ML20073D802

Proposed Tech Spec Changes Re Environ Encls

ML20073D802
Person / Time
Site:	FitzPatrick
Issue date:	04/19/1991
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20073D798	List: JPN-91-016, Forwards Application for Amend to License DPR-59,changing Tech Specs to Incorporate Sections 3.11.F & 4.11.F Re Operability Requirements for HVAC Equipment Associated W/ Four Environ Encls Installed in Electrical Load Ctrs ML20073D799 ML20073D802
References
NUDOCS 9104290227
Download: ML20073D802 (10)

Text

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ATTACHMENT I TO JPN 91016 PROPOSED TECHNICAL SPECIFICA110N CHANGES REGARDING ENVIRONMENTAL ENCLOSURES (JPTS-86-00j2 i

New York Power Authority - j on?KS A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50 333 DPR ,

.9104290227 910419 PDR .ADOCK 05000333 P PDR

i JAFNPP TABLE OF CONTENTS (Cont'd)

P_agg D. Emergency Sorvice Water System D. 240 E. Intake Deicing Heators E. 242 F. Environmental Enclosuro Ventilation and Cooling (HVAC) F. 242 3.12 Fire Protection Systems 4.12 244a A. High Pressure Water Fire Protection System A. 244a B. Water Spray and Sprinkler Systems B. 2440 C. Carbon Dioxide Systems C. 2440 D. Manual Fire Hose Stations D. 244f E. Fire Protection Systems Smoke and Heat Detectors E. 244g F. Fire Barrier Ponotration Seals F. 244g 5.0 Design Features 245 5.1 Sito 245 5.2 Reactor 245 5.3 Reactor Pressuto Vosso! 245 5.4 Containment 245 5.5 Fuel Storago 245 5.6 Solsmic Dosign 246 6.0 Admin lstrativo Controls 247 6.1 Responsibility 247 6.2 Organization 247 6.2.1 Facility Management and Technical Support 247 6.2.2 Plant Staff 247a 6.3 Plant Staff Qualifications 248 6.4 Rotraining and Replacement Training 248 6.5 Review and Audit 248 6.5.1 Plant Operating Review Committoo (PORC) 248a 6.5.2 Safety Roview Committee (SRC) 250 6.6 Reportablo Event Action 253 6.7 Saloty Limit Violation 253 6.8 Proceduros 253 6.9 Reporting Roquirements .

254a 6.10 Record Retontion 254g 6.11 Radiation Protection Program 255 6.12 Industrial Security Program 250 6.13 Emergoney Plan 258 6.14 Firo Protection Program 258 6.15 Environmental Qualification 258a Amendment No. $,;d,94,91,96, it0,130, W/,

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JAFHPP -

3.11 (cont'd) 4.11 (cont'd)

E. Intake Deicing Heaters E. Intake Deicing Heaters intake heaters are required to be operable when intake water temperature is less than or equal to 37'F. A minimum of 18 out .

MM ed %

of 88 heaters are required to be operable to maintain the e e i m m e's W W m

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required flow for the ESW and RH.RSW Systems. ,

2. The individual heaters shall be monitored once/6 months

1. If specification 3.11.E above cannot be met, the reactor for rated heater cun ent or as required by large deviations <

shall be placed in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. in the feeder checks in 3.11.E.1 above.

3. Resistance to ground shall be checked once/ year.

F. Environmental Enclosure Ventilation and Cooling (HVAC)

F. MM heVdh W Mm (HVAQ At least one HVAC unit for each environmental enclosure shall be Environmental enclosure HVAC units shall be checked for operable wherever the reactor ,s i in the run, startup/ hot standby, 7

or hot shutdown mode.

1. When it is determined that both HVAC units for any

1. When .it is

. determined that both HVAC units for one environmental enclosure are inopeidsle, the HVAC units environmental enclosure are inoperable, restore one HVAC f rh of the WNd hes shMI M unit for the affected environmental enclosure to an checked for operability once/ day to ensure that at least operaNe status y,Mn 7 days.

one HVAC unit per envirm minifital enclosure is operable.

2. When it is determined that both HVAC units for more than one envire u i rental enclosure are inoperable, restore HVAC 1 holi Mf m asiental enclosure HVAC M Wed m/Wng cycle.

units as neem such that no more than one environmental enclosure has both HVAC units inoperable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3. If Specification 3.11.F.1 or 3.11.F.2 above cannot be met, place the reactor in the cold shutdcmn or refuel mode within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Amendment No. }i!4, prf, 242

JAFNPP -

3.11 and 4.11 BASES (cont'd)

E. Intake Deicing Heaters The general objective of this specification is to ensure adequate ons pm Muons e Wm endswereiW sm hefwe,h hesWAC & m M water (30,000 gpm Ref. FSAR O2.1) is available to the ESW and RHRSW systems to fulfill the cooling requirements of the Wmd to M operWe in h opeahg d.

associated ECCS toads. Since it is required that an opening Should both of the HVAC units for one envire areental enclosure large enough to satisfy the demand (10% of the total area) be become inoperable, continued operability of the redundant LPCI preserved, it is justifiable to assume that no more than 20% of MOV IPS charger-inverter or 600 VAC bus is assured by the the heaters be available at anytime. continued operability of the other envi> O uriental enclosure's A even days am M for @rs toyestom at The weekly check of 6 heater feeder ammeters shall be made to prove that the system is supplying adequate heat to the bar me N rh MC Wo an ww status.

racks. If a major dW.ation from rated current is detected, heater Should both HVAC units beurne inoperable for more than one breakers can be checked to see if they have tripped or the environrnenta! enclosure,24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are allowed for repairs.

individual heaters can be tested for open circuits. Repair of at least one HVAC unit per envh e armuid enclosure The semiannual check of each heater will verify that the weeldy mes M WiminenW he to an opee Wh tests have been adequate. The annusi check of circuit meggar s2 h W ,@ me e a M h e readings will check against long term degradation of circuit emunues to W M WAC & We,operaton of tM ,

plant may continue for the balance of the 7-day period permitted "l by Specification 3.11.F.1.

F. Environmental Enclosure Ventilation and Cooling (HVAC) __

, gg g Envirs u nental enclosures, each with two redundant 100% operation once each week when the reactor is in tM run, capacity HVAC units, are installed around the two LPCI motor startup/ hot standby, or hot shutdown mode. An operabirity operated valve independent power supply (WCl MOV IPS) check consists of venfying that the HVAC system pressures, charger-inverters and around two 600 VAC busses (load centers temperatures, and fan operation on both the cooling coils and L-15 and L-16). The operability requirements for the the condenser coils are performing normally. Operabirrty checks environmental enclosure HVAC units ensure the operabirity of are performed once a day on operable HVAC units when both the charger-inverters and 600 VAC busses by providing a HVAC units for one or more envire a nectal enclosures are controlled mild enviro ureent under normal, high energy line inoperable to provide greater assurance that the remaining break, and post-LOCA conditions. The enclosures also provide HVAC units are funcioning nQn Giy.

radiation shielding. During time periods when the reactor is in the cold shutdown or refuel modes, the low reactor pressure and Calibration of the control instrumentation (HVAC system temperatum pressure and terrwdure indicators and switches) once each operating cycle ensures that the HVAC units are operating within their design rimrts.

Amendment No.

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l ATTACHMENT ll TO JPN 91416 i SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING ENVIRONMENTAL ENCLOSURES (JPTS-86402) i

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i l l 1 New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT ,

Docket No. 50-333 DPR-59 l

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, Attachment ll SAFETY EVALUATION Page 1 of 5

1. DESCRIPTION OF THE PROPOSED CHANGES The proposed change to the James A. FitzPatrick Technical Specifications adds two new specifications,3.11.F and 4.11.F. Bases for these specifications, and a corresponding entry in the Table of Contents. This amendment would change pages 111,242, and 244. A minor administrative change is also being made to page 111. The changes are described below.

Pageill Table of Contents ,

Add an now line entry to reflect Specifications 3.11.F and 4.11.F.

• Environmental Enclosure Ventilation and Cooling (HVAC)* on page 242.

In the entries for Emergency Service Water System and intake Delcing Heatero add a *D.*

and *E.* respectively in the surveillance requirements column to note existing specifications 4.11.D and E. l Page 242 Add new specification 3.11.F to read:

F. Environmental Enclosure Ventilation and Cooling (HVAC)

At least one HVAC unit for each environmental enclosure shall be operable whenever the reactor le in the run, startup/ hot standby, or hot shutdown mode.

1. When it is determined that both HVAC units for one environmental enclosure are Inoperable, restore one HVAC unit for the affected environmental enclosure to an operable t'.atus within 7 days, i

2. When it is determined that both HVAC units for more than one environmental  !

enclosure are Inoperable, restore HVAC units as necessary such that no more

' than one environmental enclosure has both HVAC units inoperable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3. If Specification 3.11.F.1 or 3.11.F.2 above cannot be mot, place the reactor in the cold shutdown or refuel mode within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Page 242. Add new specification 4.11.F to read:

F. Environmental Enclosure Ventilation and Cooling (HVAC)  !

Environmental enclosure HVAC units shall be checked for operability once/ week.

1.- When it is determined that both HVAC units for any environmental enclosure -

.are Inoperable, the HVAC units for the remainder of the environmental A

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. Attachment ll l SAFETY EVALUATION Page 2 of 5 4

i enclosures shall be checked for operability once/ day to ensure that at least one HVAC unit per environmental enclosure is operable.

2. Control instrumentation for environmental enclosure HVAC units shall be calibrated once/ operating cycle.

Page 244 Bases for Specifications 3.11 and 4.11 Basos are added discussing the safety function of the environmental enclosures and Justification for the proposed Technical Specifications. The complete text of the proposed Basos is contained in Attachment 1 ,

ll. PURPOSE OF THE PROPOSED CHANGES A description of the four environmental enclosures and the operation of their HVAC systems Is presented in Section 9.9.3.3 of the Updated FitzPatrick FSAR (Reference 1, pagos 9.9 6 and 9.9 7). Their location is shown on FSAR Figure 12.3 3 for the 600 VAC load centers, and on Figure 12.3 5 for the LPCI charger / inverters. The enclosures maintain a mild operating environment for the enclosed safety related electrical equipment ,

during routine and accident conditions. The mild environment will be maintalnod for all 4

postulated reactor building amblent conditions by operation of the enclosures' ventilation and air conditioning (HVAC) units.  ;

The proposed changes will ensure the operability of the safety related electrical equipment i contained within the environmental enclosures by specifying operability and testing s l requiromonts for the HVAC units associated with the enclosures. -

i 111. IMPACT OF THE PROPOSED CHANGES Documentation is not available to show that the equipment IIstod below is qualified to IEEE 323 and 10 CFH 50.49 for harsh environmental conditions.

1. LPCI Uninterruptable Power Supply Charger / Inverter System 'A"(*B"),71 INV 3A(B) 7

2. 600 VAC Emergency Power Switchgear Substation . Division 1(II),11500(11600), "

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Enclosures, each having two 100% capacity'HVAC units, were constructed around this t equipmont to provide sufficient cooling and radiation shielding to maintain a mild

- operating environment during both normal and post accident conditions. The HVAC units -

aro OA Category I and have environmental and seismic qualification for continuous operation under the Operating Basis Earthquake and limiting high-energy line break (HELB), ,

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. Attachment il SAFETY EVALUATION Page 3 of 5 When any of thoso electrical compononts is onorgizod, it gonoratos heat. This heat must be removed from the enclosure to maintain a normal operating temperaturo. This heat can be removed by oporation of olthor one of the onclosuro's two 100% capacity HVAC systems or by having a door to tho onclosure blocked opon and providing forced circulation of the reactor building air into the onclosure. However, when the reactor is in other than cold condition (hot shutdown, startup/ hot standby, or run modos) the doors to cach onclosure are closed to protect the equipment from postulated post accident (HELB or LOCA) environmental conditions. Thoroforo, the proposed technical specifications require at least ono HVAC unit for each onclosure to bo operable whenover the reactor Is in any of the modos listed above.

Should both HVAC units for an onclosuro 60 unavailable, adoquato heat romova! can be '

maintainod by opening the access door as described above. The equipmont insido the onclosuro would romain operablo. Howevor, In the highly unlikoly event of an accidont (HELB or LOCA), this equipmont would be vulnerable to the high temperaturo and/or radiation conditions which may exist in the reactor building. Thorofore, only 7 days is ellowod for rostoration. This providos adequate timo to allow repairs to an inoperablo HVAC system while minimizing the probability of exposure to a postulated accident.

During this timo, rodundant cloctrical equipment within the operablo onclosuro romains fully protected and is available under post accident conditions. This 7 day LCO period is cMsistont with the LCO period for ECCS systems with a single train out of servico, if both HVAC units for more than one enclosuro are inoperablo, insufficient electrical equipment remains fully protected against the environmental offects of an accident. Sinco this may result in redundant ECCS equipmont becoming unavailable to mitigate the accident, a much shorter,24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO porlod is appropriato.

The environmental offects in the reactor building of HELB and LOCA accidents depend on the pressure and temporaturo conditions of the reactor coolant system and not the rcactor power lovol. Thorofore, should insufficient HVAC systems be restored in the specified time, the action statomont roquires the reactor to be placed in cold shutdown or refuel modo. An additional 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> porlod is allowed to bring the reactor quickly to the cold condition under normal shutdown procedural control.

The proposed surveillanco roqu!romonts are adequate to ensure continuous oporability of the HVAC systems. Should both HVAC systems for an onclosuro be Inoporable, daily operability chocks of all other HVAC systems would ensure that rodundant equipmont would to available under post accident conditions.

The heat rejected from the HVAC units to the reactor building also has boon analyzod. The additionat heat load on the reactor building cooling system is well within its design capability and has an insignificant offect on both normal and post accident ambient building temperaturos.

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SAFETY EVALUATION Page 4 of 5 IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Operation of the FitzPatrick plant in accordance with the proposed Amendment would not involve a significant hazards consideration as stated in 10 CFR 50.92 since it would not:

1. Involve a significant increase in the probability or consequences of an accident ,

previously evaluated. The proposed technical specifications add operability and I surveillance requirements to ventilation and air conditioning equipment associated with four environmental enclosures within the reactor building. These structures ensure the availability of the enclosed safety related electrical equipment under l postulated accident conditions. No accidents as analyzed in the FSAR are affected by these changes, i

2. create the possibility of a new or different kind of accident from any accident _

previously evaluated. The enclosures and their associated HVAC units can not initiate any type of reactor transient. No postulated failure mode or combination of failures of the HVAC systems can initiate an accident.

3. Involve a significant reduction in a margin of safety. The proposed changes maintain ,

all existing margins of safety by ensuring the availability of safety related equipment under accident conditions.

In the April 6,1983 FEDERAL REGISTER (48FR14870), the NRC published examples of license amendments that are not likely to involve significant hazards considerations. ,

Example number (ii) of that list is applicable to this proposed change and states:

"A change that constitutes an additional limitation, restriction, or control not

, presently included in the technical specifications: for example, a more stringent surveillance requirement."

i V. IMPL EMENTATION OF THE PROPOSED CHANGE implementation of the proposed changes will not affect the ALARA or Fire Protection -

Programs at FitzPatrick, nor will the changes impact the environment.

VI. CONCLUSION The change, as proposed, does not constitute an unreviewed safety question as defined in 10 CFR 50.59. That is, it:

1. will not change the probability nor the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the Safety Analysis' ,

Report; 1

2. will not increase the possibility of an accident or malfunction of a different type from any previously evaluated in the Safety Analysis Report;

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3. will not reduce the margin of safety as defined in the basis for any technical specification;

4. does not constitute an unreview4d safety question; and

5. Involves no significant hazards consideration, as defined in 10 CFR 50.92.

Vll. REFERENCES

1. James A. RtzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, (FSAR Section 9.9).  ;

2. James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER),

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