ML17250A481

Amend 34 to License DPR-18,adding Limiting Conditions for Operation & Fuel Handling & Revising Surveillance Requirements for Spent Fuel Sys

ML17250A481
Person / Time
Site:	Ginna
Issue date:	07/14/1980
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
Shared Package
ML17250A482	List: ML17250A481 ML17250A483 ML17250A487
References
NUDOCS 8008060217
Download: ML17250A481 (26)

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e UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 l

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ROCHESTER GAS ANO ELECTRIC CORPORATION I

DOCKET NO. 50-244 R.

E.

GINNA NUCLEAR POMER PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.

34'icense No.

DPR-18 1.

The Nuclear Regulatory Cormission (the comission) has found that:

A.

The application for amendment by Rochester Gas and Electric Company (the licensee) dated January 24, 1977 (transmitted by letter dated February 1, 1977),

as superseded by submittals dated July 28, 1978 (transmitted by letter dated August 10, 1978),

and May 8, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter !;

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the COIIission; C.

There is reasonable assurance (i ) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in cocqliance with the COInnission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the COIIIIission's regulations and all applicable requirements have been satisfied.

,Soosooo e,l7

l 2.

Accordingly, the license is amended by changes to the Techg/caI Specifications as indicated in the attachment to this lichenfe amendment and Paragraph 2.C(2) of Provisional Operating Licekse Ka~-.1.8-is hereby amended to read as follows:

"(2)

Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amondment No. 34, are hereby incorporated in the license-The licensee shall operate the facility in accordance with the Technical Specifications."

3.

This license amendment is effective as of the date of its issuance.

FOR THE'UCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 14, 1980 Dennis i1. Crutchfield, Chi Operating Reactors Branch 85 Division of Licensing

ATTACHMENT TO LICENSE AMENDMENT NO. 34 PROVISIONAL OPERATING LICENSE NO.

DPR-18 DOCKET NO. 50-244 Remove the following pages of the Appendix "A" Technical Specifications and insert the enclosed pages.

The revised pages contain the captioned amendment number and vertical lines indicating the areas of change.

REMOVE

3. 3-4 3.3-5 3.3-6 3.3-7 3.3-11 3.3-12 3-11-2 3.1 1-4 4.5-4 4.5-5 4.5-7 4.11-1

4. 11-2 INSERT 3.3-4 3.3-5 3.3-6 3'~7 303 7a 3.3-11 3.3-12 3.11-2

3. 11-4

4. 5-4

4. 5-5 4.5-5a 4.5-5b 4.5-7 4.5-7a 4.11-1

4. 11-2

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(ii) The two reactor coolant d=ain taafc pumps-shall be tested and the'r operability demon-strated prio" to 'nit't'ng repairs of the inope able es'dual hea" removal pump.

d.

One residual hea" exchanger may be out of service for a period of no more than 24 hou s.

e.

Any valve re@@i ed fo the functioning of the sa ety inject'on or res'ual heat removal systems may be inoperable prov'ed repairs are completed wn 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Prior to initiating repairs, all valves in the systems that prov'e the duplicate function shall be tested to demonstra e ope ability.

3+3 e

e3 f.

Power may be restored to any valve referenced in 3.3.1.1 g for the purposes o

valve test'ng provid'ng no more than one such valve has power res ored and prov'ded test'ng is complet d and power removed w'hin '2 hou"s.

"-xcept dur'ng diesel generator load and sa=eg ard sea'eence tes-'ng or when the vessel head 's removed or the steam generator manway is open no more than one safety 'njection pump shall be ope"able whenever the temperature of one or more o

the RCS cold legs Ls

< 330'=-.

3.3.1.3.1 3.3.2 3.3.2.1 Whenever only one safety injection pumo may be operable by 3.3.1.3 at least two of the.hree safety injection pumps shall be demonstrated inoperable a

minimum of once per twelve hours by verifying that the control switches are in the pull-stop position.

Containment Coolinc and Iodine Remova The reactor shall no" be made cr'tical except or low tempera ure physics tests, unless the following condi-tions are met:

a.

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The spray add':

ve tank contains Tho less 4500 gallons o= solu"'on wi='". a sodium hyd"ox de concen""at on of no-less man 30;; bv we'ht.

At leas two containment s" ay pumps are operable.

Four fan cooler units are operable.

Amendment No. ~ g$,

34 A

4

~ 4

d.

At least two charcoal filter units are operable.

e.

All valves and piping associated with the above components which are required to function during accident conditions are operable.

f.

At least two HEPA filter units with demisters are operable.

3.3.2.2 During power operation, the requirements of 3.3.2.1 may be modi ied to allow one of the following components to be inoperable at any one time.

If the system is not restored to meet the requirements of 3.3.2.1 within the time period specified, the reactor shall be placed in the hot shutdown condition.

If the requirements of 3.3.2.1 are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor sha3.1 be placed in the cold shutdown condition.

One fan cooler may be out of service for a period of no more than 7 days.

b.

One containment spray pump may be out of service provided the pump is restored to operable status within 3 days.

The remaining containment spray pump shall be tested to demonstrate operability c

before initiating maintenance on the inoperable pump.

Any valve in the system, required to function during accident conditions, may be inoperable provided repairs are completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Prior to initiating repairs, a3.1 valves in the system that provide the duplicate function shall be tested to demonstrate operability.

Amendment No.

34 3.3-5

E

C.

One post accident charcoal f'lter unit may be ou of service orovided the unit is restored to ooerable status within 7 days and provided the two containment sprav pumos are demonst ated to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and daily thereafter.

The two containment spray oumps shall be tested to demonstrate operability be-fore initiating maintenance on the inoperable charcoal unit.

e.

The spray additive system may be out of service for a period of no more than 3 days.

3.3

~ 3 Component Coo linc 8 stem 3.3.3.1 The reactor shall not be made critical unless the fol-lowing conditions are met:

a.

At least two component cooling oumps are operable.

b.

At least two component cool'ng heat exchangers a

e 3.3 '

operable.

c.

All valves, interlocks and o'ping associated with the above components which are recruired to urct'n durinc accident conditions are operable.

During power operation, the recuirements o

3.3.3.1 may be modi ied to allow one of the following components to be irooerable at'ny one time.

I the system 's not restored to meet the cond'ions of 3.3.3.1 within the time period soec'"'ed, the reactor shall be placed Amendment No.

34 3.3-6

in the hot shutdown condition.

If the reauirements of 3.3.3.1 are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, 3.3.4 3.3.4.1 the reactor shall be placed in the cold shutdown condi-t'n.

a.

One component cooling pump may be out of service provided the pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

One heat exchanger or other passive component may be out of service provided the system may still operate at 100% capac'v and repairs are completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Service Water System The reactor shall not be made crit'al unless the ol-lowing conditions are met:

a.

At least two service wate-pumps and one loop header are operable.

3.3.4.2 b.

A' valves, interlocks, and piping associated w'h the operation o

two pumps are operable.

Any time that the conditions of 3.3.4.1 above cannot be met, the reactor shall be placed in the cold shutdown 3.3.5 3.3.5.1 condition.

Control Room Emergency Air Treatment System The reactor shall not be made critical unless.the cont ol room emergency air treatment system is operable.

3 c 3 7

Amendment No. 34

3.3. 5.2 During power operation, the recruirements of 3. 3.5. i mav be modif'ed to allow the control room emergencv air treatment svstem to be inoperable for a period of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Zf the system is not made operable within those 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in hot shut-down condition utilizing normal operating procedures.

Basis:

The normal procedure "or starting the reactor 's, first to heat the 3+3 7a Amendment No. 34

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dundancy for certain ranges of break sizes. (2)

The containment cooling and iodine removal functions are provided by two independent systems:

(a) fan-coolers plus post accident charcoal filters and (b) containment spray with sodium hydroxide addition.

During normal power operation, only two of the four fan-coolers are required to remove heat lost from equipment and piping within conta'nment.

In the event of a Design Basis (3)

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Accident, any one of the fol'owing will serve to reduce airborne iodine activity and ma'ntain doses within the values calculated in the PS':

(l) two containment spray pumps and sodium hydroxide

addition, (2) two fan-coolers and two post accident charcoal filters, or (3) one containment spray pump and sodium hydroxide addition plus one fan-cooler and one post accident charcoal filter.

In addition, the conta'nment integrity analysis (4) assumes that one containment spray pump and two fan-coolers oper-ate to reduce containment pressure following a Design Basis (9)

Accident.

Because of the difficulty of access to make repairs to a fan-cooler and because of the low probability of a Design Basis Accident during that time, an additional seven days opera-tion with an inoperable fan-cooler is permitted.

The containment spray pumps and spray additive system are located outside con-tainment and are, therefore, less diff'cult to repair.

There-fore, three days with an inoperable containment spray pump or spray additive system is deemed acceptable.

The Component Cooling Svstem is di ferent from the other systems discussed above in that the components are so located in the Auxiliary Building as to be accessible for repair after a loss-o -coolant accident.

In addition, if during the post-accident (5) phase the component cooling water supply is lost, core and contain-ment cooling could be maintained 3.3-ll Ameridment. No. 34

until repairs wer effected.(

0 The facility has four service water pumps.

Only one is needed

,during the inject'on phase, and two are reauired during the re-'ircula ion phase of a postulated loss-of-coolant accident. (8)

The cont ol room emergency ai" treatment system is designed to filter the control room atmosphere during periods when the control oom is isolated and to maintain rad'ation levels in the control room at acceptable levels ollowing the Design Basis (9)

Accident.

Reactor operation may cont'nue "for a limited time while repa'rs are heing made to the a'r treatment svstem since it is unlikely that the system would be neeced.

The 1'm' for the accumulator pressure and volume assure the re-quired amount of water injection during an accident, and are based on values used for the accident analyses.

The indicated level of 50% corresponds to 1108 cubic feet of water in the accumulator and the indicated level of 82% corrresponds to 1134 cubic eet.

The limitation of no more than one safety injection pump to be operable and the surveillance eguirement to ver'y that two safety injection pumps are inoperable below 330'F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

References (1)

FSAR Sect'on 9.3 (2)

FSAR Section 6.2 (3)

FSAR Section 6.3 (4)

FSAR Section 14.3.5 (5)

FSAR Section 1.2 (6)

FSAR Section 9.3 (7)

FSAR Section 14.3 (8)

FSAR Section 9.4 (9)

FSAR Section 14.3.5 3.3-12 Amendment No.

7>

28>>

34

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e.

Charcoal adsorbers shall be installed in the venti-lation svstem exhaust from the spent fuel storage pit area and shall be operable.

E!adiation levels in the spent fuel storage area shall be monitored continuously.

The trolley of tne auxiliary building crane shall never be stationed or permitted to pass over storage racks eon-taining spent fuel.

Fuel assemblies with less than 60 days since irradiation shal'ot be placed in storage pos'ions with less spacing between them than that indicated in Figure 3.11-1 by the cesignation RDF.

Change No. 8, Anendment No. ilA, 34 3.11-2

facility.

The roughing filter protects the adsorber from becoming fouled with dirt; the adsorber r emoves iodine, the isotope of highes" rad'ological s'gnificance, resulting from a fuel handling accident.

The effectiveness of charcoal for removing iodine is assured by hav'ng a high throughput and a high removal efficiency.

The throughput is attained by operation of the exhaust fans.

The high removal e

ic'encv is attained by minimizing the amount oc iodine that bypasses he charcoal and having charcoal with a high potential for removing the iodine that does pass through the char-coal.

The ainirmne spacing specified for fuel assenhlies with less than 60 days decay is based on maintaining the pot.,tial release of fission products that could occur should an object fall on and damage stored fuel to less than that which could have occurred with fuel stored in the original fuel storage racRs.

Amendment No. 77, 34 3.11-4

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o the spray additive valves closed, each valve will be opened and closed by operator action.

This test shall be performed prior to startup if the time since the last test exceeds one month.

4.5.2.3 4.5.2.3.1 c.

The accumulator check valves shall be checked for operability during each refueling shutdown.

Air Filtration System At least once every 18 months or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal filtrat'on system operation since the last test, or following painting, fire or chemical release in anv ven-tilation zone communicating with the system, the post accident charcoal system shall have the following cond'ions demonstrated The pressure drop across the charcoal adsorber bank is b.

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less than 3 inches of water at design flow rate

(+ 10%).

In place Freon testing, under ambient cond'ions, shall show at least 99% removal.

The iodine removal efficiency of at least one charcoa'ilter cell shall be measured.

The filter cell to be tested shall be selected randomly from those cells w'th the longest in-bank residence time.

The minimum acceptable value for filter efficiency is 90% for re-moval o" methyl iodide when tested at at least 2S6'F and 95%

RH and at 1.5 to 2.0 mg/m3 loading with taggec CH3I.

Change No.

7S, Amendment No. gg, 34 4.5-4

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4.5.2.3.2 A ter each replacement of a charcoal drawer or after anv structural maintenance on the housing for the post accident charcoal

system, the condition of Specification 4.5.2.3.1.b shall be demonstrated for the a fected portion o the system.

4.5.2.3.3 At least every 18 months or following painting, fire, or chemical release-in any ventilation zone communicating with the system, the containment recirculation system shall have the fo 1lowing conditions demons trated.

a.

The pressure drop across the HEPA filter bank is less than 3 inches o

water at design flow rate

(~ 108).

b.

En place thermally generated DOP testing of the HEPA ilters shall snow at least 99% removal.

4.5.2.3.4 After each complete or partial replacement of the HEPA filter bank or afte" any structural maintenance on a housing for 4.5.2.3.5 the containment recirculation system, the condition of Spec'cation 4.5.2.3.3.b shall be demonstrated for the affected portion of the system.

Except du 'ng cold or re ueling shutdowns the post accident charcoal filter isolation valves shall be tested at interva's not g eater than one month to verify operability and proper o ientation and flow shall be maintained through the system or at least 15 m'nutes.

The test shall be performed pr'r to startup if the time since the last test exceeds 1 mon"a.

Amendment No. 5, 34 4.5-5

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4.5.2.3.6 At least once every 18 months or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal filtration system operation since the last test, or following painting, fire or chemical release in any ventilation zone communicating with the system, the control room emergency air treatment system shall have the following conditions demonstrated.

a.

The pressure drop across the combined HEPA ilte s and charcoal adsorber banks is less than 6" of water at de-sign flow rate

(+ 10%).

b.

In place Freon testing, under ambient conditions, shall show a least 99% removal.

c.

In place thermally generated DOP testing of the HEPA filters shall show at least 99K removal.

4.5.2.3.7 d..

The results of laboratory analys's on a carbon sample shall show 90% or greate" radioactive methvl iodide removal when tested at at least 125'F and 95%

RH and at 1.5 to 2.0 mg/m3 loading w'h tagged CH3I.

After each complete or partial replacement of the HEPA filter bank or after any structural maintenance on the HEPA nousing for the control room emergency air treatment

system, the con-dition of Specification 4.5.2.3.6.c shall be demonstrated for 4.5.2.3.8 the af"ected portion of the system.

After each replacement of a cha coal drawer or after anv structural maintenance on the charcoal housing or the control room emergency air treatment

system, the cond'tion o

Speci-ficat'on 4.5.2.3.6.b shall be demonstrated or the affected portion of the system.

Amendment No.

34 4.5-5a

4.5.2.3.9 Except during cold or refueling shutdowns the automatic init'ation of the control room emergency air treatment system shall be tested at intervals not to exceed one month to ver'y operabilitv and proper orientation and flow shall be maintained through the system for at least l5 minutes.

The test shall be performed prior to startup if the time since the last test exceeds one month.

Basis:

The Safetv Zn-'ection System and the Co..t inment Spray System are princip l plant sa=egua"ds that are no ).ally inoper t've dur'rg reactor operation.

Comple e systems tests canrot be perzormed wnen the reactor is operatirg because Safetv Znjection signal causes'on-tair ment isolation and a Containment Spray System test r-quires the system to be temporarily disabled.

The 'me hod oz assur'ng operability of these systems herezore to com-bire svstems tests to be performed during annual plart shut-downs, w'th more reauent component tests, which can be performed dur'g reac oz'peration.

The annual systems t sts demons rate proper autcm tic operation of the Safety Znjection and Co..tainment Spray S% stems

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Ninth the pumps blocked zom starting, a test signal is applied to ini 'ate automatic action Amendment No.

34 4.5-5b

The air filtration portion of the containment air recirculation system is a passive safeguard which 's isolated from the cooling air flow during normal reactor operation.

Hence the charcoal should have a long useful lifetime.

The filter frames that house the charcoal are stainless steel and should also last indefinitely.

The pressure drop, filter efficiency, and valve operation test fre-quencies will assure that the svstem can operate. to meet i"s desicn function under accident conditions.

As the adsorbing charcoal is normally isolated, the test schedule, related to hours of operation as well as elapsed time, will assure that it does not degrade below the required adsorbtion efficiency.

The test condit'ons for charcoal sample adsorbing e ficiencv are those which might be encountered under an accident situation. (2)

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ll The control room air treatment system is designed to filter the control room atmosphere (recirculation and intake air) during control room isolation Conditions.

HZPA filters are installed be-fore the charcoal filters to remove -particulate matt r and prevent clogging of the iodine adsorbers.

The charcoal ilters reduce the airborne radioiodine in the control room.

Bypass leakage must be at a min'mum in order for these f'ters to perform their designed function.

, Ef tne performances are as specified the calculated doses will be less than those analyzed. (3)

Retesting of the post accident charcoal system or the control room emergency air treatment system in the event of painting, fire, or chemical release is required only if the svstem is operating and is providing f'ltration for the area in which the painting, fire, or Amendment No.

34 4.5-7

chemical release occurs.

Testing of the air filtration systems will be, to the extent it can, given tne configuration of the systems, in accordance with ANSI N5l0-1975, "Testing of Nuclear Air-Cleaning Systems."

Re erences:

(l)

PSAR Section 6.2 (2)

PSAR Sect'on 6.3 (3)

PSAR Section l4.3.5 Amendment No.

34 4.5-7a

4.11 S ent Fuel Pit Charcoal Adsorber Testin A

1 icabi 1 it 4.11.1 Applies to testing the performance of the spent fuel pit charcoal adsorbers.

~5"'" '"

Within 60 days prior to each major fuel handling*, the spent fuel pit charcoal adsorber system shall have the following conditions demon-strated.

After the conditions have been demonstrated, the occurrence of painting, fire or chemical release in any ventilation zone communicating with the spent fuel pit charcoal adsorber system shall require that the following conditions be redemonstrated before major fuel handling* may continue.

a.

The total air flow rate from the charcoal adsorbers shall be at least 75% of that measured with a complete set of new adsorbers.

b.

In-place Freon testing, under ambient conditions, shall show at least 99% removal.

4. 11. 2 c.

The results of laboratory analysis on a carbon sample shall show 90% or greater radioactive methyl iodide removal when tested at at least 150 F and 95%

RH and at 1.5 to 2.0 mg/m loading with tagged CH3I.

d.

Flow shall be maintained through the system using either the filter or bypass flow path for at least 15 minutes each month.

After each replacement of a charcoal filter drawer or after any structural maintenance on the charcoal housing for the spent fuel pit charcoal adsorber

system, the condition of Specification 4.11.1.b shall be demonstrated for the affected portion of the system.

Major fuel handling is considered as removal of 20% or more of the fuel assemblies from the reactor vessel.

Amendment No.

34 4.11-1

Basis The measurement of the air flow assures that air is being withdrawn from the spent fuel pit area and passed through the adsorbers.

The zlow is measured prior to employing the adsorbers to establish that tnere has been no gross change in performance since the system was last used.

The Freon test provides a measure oz the amount o

leakage from around the charcoal adsorbent.

The ability of charcoal to adsorb iodine can deteriorate as the charcoal ages and weathers.

Testing the capacity of the charcoal to adsorb iodine assures that an acceptable removal efficiency under operating conditions would be obtained.

The difzerence between the tes" recuirement of a removal efficiency of 90% for methyl iodine and the percentage assumed in the evaluation of the fuel handling accident provides adequate sa ety margin for degradat'on of the filter after the tests.

Retesting of the spent fuel p't charcoal adsorber system in the event of painting, fire, or chemical release is requi ed only iz the system is operating and is providing filtration for the area 'n which the painting, fire, or chemical release occurs.

Testing of the air filtration systems will be tested, to the extent it can given the configuration of the systems, in accordance with ANSI N510-1975, "Testing of Nuclear Air-Cleaning Systems".

Refe ence:

(1)

Letter "rom E.J.

Nelson, Rochester Cas and Electric Corporat'n to Dr. Peter A. Morris, U.S. Atomic Energy Commission, dated February 3,

1971 Amendment No. 34

4. 11-2

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