ML20247A686
| ML20247A686 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/22/1989 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20247A641 | List: |
| References | |
| NUDOCS 8903290169 | |
| Download: ML20247A686 (8) | |
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. ATTACHMENT I TO JPN-89-010 1
s PROPOSED TMpHNICAL SPECIFICATION CHANGES l
REGARDING MAINTENANCE OF FILLED DISCKARGE PIPE IN ECCS AND RCIC SYSTEMS (JPTS-86-022) i l
New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59' 8903290169 890322 PDR ADOCK 05000333 p
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'l ATTACHMENT II TO JPN-89-010 J
i l
I SAFETY EVALUATION FOR THE PROPOSED TECHNICAL SPECIFICATION CHANGE REGARDING MAINTENANCE OF FILLED DISCHARGE PIPE IN l
ECCS AND RCIC SYSTEMS (JPTS-86-022)
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New York Power Authority JAMES A.
FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 i
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I SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING MAINTENANCE OF FILLED DISCHARGE PIPE IN ECCS AND RCIC SYSTEMS-(JPTB-86-022).
I.
DESCRIPTION OF THE PROPOSED CHANGES The proposed changes'to the James A.'FitzPatrick Technical Specifications revise Technical Specifications.3.5.G and 4.5.G on.page 123.
The changes are as follows:
Pace 123; Section 3.5.G.a Replace the phrase " purposes satisfying" with " purposes of' satisfying".
Pace 123; Section 4.5.G.2.
Replace the phrase " required to be operable" with " maintained in a filled condition"; change the word " inoperable" to "affected";
and replace the phrase " prior to the return of the system to' service" with "of the system and water flow observed".
The revised Surveillance Requirement 4.5.G.2'should read:
Following any period when the LPCI subsystems or core spray subsystems have not been maintained in a filled condition; the discharge piping of the affected subsystem shall be j
vented from the high point of the system and water flow.
observed.
Pace 123; Section 4.5.G'.3.
J Delete the phr6ses " Core Spray System"-and " Core Spray".
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The revised Surveillance Requirement.4.5.G.3 should read:
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Whenever the HPCI or RCIC System is lined up to take suction from the condensate storage tank, the discharge pipings of 4
the HPCI or RCIC shall be vented from the high point of the system, and water flow observed on a monthly basis.
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PageL2 of 5 II. PURPOSE OF THE PROPOSED CHANGES These Technical Specification changes correct minor editorial errors and clarify the requirements for maintaining the discharge piping of the'ECCS and RCIC Systems full of water, j
The reasoning for each change is as follows:
Section-3.5.G.a:
Minor wording change to correct an error in l
grammar.
Section 4.5.G.2:
Literal application of the present specification would require venting of. Core Spray and LPCI l
subsystems following.any period during which they.were declared j
These subsystems can be made inoperable, without l
draining the discharge piping, for the purposes of performing-maintenance and testing activities (e.g. maintenance of valve operators).
The intent of Technical Specification 3.5.G is to require the discharge piping to be kept full of water to assure system operability.
Therefore, the wording of Surveillance Requirement.4.5.G.2 is revised to require vent and fill operations after the piping
.has not been maintained in a filled condition; rather than the
. existing wording which requires vent and fill operations after periods of subsystem inoperability.
1 Section 4.5.G.3:
Specification 3.5.A requires the Core Spray System to be operable whenever irradiated fuel is in the rgactor vessel and reactor coolant temperature is' greater than 212 F.
Specification 3.5.G
" Maintenance of Filled Discharge Pipe",
is applicable whenever the Core Spray System is required tc be operable; thus, a water filled Core Spray System is a condition for operability.
Surveillance Requirement 4.5.G.3 requires venting the Core Spray System whenever the suction piping is aligned to the condensate storage tank.
Alignment to the condensate storage tank is not L
considered an operable condition since the accident analyses assume suction supply from the suppression pool.
Consequently, the wording of Surveillance Requirement 4.5.G.3 ~is revised to eliminate reference to aligning the Core Spray System to the condensate storage tank.
This change reduces the potential for misinterpreting an operable Core Spray flow path and improves the consistency between Technical Specifications.
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-III.. IMPACT OF THE PROPOSED CHANGES The proposed Technical Specification changes correct minor editorial errors and clarify thefrequirements for maintaining the discharge piping of the ECCS and RCIC Systems full of water.
The impact of each proposed change is as follows:-
Section'3.5.G.a:. This change does not impact: safety systems;.
nor does it decrease the existing level 1of" safety as defined in the plant's Final Safety Analysis Report (FSAR).
It is purely
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administrative in nature.
Section.4.5.G.2:
The intent of Technical Specification 3.5.G
'is to assure that the discharge piping lof the-Core Spray,ELPCI, RCIC,.and HPCI. subsystems are maintained water' solid; thus, providing. cooling water.at the' earliest moment and precluding the potential for water hammer transients.
Surveillance Requirement 4.5.G' ensures.that the affected piping is full.by specifying periodic, vent and fill operations and by requiring surveillance of the high point level switches, which provide direct indication of the discharge pipe's full status.
The j
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proposed change still requires that the piping be maintained
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water solid, as well as minimizing unnecessary. venting and.
filling of the discharge piping of the' Core Spray.and LPCI j
subsystems.
Section 4.5.G.3:
The proposed change eliminates reference to an alignment of the Core Spray System which would render it inoperable;fthat is, suction supply from the condensate storage tank. This change improves the consistency within the Technical Specifications for Core Spray System alignment with a suction supply flow path from the suppression pool.
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The condensate storage tank can be used as a suction supply
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to the Core Spray System during cold shutdown conditions with 4
the torus drained pursuant to.the requirements of' Technical Specification 3.5.F.2.
Protection against water hammer is provided in this mode by procedural controls, which require venting and keeping the discharge pipe full of water whenever the Core Spray, suction supply is changed from the suppression pool to the condensate storage tank.
Each of the proposed changes are purely administrative They clarify the intent of the Technical Specifications, improve the consistency within..the Technical Specifications, or correct editorial and grammatical errors.
The proposed changes do not involve' modification of any existing equipment, systems, or components; nor do they change any administrative controls or limitations imposed on existing plant equipment.
The changes l
do not alter the conclusions of the plant's accident analyses or radiological release analyses as documented in the FSAR (Reference 1) or the NRC Staff's SER (Reference 2).
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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.
The basis for concluding that a significant hazards consideration does not exist for each of the proposed changes to i
the Technical Specifications is as follows:
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- 1. The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The change to Specification 3.5.G.a is purely administrative.
The clarification of Specification 4.5.G.2 retains the existing functional requirements to maintain the discharge piping of the ECCS and RCIC Systems filled with water.
The revision to Specification 4.5.G.3 eliminates a reference to an alignment of the Core Spray System which would render it inoperable.
The proposed changes do not involve modification of any existing equipment, systems, or components; nor do they change any administrative controls or limitations imposed on existing plant equipment.
The changes do not alter the conclusions
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of the plant's accident analyses or radiological release analyses as documented in the FSAR or the NRC Staff's SER.
2.
The proposed changes do not create the possibility of a new or different kind of accident from any accident previously j
evaluated.
They merely correct editorial and grammatical errors, clarify the intent of the Surveillance Requirements, j
and improve the consistency of Technical Specifications.
1 They do not involve modification to any of the plant's j
systems, equipment, or components; nor do they place the
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plant in an ananalyzed configuration.
These changes are of an adminis&c tive t mure.
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The change to specification 3.5.G.a is purely administrative, and as such, does not involve a significant reduction in the margin of safety.
The other proposed changes affect the Core Spray and LPCI Systems.
These systems are the primary source j
of emergency core cooling after the reactor is depressurized and for flooding of the core after a postulated accident.
Revised Specification 4.5.G.2 still requires that the discharge piping of the ECCS and RCIC Systems be maintained water solid; thus, the system response times for providing L
emergency cooling water are not impacted and the potential j
for a water hammer transient is still precluded.
Revised Specification 4.5.G.3 eliminates a reference to an inoperable alignment of the Core Spray System; thus, providing additional assurance that the Core Spray System's suction supply is from the torus as assumed in the plant's accident analyses.
The proposed changes do not involve modification to any of the plant's systems, equipment, or components.
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IV. IMPLEMENTATION OF THE PROPOSED CHANGE Implementation of the proposed changes will not impact the ALARA or Fire Protection Programs at FitzPatrick, nor will the changes impact the' environment.
'1 V. _C_ONCLUSION The change, as proposed, does not constitute an unreviewed safety question as defined in 10 CFR 50.59.
That is, it:
- a. 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;
- b. will not increase the possibility of an accident or malfunction of a'different type'from any_previously evaluated in the Safety Analysis Report; 1
- c. will not reduce the margin of safety as defined'in the basis for any technical specification
- d. does not constitute an unreviewed safety; question; and i
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involves no significant hazards consideration, as defined in 10 CFR 50.92.
I VI. REFERENCES
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- 1. James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, Sections 6 and 14.
2.
James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER), dated November 20, 1972, and Supplements.
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