U-602804, Forwards Addl Info in Response to 970730 RAI Re Review of Application for Temporary Partial Exemption from 10CFR50,App a General Design Criterion 17 & Amend to License NPF-62

Forwards Addl Info in Response to 970730 RAI Re Review of Application for Temporary Partial Exemption from 10CFR50,App a General Design Criterion 17 & Amend to License NPF-62

ML20151J321
Person / Time
Site:	Clinton
Issue date:	08/01/1997
From:	Romberg W ILLINOIS POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
U-602804, NUDOCS 9708050134
Download: ML20151J321 (43)

Text

08/01/97 13:19 CPS *LICENSitG -+ LIC PROJECT MGR NO.391 D01

, Ilknor$ Powter Company i Chnton Power St hori P o HonC78 ,

Chnton. LL 61727 I Tel 217 935-6220 (

Fax 217 935 4632 ILLIN l PgT Wayne o. Rornberg Assistant Wt.e PresO4nt Nwear l

m., m= c.meww __

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• • '* ID*N$ RE.100a Post-it' Fu Note

,No AeIM i w % G7w'eo cl August 1,1997 c* Y I

co m f/ y ,.6, O I3 D I enon ug tHS I 3 (s 's' AI IS

v. e 10CFR50.12 Docket No. 50-461 10CFR50.90 Document Control Desk l Nuclear Regulatory Commission l Washington, D.C. 20555 l l

Subject:

Response to Request for AdditionalInformation to Support Review of Application for Temporary Partial Exemption from 10CFRSO Appendix A General Design Criterion 17 and Amendment of Facility Operatina License No NPF-62 for Clinton Power Station l

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Dear Madam or Sir:

By letter dated July 22,1997 [ Illinois Power (IP) letter U-602796), IP submitted a combined application for amendment of the Clinton Power Station (CPS) Operating l License (No. NPF-62) and a panial, temporary exemption from 10CFR50 Appendix A l General Design Criterion 17, " Electric Power Systems". The request was submitted in response to the determination that, for intermittent periods of time during the current summer, voltage on one of the two required offsite electrical power sources for CPS may not be able to be maintained above the mimmum required value conservatively established for CPS. This condition is attributed to the current lack ofoperating generators in Illinois coupled with high load demands during peak hours, and IP's imposition of a more conservative philosophy regarding offsite source capacity and I capability resulting from the resolution of related technicalissues during the current lj refueling outage. pQ The proposed exemption / amendment, which would only be effective through and including October 15,1997, would permit plant stanup and continued operation with one of the two offsite electrical source circuits experiencmg intermittent periods of less than the minimum required voltage, as determined by actual readings (when the f()p[,

h) plant is offline) or by a model that predicts (with thi, plant online) when voltage would be inadequate in the event of a plant trip. NRC review and approval of the request was f{

l respectfully requested to be completed in time to suppon CPS startup from the current I refueling outage, which is now scheduled for August 4,1997.

Y 9708050134 970801

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• LIC PROJECT MGR NO.391 D02

. l DRAFT Subsequent to submittal of P's application, several telephone discussions were

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conducted between F and NRC staff personnel to support NRC review of the application.

Additional information was provided, including the information provided in F letter U-602798, dated July 23,1997. However, two events recently occurred that potentially .

impacted thejustification and acceptability ofIP's request. The two events were (1)  !

completion ofIP's initial effort to address the concern that, due to design limitations on _

the diesel generator room cooling subsystems, adequate cooling capability may not be able ,

to be provided to support operability of the generators if outside air temperatures exceed  :

levels that are not improbably high for the summer season, and (2) failure of the Westinghouse 4160-volt 1 A1 bus mein feed breaker to trip wh:le loads were being transferred from the reserve auntiary transformer (associated with the offsite 345-kV ,

system power source) to the emergency reserve auxiliary transformer (associated with the j alternate offsite 138-kV system power source). [The latter was first described in IP letter U-602799 to Mr. A. Bill Beach, dated July 25,1997.] l l

In light of the above events, and after further consideration ofIP's application, the NRC staff has identified three separate concerns that involve high temperatures being a I potentially common causal factor:

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(1) High temperaturas increase load on the grid and may thus prevent either' or both the 138-kV and 345-kV offsite sources from meeting minimum established voltage limits  !

l (2) High temperatures may apparently result in the onsite diesel generators being declared inoperable due to inadequate room cooling capability.

(3) The prediction of high temperatures may result in requiring a transfer between the 345-kV and 138-kV sources, which is a concern in light of the recent failure of the Westinghouse 4160-volt breaker to fully trip while operators were performing such a transfer.

The above concems were identified by the NRC in a request for additional information that was transmitted to CPS via telecopy on July 30,1997. In that request, and to support the NRC's review ofIP's application, F was asked to provide responses to a list ofitems related to the NRC's concerns Pr@=ir=y, verbal responses to these items were provided to NRC staff personnel in a telephone conference conducted on July 31,1997. IP's response to each item is provided in the attachment to this letter.

As noted in the emes =% IP is re-evaluating the air inlet temperature limits recently established for the diesel generator (DG) room coormg sutisystems. Preliminary evaluation has determined additional margin exists to provide reasonable assurance that, for an air inlet temperature of greater than 1039, the subsystems will function adequately to maintain operability of the diesel generators, including all required components and instrumentation within the DG rooms. According to National Oceanic and Atmospheric Adrainistration data,103T represents the highest extreme temperature recorded for the last 50 years for this area for any day within the period that the requested exemption will be in effect (i.e., from the beginning of August until the middle of October). This resolves j

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the concern regarding the impact of high temperatures on DG reliability, thus eliminating the concern for high temperatures being a common causal factor that could lead to a degradation or failure of the offsite electric power supplies concurrent with a degradation

! or failure of the onsite electric power supplies.

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With respect to the concern about high temperatures increasmg load on the grid and preventing either or both of the offsite power sources from meeting established minimum vokage limits, IP understands the NRC's particular concem for both sources potentially becoming degraded (concurrently) with respect to voltage, as expressed in

telephone discussions with the NRC regarding IP's request. IP has previously described (in its application letter and in its July 23,1997 follow-up letter) what actions can be taken to recover voltage or prevent voltage from decreasing below the minimum required level i in the unhkely event that voltage for the 138-kV system decreases or is predicted to j decrease below the required minimum, concurrent with low voltage on the 345-kV j system. IP wishes to emphanin that it will take whatever actions are necessary, including i curtailing service to customers, to maintain the capability and capacity of the 138-kV

! system as a reliable source of offsite power to CPS.

Finally, with respect to the concern about transferring plant safety loads from one

offsite source to another, with consideration given to the recent breaker failure, IP has

! addressed the failure of the 1 A1 bus breaker in a separate letter (IP letter U-602803 to A.

j Bill Beach, dated August 1,1997). It should be noted that if this breaker or one in similar

service had failed in the same manner while attempting to manually transfer loads from one i source to the other during plant operations, a plant trip would not be expected to occur.

Recovery from such a condition would be handled by transferring the other divisional I power supplies to the available source and then removing the power supply to the failed l

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breaker. Once power was removed, the breaker could be removed from service and the remaining loads transferred to the available source. To repeat, availability of the alternate j source would be unaffected by such a failure, and no plant trip would be expected to occur.  !

IP's position regarding the breaker failure event is that it was an isolated l l occurrence and does not involve a significant increase in the probability of a failure to I j transfer plant safety loads from one offsite source to the other when desired (manually) or automatically on demand However, IP is taking compensatory measures to ensure that

4160 breakers are in the correct position (i.e., full open or full closed) following breaker operation, thus assuring they are ready and able to perform their next operation.

j Notwithstanding, as further explained in the an= Ament, IP has adopted the policy that, j during the period the requested exemption is in effect, plant loads will normally be aligned to the emergency reserve auxiliary transformer (associated with the'138-kV system) unless projections indicate a prolonged period of mild weather. The number ofload transfers will thus be kept to a minimum and is expected to be less than or equal to four per month.

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DRAFT IP believes the information provided herein and in the attached resolves all remaining concerns regarding the exemption / amendment request. It is therefore our hope that receipt of this letter will support completion of the NRC's review and approval of l IP's request in time to permit plant startup on August 4,1997 Sincerely yours, I

Wayne D. Romberg Assistant Vice President TBFJkrk Attachment / Enclosures i cc: NRC Clinton Licensing Project Manager CPS Restart Manager, Region III, USNRC NRC Resident Office, V-690 Regional Administrator, Region III, USNRC Illinois Department ofNuclear Safety j l

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Pase 1 af 8 l l In the telecopy provided to Illinois Power on July 30,1997, the NRC provided a list of i eight itema to be addressed by Illinois Power (IP). IP's response to each item is provided i below:

(1) Temperature history and statistics surrounding the site need to be docketed.

Temperature profiles for August and September need to be projected. Describe any correlation between ambient temperatures at the site and in the region and load 4

on the grid.

IP Response i

j Enclosure 1 provides selected pages from the 1985 National Oceanic and l Atmospheric Administration (NOAA) report, " Local Climatological Data," for 1

Springfield, Illinois. The table entitled, " Normals, Means, and Extremes," is j provided. NOAA speci6es the mtximum temperature for August as 103*F which

! occurred in 1964, and 101*F for September, which occurred in 1984. Enclosure 2

provides the 1956 Weather Bureau Local Climatological Data report for Spring 6 eld,111inois. Review of the same table in that report shows that extremes are carried from 1948 on, indicating data prior to that time was not considered for

] usein providing extremes.

1 Enclosure 3 to this section consists of several attachments providing additional j data and/or the results ofIP's evabation of data. This data provides reasonable i

assurance that it is unkkely for temperature to exceed 103' at CPS during August.

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Although the effective period for the proposed exemption is from i the date of NRC approval until (and including) October 15,1997, i

much of the temperature data provided in Enclosure 3 covers only l i the months of August and September. Data for October was l

{ excluded on the basis that the August and September maximum '

temperatures bound the maximum temperatures expected or recorded for October.

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With regard to temperature proSles for August and September, the table on page 1 ofEnclosure 3, and the graph on Attachment 1 of Enclosure 3, provide data that characterize the temperature profiles for these months. The table gives the number of occurrences when the maximum temperature exceeded, say,100*F in August and September, over the years 1930 to 1995. The graph depicts the daily mean

! maximum temperature for August and September (and all other months), as well 1

as the extremes for each day during those months, based on the years from 1961 to 1990.

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Page 2 af s '

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1 With respect to any correlation between ambient temperatures at the site and in the

region, and load on the grid, the infonnation provided in Enclosure 4 is provided.  ;

That information includes a plot of transmission voltage (for both the 345-kV and 138-kV circuits), system load and ambient temperature versus time for an ,

arbitrarily chosen, recent 24-hour period (July 14-15,1997).. Plots ofmean system

} load for 24-hour periods, mean system load versus days of the week, and mean i

system load by month are also included. These plots are based on an IP study

, using 1993-1995 data.

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With further regard to any correlation between ambient temperatures and system l l load or transmission system voltage, ambient temperatures and weather conditions i have been shown to have a good correlation to system grid loading. For summer  !

time temperature ranges, the major temperature-dependent load contribution is i from air conditioning. l

1 Many factors affect the load on the system, such as ifit is a weekday or weekend,

if factories are shut down, time of day, if school is in session or not, new customer loads, and temperature. The system load is responsive to both heating and cooling

loads. As the temperature increases in the summer and customers tum on air conditioning and other cooling equipment the system load increases as the temperature increases. As the temperature reaches higher temperatures (e.g., '

100*F to 101*F), the system load is less influenced by temperature increases because the air conditioning load is mnning almost constantly. 1 The system voltage and temperature do have some correlation, but not e--ily j

, a direct correlation. The increase in temperature in the summer will cause the load l to increase and as a result cause additional voltage drop on the system. As the voltage on the system drops, the dispatcher will manage the voltage on the system by connecting capacitor banks and having power plants supply VARs to the system l to help compensate for the voltage drop that the load increase may have caused.

There are many other factors on the system that can cause voltage changes that are not related to temperature such as transfer of power across the power grid, generating unit outages, and line outages.

Additional Item IRenardina Item (111 During the discussion ofItem (1) in the telephone conference conducted between IP and NRC personnel on July 31,1997, the NRC requested that IP also provide projected monthly reserve margins for the effective period (beginning of August through October 15). This informstion is provided (on a per-week basis) in tabular form in Enc,losure 5. Please note that the information provided in Enclosure 5 is considered proprietary.

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Page 3 of 8 1

i (2) Describe the conservatism's in the temperature analysis for the diesel generator rooms.

i IP Response

h diesel generator room temperature analysis performed per calculation IP-M-0448 determined the hourly temperatures in the diesel generator rooms over a 24-hour period. Conservatisms in the calculation include the following

• The calculation uses a 21T daily temperature range between the maximum and i minimum temperatures for the day in determining the transmission heat transfer

through the exterior walls and roof. On July 14,1954, when the maximum

outdoor air temperature in Springfield was 1127, the daily low temperature l was 787 which gives a 34*F daily range. Due to the thermal mass of the concrete walls and roof a 34T daily temperature range would increase the

transmission heat loss to the outdoors above that used in the calculation. This j would reduce the net cooling load in the room and the resulting room

temperature.

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= The calculation does not consider thermal heat sinks within the room which

would reduce the net cooling load in the room and resulting room temperature.

• The calculation assumes that the air temperature in adjacent interior areas is 4

constant over the 24-hour period. The temperatures in these areas will vary as the outside air temperature varies over the same time period. This would increase the amount of transmission heat loss through the interior walls and floor and reduce the net cooling load in the room and re#ng room temperature.

In addition to the above, an additional conservatism providing probable margin in the calculation is the lack of credit for stratification of room air.

Esisting Analysis 1

S&L calculation IP-M-0448 is a heat balance with the diesel generator room modeled as essentially a single node. This is the calculation that determined the outside air temperature limits of 102.77 for the Division 1 diesel generator room, and 104T for the Division 2 and Division 3 diesel generator rooms. It includes a ,

volume of air based on room dimensions. It has outputs of air flow and heat '

transmission through building materials of the ceiling, the floor, the south exterior wall, the north interior wall which includes a roll up door, and the east and west interior walls which in some cases are common with other hot diesel generator rooms. The room is about 23 feet high inside. The room temperatures calculated are bulk temperatures of the total volume of room air at steady at steady state.

08/01/97 13:23 CPS *L1 CENSING

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1 It is reasonable to assume that in a 23 ft. high room there is some stratification. If there is stratification, the top of the room will be hotter than the bottom. The mid l

point of the room is 11.5 feet above the floor. Panel-mounted sensitive electrical l equipment is below the midpoint. Most of the engine mounted equipment is below I midpoint. The turbo charger, however, is high on the engme and may be close to the 11.5 ft level but it is designed for exposure to exhaust gases. Use ofbulk room temperatures as equipment rating temperatures in this case is conservative.

Ongoing Analysis IP has contracted ENERCON to model the diesel generator rooms with a computer code that allows nodalization of the room itself. The EPRI code, l' Gothic, is being used for this calculation. This is intended to define the temperature profile of the room and quantify some of that margin. The exhaust from the rooms is at the ceiling,23 ft. above the floor, at the north and of the rooms. W inlet ducts to the rooms run parallel to the diesels along the walls and discharge horizontally toward the engines at an elevation about 15 ft. above the floor. The cool air falls toward the hot engine, is heated, rises, and is exhausted at the ceiling. This is basically good HVAC design. This information will be nodalized in the rooms. The location of the heat loads within the rooms will also be nodalized.

IP expects some degree of success using this approach to further evaluate the impact that higher outside air temperature has on equipment performance.

(3) Describe the ongoing actions of Sargent & Lundy to increase the current )

temperature limits of the diesel generator rooms. Include anticipated schedules.

IP Response l IP and Sargent and Lundy are working together to re-evaluate the temperature

. limits associated with the diesel generator rooms and their associated cooling systems. Significant progress has been made to demonstrate the operability of equipment or components in the DG rooms with room temperatures greater than 1307. The current calculation provides that an inside bulk room temperature of 130T results from an outside air temperature of 102.7T for Div. I and 104T for Div. II and Div. III. The present calculation provides a peak room temperature of 139.9T and a duration of 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> above 1307 based upon a July maximum temperature of 1127 in Springfield, IL.

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i l Equipment located in the DG rooms does not require environmental quali6 cation.

j The area is considered mild, and therefore, requirements of 10CFR50.49, j " Environmental Quali$ cation of Electric Equipment Important to Safety for 4

Nuclear Power Plants," do not apply. Nevartheless, a review was performed to

demonstrate the operability of equipment at 1407 (ambient room temperature) for j a marinum period of12 hours.

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j Originally, the equipment was procured to meet IP's initial design condition of

! 122T (50*C) ambient temperature (which was later evaluated and increased to 130T as pn d ine the USAR). In the case of ambient room temperature l reaching 1407 (based on the July maximum ambient temperature of 112T), and

, using 1227 as a reference point, the resultant increase in the peak temperature

! relative to 1227 is about 187 (-10*C). This peak temperature would exist for

only a few hours (a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />).

i The effect of this IST increase on equipment can be characterized relative to the

"10*C rule" that has been used in the industry where aging information was not j available. The rule provides a quick approximation.and it says for every 10*C rise

! in the ambient temperature at which equipment is p-*ad ot operate j continuously, equipment life can be reduced by one-half This rule provides

! reasonable assurance that the equipment design life will not be affected i signi6cantly by a maximum of 10*C increase in the room temperature for a short l period. (

Reference:

EPRIReportTR100516)

Additionally, based on IP's experience in the qualification of materista for harsh environment, it is also Ip's engineeringjudgment that the components that are designed for a continuous operating temperature of 122T will not have their materials-damaging threshold within the 10*C range. 'In general, design temperature does not imply the equipment will not function at higher than design operating temperature, it merely provides the continuous operating temperature for the equipment.

To further substantiate the above ensinooring judgment,'a detailed review of the equipment is in progress for its thermal aging information, vendor supplied design operating temperature range and the criticality of components for the operation of DGs. Based on IP's review of the available thermal aging data contained in quali6 cation binders and the vendor supplied information so far, the equipment has either been designed or thermally aged for significantly higher temperatures (at least 158T). IP recognizes the temperature for components inside panels may also change due to the ambient temperature change, however the margin between the postulated ambient and the design or aging temperatures of the components is judged significant enough to envelope this. Some of the components have also been eliminated from Anther review heam they do not impact the operability of the D Os.

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Page 6 of 8 j l

l Equipment lists were taken from the qualification binders that contain all applicable  ;

electrical and mehanical components. To verify the completeness of this list, it '

was compared with the equipment list included in the vendor manuals for the diesel generators. To increase confidence and to insure that all equipment located in the room was identi6cd, a walkdown of the DG rooms was performed by the IP staff on July 30,1997. The walkdown identified some additional components (safety and non-safety) from different systems. These components are included in our evaluation. ,

I The equipment review effort is continuing for the remaining components, and is being conducted jointly by IP staff and environmental qualification engineers from Sargent &Ixndy. I Based on the above information, IP has reasonable assurance that the contents of the DG rooms will remain operable if ever there was a maximum of 10*C ambient temperature rise in the room above original continuous operational rating. I l

(4) Explain contingency plans to ensure that electrical power is available as temperatures are predicted to approach limits. This should not include shutting down the plant with inoperable diesels and questionable offsite circuits. l l

IP Response As noted in the cover letter, successful re-evaluation of the temperature limits associated with the diesel generator rooms eliminates the potential for high temperatures to affect diesel generator operability due to any limitations on roorn cooling capability. The postulated condition of"minming down the plant with inoperable diesels And questionable offsite circuits"is thus extremely unlikely. On I this basis, with respect to the onsite power sources (the diesel generators), no contingency plans for forecasted high temperatures will be required.

! With respect to the offsite sources, contingency plans for maintaining offsite circuit l voltages as high as possible have been addressed in previous IP correspondence to the NRC. This is further addressed in IP's response to Item (6) below. '

(5) Describe actions to supplement diesel room cooling (e.g., temporary fans, i propping doors open, opening cabinet doors, etc.).

1 IP Response Consistent with the above response [for Item (4)], successful re-evaluation of the current, conservative temperature limits associated with diesel generator rooms and associated cooling subsystems resolves the concern for high temperatures potentially making th diesel generators inoperable. Therefore, no actions to supplement diesel r 4m cooling are anticipated.

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Page 7 of 8 (6) Describe those conditions when industrial customers will be dropped to ensure suf5cient offsite voltage is available on the offsite circuits. As temperatures approach limits and diesel operability comes into question, the staffwill need assurance that offsite sources will be available.

IP Resoonse This item is addressed in the cover letter (page 3).

(7) Discuss plant-wide implications offailure of Westinghouse 4-kV breaker. The Westinghouse breakers in the plant may need more comprehensive testing to ensure their reliability.

IP Response As noted in the cover letter, IP has addressed the Westinghouse 4-kV breaker failure event in a separate letter (IP letter U-602803 to A. Bill Beach dated August 1, 1997).

(8) Supplement the letter of July 23,1997, describing ahgnment between the 138 and 345-kV lines. The staffis concerned about the potential of error in switching power between the 138 and 345-kV sources. Discuss how often switching is predicted to occur and describe how it will be minimind.

IP ResDOng In its letter of July 23,1997, IP described the fact that the reserve auxiliary transformer (RAT) and the associated 345-kV system is nonnally regarded as the more robust source relative to the emergency reserve auxiliary transformer (ERAT) and the associated 138 kV system. IP acknowledges that in light of the current 345-kV voltage situation, IP's philosophy will be to have safety-related loads aligned to the ERAT. IP further noted, however, that "ifvoltage is not expected to be below the minimum required level for an extended period of time (e.g., weekends or a period oflow-load weekdays, such as would occur during cooler weather) the safety-related loads may be aligned to the RAT."

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Page 8 of 8 In light of the NRC's increased concern about transferring loads and the recent breaker failure event, IP wishes to emphasize that plant loads will normally be aligned to the ERAT during the period that the exemption is in effect. Loads will be transferred to the RAT when required to perform surveillance testing.

Otherwise, IP will consider transferring loads to the RAT only when it appears that the summer has sufficiently passed such that predicted voltage on the RAT is expected to remain above the maximum level required for CPS. Thus, besides transfers required for surveillance testing or maintenance, the intent is to perform only a single transfer ofloads from the ERAT to RAT late in the efective period for the exemption. In total, IP estimates the number of transfers to be less than or equal to four per month.

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Enclosure 1 DRAFT

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! LOCAL CLIMATOLOGICAL DATA

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08/01/97 13:26 CPS *LICENSlHG -* LIC PROJECT NGR ,

NO.391 D14

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08/01/97 13:27 CPS

• LICENSING -* LIC PROJECT MGR NO.391 D15 i

i DRAFT =

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1 LOCAL CLIMATOLOGICAL DATA 9

WITH OOMPARATIVE DATA i

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BPRINOFIELD, ILLINOIS I

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08/01/97 13:28 CPS $ LICENSING

• LIC PROJECT f1GR NO.391 D17 DRAFT - - >

Page1 d

Review of Atmospheric Data

. Attachment 1: Graph provides daily mean and maximum temperatures I between years 1961-1990, 30 years.

Attachment 2: Provides daily maximum temperature curves for the months- . l of June, July, August and September for the years 1930 to 1995. These l temperatures are for Soringfield, Illinols. Each page represents 10 years of i data for the four months identified above. Following is the summary of the data:

Month Maximum Number of Temperature Occurrences in  !

last 65 years -

i June 104 F, 3

July 112 F, 1 j

August 108 F '2 September 101 F 1 All temperatures and their frequencies are given below for the months of June, July, August, & September:

1 MONTH MONTH MONTH MONTH

$ 7 8 9

Tenne. Frequency Te m Proeuenov Terrup. "T zi Tem '===.

l 96 26 96 Se se 40 . 96 15 97 26 97 48 97 21 97 9 98 18 98 29 08 25 06 6 i<

90 14 90 24 99 18 to 6 100 14 100 21 100 13 100 a

]

101 5 101 15 101 11 101. 1

! 102 8 102 9 102 4 102 0 103 2 103 6 103 4 103 0

- 104 3 104 8 104 '2 104 0 106 0 105 4 106 0 105 0 J j

106 0 100 7 106 't 106 0 107 0 107 2 107 0 107 0 108 0 108 2 108 *2 toe 0 10e 0 10e 0 10e 0 toe 0 l 110 0 110 1 110 0 110 0 1 111 0 tii 0 111 0 111 0

, 112 0 112 1 112 0 112 0 ,

More O ML we O More O More 0 j i

• Note: Review of data shows these values were recorded in 1930's and j have not been repeated. The footnote (b) of page 2 of 1956 Local Climatological Data indicates extremes prior to 1948 were at different location and are not listed and carried by NOAA.

,I

OEV01/97 13:28 CPS

• LICENSING

• LIC PROJECT T1GR NO.391 D18 )

~

DRAFT c

1 i

a Attachment 3: Provides 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> tamperature variance for typical hot days. '

l

! Peak occurs in month of July at approximately 3 PM. Peak temperature stays for a few hours and then the temperature drops. A typical swing in ,

temperature over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period is 20 F to 34 F. j 1

Attachment 4: Compares Decatur temperature for month of August {

in last 10 years with CPS temperature. Days at or above 100 F in Decatur l l were identified over the last 10 years. The CPS temperature on these days '

were looked at. Only one day CPS exceeded 100 F when Decatur temperature was greater than or equal to 100 F.

Attachment 5: Provides last three years of temperature trend data. It indicates temperature never exceeded 100 F at CPS between 1995 and 1997. This data was taken at 10M meteorological t'ower.

References:

1. The National Oceanic Atmospheric Administration (NOAA)-CRIES Climate Diagnostics Center (htt://www.cdc.noaa. gov /).

2. Local Climatological Data, Springfield ,1956 l

1 i

1 I

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084167 13:29 CPS

• LICENSING

• LI,C PROJECT MGR No.391 pig r DRAFT  :=

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• LICENSING

• LIC PROJECT MGR NO.391 D21

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• LIC PROJECT MGR NO.391 D22 i .

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• LICENSING

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j 08/01/97 13:31 CPS

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• LIC PROJECT MGR NO.391 D25 4

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Hourty outakle AirTemperatures 1 At 8ptingflekt IEinois j

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day 3 10 11 12 is is i 82.0 7 8.15 81.0 80.8 Sn.1 80.0 78JD 83.0 78.0 82.0 j

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Note: The intemstlonal Station Meteorolo0 lost 00msts St TT.ary indlestes that i entreme deUy high temperature >=103 occurred in Jun 1954. July 1984 Au8ust 1984, and July 1966 i I i I I i

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084147 13:33 CPS

• LICENSING

• LIC PROJECT t13R NO.391 D28

~

~

DRAFT

• l I l ATTACHMENT FOUR Decatur Maximum Temperature for Month of Aunust for Last 10 Yaars

! Days When Temperature exceeded 100 P 1 l

l Date Decatur Springfleid CPS l 8/1/87 100 99 92.6 l 8/2/87 100 100 93.4 8/8/88 100 98 98.2 1 8/16/88 100 99 98.8 8/16/88 105 102 103 8/17/88 104 101 99.2 8/18/88 100 100 99.9 l

Ref: Decatur - Midwest Climate Center of the Illinois State Geological Survey Springfield NOAA ,- Intemational Station Meteorological Climate Summary CPS- Met. Tower Data at 10M. l l l l l

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! 08/01 6/ 13:33 CPS

• LICENSING

• LIC PROJECT MGR r

NO.391 929 e b DRAFT. '

i ., Enclosure 3 1

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j OEV01/97 13:34 CPS

• LICENSING -* LIC PROJECT MGR NO.391 930

+

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• LICENSING

• LIC PROJECT MGR NO.391 D31 ,

J.

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08/01/97 13:37 CPS

• LICENSING + LIC PROJECT MGR NO.391 D32

. Enclosure 4 DRAFT

~ " "

Plot of System Load, Temperature at Clinton Power Station and Transmission Voltages - July 14,1997 l

The attached plot is a printout of video trend data from Illinois Power's Energy Supply Center ( electric dispatch center ). The time line plot reads right to left I and begins at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> July 14,1997. Illinois Power's system load increases until about 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> (2 p.m.) and then decreases. The local temperature at l

I Clinton Power station is hand plotted from recorded data taken from the plants I meteorological tower,10 meter temperature sensors. Transmission voltages from the 345kV and 138kV system are also plotted.  ;

l (The heavy vertical lines at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> are caused from the translation from the video screen to paper.)

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08/01/97 13:37 CPS

• LICENSING -* LIC PROJECT t1GR HO.391 D33 4

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08/01/97 14:22 CPS *l ICENSING

• LTC PROJECT F1GR NO.394 D01 DRAFT l

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I Appendix to U-602804 Marked-up Pages of the Clinton Power Station Operating License  !

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_ _ _ _ _ . _ . _ _ _ _ _ . . _ ._ _ .. _ .__ _ . _ .___ _.__._ _ _._ _ _ __ _. _ _ _ _ _ _ _ _ _ _ .m

) 08/01/97- 14 22 CPS *L1CENS1NG -* LIC PRDJECT NGR NO.394 D02 b s*>

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Appendix to U-602804 I NS b be,g g g -

Page 2 of 6 1% vidsk Wer C*d.'*wly *=' If l

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- 3, l (4) IP. pursuant to the Act and 10 CFR Parts 30. 40. and 70. to i receive, possess, and use at any time any byproduct source and

! special nuclear material as, sealed neutron sourses for reactor .

i startup, sealed sources for reactor instrumentation and radi-j atton monitoring equipment calibration, and as fission detectors -

in amounts as required; ..

I (5) IP. pursuant to the Act and 10 CFR Parts 30, 40. and 70, to receive, possess, and use in amounts as required any byproduct.

source or special nuclear material without restriction to chemical or physical form. for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) IP pursuant to the Act and 30 CFR Parts 30, 40, and 70. to possess. but not separate, such byproduct and special nucilear materials as any be produced by the operation of the facility.

, C. This license shall be deemed to contain and is subject to the condi-tions specified in the Commission's regulations act forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and j to the rules, regulations and orders of the Commission now or here- a

. after in effect; and is subject to the additional conditions specified

- or incorporated below

(1) Maximum Power Level ,

IP is authorized to operate the facility at reactor core power levels not in excess of 2894 megawatts thermal (100 percent rated power) in a,ccordance with the conditions specified herein.

The items identified in Attachment 1 to this license shall be .

. completed as specified. Attachment 1 is hereby incorporated .

into this license.

I j (2) Technical Specifications and Environmental Protection Plan L

The Technical Specifications contained in Appendix A and the i Environmental Protection Plan contained in Appendix 8. both of which are attached hereto, are hereby incorporated into this license. IP shall operate the facility in accordance with the Technical Specifications and the Environmental protection Plan. .

(3) Antitrust Conditions -

IP shall comply with the antitrust conditions in Appendix C attached hereto which is hereby incorporated into this license.

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(.4) Control System Failures (Section 7.7.3.1. SER and SSER 6)*

i' IP.shall submit, in accordance with commitments contained in letters dated May 15. 1986 and July 16, 1986, the results of .

the additional evaluations of control systes failsres and the j proposed implementation of any corrective actions that may be i found necessary. for staff review four months prior to plant startup after the first refueling outage. Ieplementation of

any corrective actions found acceptable by the staff shall be

] . completed prior to plant startup after the first refueling outage.

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(S) New Fuel Storace (Section 9.1.1. _$ER. $$ER 6 and SSER 7)

IP shall store new fuel assemblies in accordance with the requirements specified in Attachment 2. Attachment 2 is hereby j

incorporated into this license.

(6) Plant Operation Experience (Section 13.1.2.1. SSER 5)

! IP shall have a licensed senior operator on each shift who has j

had at least 6 months of hot operating experience on a large

! connercial SWR including at least 6 weeks at power levels J greater than 20. percent of full power, and who has had SWR startup and shutdown experience. This license condition shall be effective for a period of 1 year from fuel load or until the ,

attainment of a nominal 100 percent power level, whichever j occurs later.

(7) E'meroency Plannino (Section 13.3. $$tR 6) i In the event the NRC staff finds that the lack'of progress in i completion of the procedures in the Federal Emergency Management j Agency's final rule, 44 CFR Part 350, is an indication that a

! major substantive problem exists in achieving or maintaining l en adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.

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! *The parenthetical notation following the title of many license conditions i denotes the section of the Safety Evaluation Report and/or its supplements

! wherein the license condition is discussed.

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• LICENSING -+ L1,C PROJECT MGR NO.394 D04 3 47 a I Appendix to U-602804 Page 4 of 6  ;

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(8) Post-Fuel leadina Initial Test Proeram fe=etion 14. SER. SSER 5 and ISER_6)

Any changes to the initial test program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59

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shall be reported in accordance with 50.59(b) within one month of such change.

(9) F==r::cer Resnante rma=hi' itios 'fC acric Letter 82-33. SaaE

.t I to NJREG-0737. Section 9 U.S. . $$ER 5 and SHER 8. and Sect < on 18.

SER. SSER S and Safety Rvaluation Dated Anri' 17. 1987)

a. IP in accordance with the commitment contained in a letter dated December 11, 1986, shall install and have operational separate power sources for each of the fuel zone. level channels as provided for in Regulatory Guide 1.97 prior to startup following the first refueling outage.

b. IP shall submit a detailed control room design' final supple-mental summary report within 90 days of issuance of the full

/N5f/tT 8 power license that completes all the remaining items identified in Section 18.3 of the Safety Evaluation dated April 17, 1987.

D. The facility requires exemptions from certain' requirements of 10 CFR l Part 50 and 10 CFR Part 70. These include:' (a) an exemption from the  ;

requirements of 10 CFR 70.24 for the criticality alaru monitors around  !

the fuel-storage area; (b) an exemption from the requirement of 10 CFR l Part 50, Appendix J - Option 8, paragraph III.8,' exempting the measured j leakage rates from the main steam isolation valves from inclusion in the ,

ined leak rate for local leak rate tests (Section 6.2.6 of SSER 6); a (c) an exemption from the requirements of paragraph III.8 of Option 10 CFR Part 50, Appendix J, exempting leakage from the valve l

packing and the body-to-bonnet seal of valva 1E51-F374 associated with containment penetration IMC-44 from inclusion in the combined leakage rate for penetrations and valves subject to Type 8 and C tests (SER supporting Amendment 62 to Facility Operating License No. NPF special circumstances regarding each exemption; except for Item (a) above, are identified .in the referenced section of the safety evaluation report and the supplements thereto.

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08/01/97 14:24 CPS

• LICENSING + LIC PROJECT NGR HO.394 DOS DRAFT l Appendix to U-602804 Page 5 of 6 Insert A

and (d) a temporary partial exemption from the requirements of 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 17 to allow plant operation with one offsite electrical power circuit that does not strictly conform to the capacity and capability requirements of GDC 17 due to voltage concerns addressed in IP Letter U-602796 dated July 22,1997, effective from the date ofissuance up to and including October 15,1997 (SER supporting Amendment 115 to Facility Operating license No. NPF-62)

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l l l (10) ONt* Ele _rical Power Source Val *a=* (Safety Eva6adon D=+=d >=w .

122 3 In accordance with the commitment established in Illinois Power (IP) letters U-602796 and U-602804 (respectively dated July 22 and August 1,1997) to support a partial exemption from the requirements of 10CFR50 Appendix A, General Design Criterion 17 concerning the two required offsite electrical power sources for Clinton Power Station (CPS),IP aball, in the event,that voltage on the 138-kV system decreases or is predicted to decrease below the minimum required for CPS concurrent with less-than-required voltage on the 345-kV system during Modes 1,2, and 3, take whatever actions are m== y, including reducing load, to maintain or restore voltage on the 138-kV system such that it meets the capability and capacity requirements for CPS as required by GDC 17. This license condition is effective upon approval of the exemption to GDC 17 through and including October 15,1997.

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