
Q&R 362-21 4
Replaces the response to NRC question by referencing the applicable FSAR figures, i
Editorial This change is made to ready the O&R section for l
deletion when the USAR is prepared.
i Change Request Number
- SA-92-448.
l Commitment Register Number :
Related SER :
SSER :22 2.5 i
SER/SSER. Impact
- No i
0&R 421-38 4
Deletes response and adds a note to see Sections 17.2.10 and 17.2.12.
l O&R Incorporation :
This is an editorial change to ready the O&R Section l
for deletion when the Updated FSAR is prepared. The l
existing FSAR Sections 17.2.10 and 17.2.12 adequately describe the provisions regarding the calibration, accuracy and use of M&TE utilized in the accomplishment of quality related activities.
Thus, the response can be deleted.
Change Request Number
- SA-92-514.1 Commitment Register Number :
Related SER :
SSER :
SER/SSER Impact
- No Q&R 421-40 4
Deletes response and adds note to see Sections 17.2.5 and 17.2.10..
Q&R Incorporation :
This is an editorial change to ready the 0&R Section for deletion when the Updated FSAR (USAR) is prepared. The existing FSAR Sections 17.2.5 and 17.2.10 contain information which describes the provisions of the 0A Program regarding the
~
I Attachment to-TXX-93149 April 16, 1993 I
Page 44 of 45 Prefix Page (as amended)
Sroun Description
]
ru establishment of mandatory quality control inspection hold points in the accomplishment of e
quality related activities. Thus, this response can be deleted.
Change Request Number
- SA-92-517.1 Commitment Register Number :
.}
Related SER :
SSER :
l SER/SSER Impact
- No j
Q&R 421-48 4
Deletes response and inserts reference to see Section 17.2.
0&R Incorporation :
This is an editorial change to ready the Q&R Section for deletion when the Updated FSAR is prepared. The portion of the response dealing with the design and j
construction phase is no longer applicable to CPSES.
i Section 17.1 is being deleted in its entirety by I
Amendment 88.
The remaining information in the l
respon:;e which concerns OA Management involvement in i
the review and concurrence of the QA Program and I
qualification criteria for personnel performing examinations, inspections and tests, is adequately addressed by pertinent subsections of Section 17.2 (see 17.2.1.1.3, 17.2.1.3, 17.2.1.5, 17.2.2, 17.2.9 j
and 17.2.10).
Thus, this response may be deleted.
Change Request Number
.: SA-92-523.1 l
Commitment Register Number :
l Related SER :
SSER :
f SER/SSER Impact
- No i
0&R 423-19 4
Replaces the response to NRC question by referencing the applicable FSAR figures.
Editorial j
This change is made to ready the Q&R section for l
deletion when the USAR is prepared.
Change Request Number
- SA-92-535.1 l
Commitment Register Humber :
l Related SER :
SSER :22 14 SER/SSER Impact
- No O&R 423-65 4
Replaces 0&R response to NRC question 423.34 by referencing the appropriate FSAR text.
Editorial This change is made to ready the 0&R section for deletion when the USAR is prepared.
Change Request Number
- SA-92-551.1 Commitment Register Number :
Related SER :
SSER :22 8.2.1 SER/SSER Impact
- No 0&R 500-2 4
Add note to R500.1 to indicate that this response will not be incorporated into the FSAR text as part of the O&R relocation for the Updated Safety-i-
i Attachment to TXX-93149 April 16. 1993 Page 45 of 45 Prefix Page (as amended)
GrouD Description Analysis Report (USAR).
Editorial The information contained in R500.1 is already included in the Security Plan.
Change Request Number
- SA-92-562.
Commitment Register Number :
Related SER : 13.1.6 SSER :22 13.1.6 SER/SSER Impact
- No i
l